373
ASME SECTION XI VALVE TEST PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D. C. COOK NUCLEAR POWER STATION UNIT NO 2 Revision No: 3 Date: 2-5-90 TABLE OF CONTENTS l. INTRODUCTION (FIGURE - l) 2. LIST OF DRAWINGS (FIGURE 2) 3. NOMENCLATURE FOR TEST METHODS (FIGURE 3) 4. RELIEF REQUEST/COLD SHUTDOWN JUSTIFICATION NOTES 5. ATTACHMENT-A 6. VALVE SUMMARY SHEETS 7. FLOW DIAGRAMS 9003090183 9002ih PDR ADQCN, 050003i5 P PNU page l of Sl

Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

  • Upload
    others

  • View
    0

  • Download
    0

Embed Size (px)

Citation preview

Page 1: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

ASME SECTION XI VALVE TEST PR

2ND TEN YEAR INSPECTION INTERVAL

FOR THE D. C. COOK NUCLEAR POWER STATION UNIT NO 2

Revision No: 3

Date: 2-5-90

TABLE OF CONTENTS

l. INTRODUCTION — (FIGURE - l)2. LIST OF DRAWINGS — (FIGURE — 2)

3. NOMENCLATURE FOR TEST METHODS — (FIGURE — 3)

4. RELIEF REQUEST/COLD SHUTDOWN JUSTIFICATION NOTES

5. ATTACHMENT-A

6. VALVE SUMMARY SHEETS

7. FLOW DIAGRAMS

9003090183 9002ihPDR ADQCN, 050003i5P PNU

page l of Sl

Page 2: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

ASME SECTION XI VALVE TEST-PR

2ND TEN YEAR INSPECTION INTERVAL

FOR THE D. C. COOK NUCLEAR POWER STATION UNIT NO. 2

Revision No: 3 Figure — 1

Date: 2-5-90

INTRODUCTION

Valve Testin Pro ram

A'- The valve test program shall be conducted in accordance withSubsection IWV of Section XI of the 1983 edition of the ASME Boilerand Pressure Vessel Code through Summer 1983 Addenda, except forspecific relief requests which are identified in the Valve SummarySheet.

B. The valve test program is applicable for the second 10 yearinspection interval which commences on July 1, 1986.

C. The valve test program was developed employing the classificationguidelines contained in 10 CFR 50.2(v) for Quality Group A andRegulatory Guide 1.26, — Revision 3 for Quality Groups B and C.(Quality Group A is the same as ASME Class 1, Group B is 2, andGroup C is 3). NRC staff guidance was provided by memorandum datedJanuary 16, 1978.

D- Figure 2 identifies the system flow diagrams which were used todevelop this valve test program.

,Valve Summary Sheets contain the following:* E''* Flow Dia ram: Unit Number — Flow diagram number — Revision Number

(e.g., 2-5105B-42)

* Valve Number: Unique valve number (e.g., 2-DCR-310)

Page 2 of 81

Page 3: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

D. C. Cook Nuclear Plant

Revision No: 3

Date: 2-5-90

Valve Test Program

Figure — l

* Revision Number: Any change of valve description, function or testrequirement.

* ~ B ~

W'EL-

CKBFGAGLDA3WNDAGBLVB

Relief and SafetyCheckButterflyGateGlobeDiaphragmThree-WayNeedleAngleBallVacuum Breaker (Reverse Check Valve)

* Valve Size: Nominal valve size in inches

* Valve Actuator T e: Type of actuator, one of the following:

SA — Self Actuated (e.g., CK or REL)MO - Motor OperatedA — Air OperatedM — ManualPO — PneumaticSO - Solenoid Operated

* Flow Dia ram Coordinates: Alpha/Numeric grid location of valve

Page 3 of Sl

Page 4: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 5: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Revision No: 3

D. C. Cook Nuclear Plan

Valve Test Program

Figure — lDate: 2-5-90

* Valve osition during normal plant operation or during performance ofits safety function, one of the following:

0C0/C

OpenClosedOpen/Closed or vice versa

* Code Class: ASME Code class of valve, either l, 2, or 3

* Valve Status-A P: Active or passive

w vdefined in IWV-2200

NOTE: Combinations are possible (e.g., AC)

Prima Test Re 'd: Test required per Section XI

* Test Performed: Testing that will be performed

NOTE: Test nomenclature is explained in Figure 3

* Test Mode Test Fre enc : One of the following:

P - Every 3 months while system is required to be operable.C - Testing will be performed at cold shutdown frequency

(See Note <(Fn)R — Testing will be performed at refueling outage frequency.

Page 4 of 8l

Page 6: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

D. C. Cook Nuclear Plan

Valve Test Program

Revision No: 3

Date: 2-5-90

Figure — 1

* Code Relief: Whether or not a code relief is being requested; willbe one of the following:

NONO, NOTE X

NO, CSZ Y

YES, NOTE Z

Valve is to be tested per code, no comments.Valve is to be tested per code, but there arecomments.Valve is to be tested per code at a cold shutdownfrequency with cold shutdown justification providedin notes.Code relief is requested. Alternate testing isproposed in lieu of that required by code, the noteexplains why the code relief is requested.

E. Alternative testing performed on' check valve in accordance withGL-89-04, Attachment 1, Item g2 is indicated under relief requestnotes. This testing is performed in lieu of stroke testingrequired by Section XI, IWV-3521. This is accomplished bydisassembly method in the following manner:

Disassembl Method The valve bonnet is removed, the disc is-manually full stroke exercised and the valve internals are visuallyexamined. The results of this examination are documented. Thiswill be performed on a refueling outage frequency. The valvegroupings for sample disassembly is in accordance with GL-89-04.This alternative testing to be performed for a particular valve isindicated on the valve summary sheets and relief request notes.

Page 5 of 81

Page 7: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

D. C. Cook Nuclear Plan

Valve Test Program

= Revision No: 3

Date: 2-5-90

Figure — 1

F. Schedulin of Valve Testin at Cold Shutdown Fre enc . Valvestested at a cold shutdown frequency shall be scheduled using thefollowing criteria:

2 ~

3.

4 ~

Valve exercising need not be done more often than once every 3months in case of frequent cold shutdowns.

The testing shall commence as soon as the cold shutdowncondition is achieved, but not later than 48 hours aftershutdown, and continue until complete or the plant is ready toreturn to power.

Completion of all valve testing is not a prerequisite toreturn to power. Any testing not completed during one coldshutdown should be performed during any subsequent coldshutdowns starting from the last test performed at theprevious cold shutdown.

For planned cold shutdowns, where ample time is available andtesting all the valves identified for the cold shutdown testfrequency in the IST Program will be accomplished, exceptionsto the 48 hours commencement of testing is allowed.

G. The following criteria have been used in developing limiting valuesof full-stroke time for the power operated valves:

0

0

o

Review of valve's design specification and/or manufacturer'stest stroke timesReview of system response time requirements (TechnicalSpecification, FSAR, etc.)Valve's historical stroke time values at various systemconditions

Page 6 of 81

Page 8: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

D. C. Cook Nuclear Plant

Revision No: 3

Valve Test Program

Figure — 1

Date: 2-5-90

Using the above criteria, the limiting stroke time for each valveis derived as follows:

1. Nominal Valve Stroke Time < 2 Seconds*

HistoricalStroke Time

Ran e in Seconds

EstablishedBase Line on Curves

in Seconds

Recommended Action Time(Limiting Stroke Time

Values in Seconds

Base Line Time x 2 + 1Second=Recommended ActionTime or Tech..Spec. Limit,whichever is less.

up to to 1.241.25 to 1.741.75 to 2.49

1.01.52.0

= 1 x 2 + 1 = 3 Seconds= 1.5 x 2 + 1 = 4 Seconds= 2 x 2 + 1 = 5 Seconds

2. Nominal Valve Stroke Time — 3.0 to 10.0 Seconds

2.5 to 10.49 3 to 10 Base Line Time x 1.5 =Action Time

3. Nominal Valve Stroke Time — 11.0 Seconds and U

10.5 and Up 11.0 and Up Base Line Time x 1.25 =Action Time (or 15 seconds,whichever is larger)

*Excluding those valves designated as rapid valves per Paragraph "H" notedbelow.

Page 7 of 81

Page 9: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 10: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Revision No: 3 .

D. C. Cook Nuclear Plan

Valve Test Program

Figure — 1

Date: 2-5-'0

H.

The stroke time limiting values for the power operated valves willbe controlled via plant Technical Data Book.

Stroke Time Measurements for Ra id Fast Actin Valves. Inaccordance with GL-89-04, Attachment 1, Item g6, power operatedvalves with normal stroke times of 2 seconds or less may beassigned 2 seconds limiting values. If a valve is assigned a 2second limiting value, it shall be timed only and not trended inaccordance with Section XI, IWV-3417a. If the valve exceeds 2second limit, it will be declared inoperable and corrective actionswill be taken in accordance with DlV-3417(b). The major influencein the stroke time testing of rapid acting valves is the operator'sresponse. Therefore, the timing tolerances are influenced by theoperator action and trending is not indicative of valveperformance. The valve limiting values will be documented in theplant Technical Data Book. The results of these tests will bedocumented via plant procedures.

page 8 of 81

Page 11: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

4

Page 12: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

2ND TEN YEAR INSPECTION INTERVAL OF

Revision No: 3

Date: 2-5-90

VALVE TEST PROGRAM FOR UNIT — 2

LIST OF DRAWINGS

Figure 2

NO.SYSTEM FLOW DIAGRAM NO. REVISION

Main SteamSteam Generating System

FeedwaterFeedwater (Auxiliary)Essential Service Water

Non-Essential Service Water

Station Drainage Containment

Reactor CoolantReactor Coolant

CVCS-Reactor Letdown & Charging

Component CoolingComponent CoolingComponent Cooling

Nuclear SamplingNuclear Sampling

Post Accident Sampling-Containment Hydrogen

2-5105B2-5105D

2-51062-5106A

2-5113

2-5114A

2-5124

2-51282-5128A

2-51292-5129A

2-51352-513 5A2-5135B

2-51412-5141A

2-514 1D

422

3441

36

27

20

1934

3220

343014

2730

Page 9 of 81

Page 13: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

01

Page 14: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

-Revision No: 3

Date: 2-5-90

DONALD C. COOK NUCLEAR P

2ND TEN YEAR INSPECTION INTERVAL OF

VALVE TEST PROGRAM FOR UNIT — 2

LIST OF DRAWINGS

Figure 2

SYSTEM

Emergency Core Cooling (SIS)

Emergency Core Cooling (RHR)

Containment Spray

Containment Penetration &

Weld Channel Pressurization

Ice Condenser Refrigeration

Containment VentilationControl Room VentilationEmergency Diesel Generator

Emergency Diesel Generator

Emergency Diesel Generator

Emergency Diesel Generator

Make-Up Water & Primary Water System

Compressed Air System

FLOW DIAGRAM NO.

2-5142

2-5143

2-5144

2-5145

2-5146B

2-5147A

2-5149

2-5151A

2-5151B

2-5151C

2-5151D

12-5115A

12-5120B

REVISION NO.

28

35

29

20

23

35

23

26

27

26

27

41

22

Page 10 of 81

Page 15: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

i

Page 16: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLA

2ND TEN YEAR INSPECTION INTERVAL OF

VALVE TEST PROGRAM FOR UNIT — 2

LIST OF DRAWINGS

'evisionNo: 3

Date: 2-5-90

Figure 2

SYSTEM

CVCS-Boron Makeup

Spent Fuel Pit Cooling & Clean-Up

WDS Vents & Drains

FLOW DIAGRAM NO.

12-5131

12-5136

12-5137A

REVISION NO.

19

25

21

Post Accident Liquid & Gas SamplingPost Accident Liquid Sampling Inst. Panels

12-5141C12-5141F

86

Page ll of 81

Page 17: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PNOMENCLATURE FOR TEST METHOD

USED IN COLUMNS FOR PRIMARY TEST REQUIRED ANDTEST PERFORMED UNDER ASME SECTION XI

Revision No: 3

Date: 2-5-90

Figure 3

1 CATEGORY A-B VALVESASME CODE SECTION XI

PARAGRAPH

EF-1

EF-2

EF-3

EF-4

Exercise valve (full stroke) for operability quarterly(3 months).

Exercise valve (full stroke) for operability at a cold shutdownfrequency or refueling outage frequency as indicated. Coderelief requests and/or cold shutdown justification are providedin the corresponding valve notes.

Exercise valve (part stroke) for operability quarterly;exercise (full stroke) at a cold shutdown frequency or refuelingoutage frequency as indicated. Justification for exercising thevalve at cold shutdown frequency is provided in the correspondingvalve notes. Code relief request is provided if full stroke testis deferred to coincide with refueling frequency.

Exercise valve (full stroke) for operability prior to return toservice

( IWV-3 4 1 1)

(IWV-3412)

(IWV-3412)

(IWV-3416)

EF-5

EF-6

EF-7

EF-8

Valves with remote position indicator shall be observed at leastonce every 2 years to verify that valve operation is accuratelyindicated.

This note was intentionally deleted.

Exercise valve (with fail-safe actuators) to observe failuremode quarterly.Exercise valve'with fail-safe actuators) to observe failuremode at a cold shutdown frequency or refueling frequency asindicated.

(IWV-3300)

(IWV-3415)

(IWV-3415)

Page 12 of 81

Page 18: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 19: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Revision No: 3

Date: 2-5-90

DONALD C. COOK LEAR PLANTNOMENCLATURE FOR TEST MET D USED IN COLUMNS FOR

PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI

Figure 3

(cont'd)

ET-XXX

1 CATEGORY A-B VALVESASME CODE SECTION XI

PARAGRAPH

Exercise power operated valve (full stroke) to its safety positionand measure time. The stroke time limiting values of these valves .

including rapid acting valves will be identified and controlledper plant Technical Data Book and plant procedures. Valvesassigned 2 seconds limiting values are subject to relief

specified'n

"Paragraph H, Figure 1."

2 CATEGORY C VALVES

(IWV-3413&3417)

CF-1

CF-2

CF-3

CF-4

TF-1

Exercise valve (full stroke) for operability quarterly.Exercise valve (full stroke) for operability at a cold shutdownfrequency or refueling outage frequency as indicated. Code reliefrequests and/or cold shutdown justification are provided in thecorresponding valve notes.

Exercise valve (part stroke) for operability quarterly; exercise(full stroke) for operability at a cold shutdown frecpxency orrefueling frequency as indicated. Justification for exercisingvalves at a cold shutdown frequency is provided in thecorresponding valve notes. Code relief requests are provided iffull stroke testing is deferred to coincide with refuelingfrequency.

Exercise valve (full stroke) for operability prior to return toservice.

Safety and relief valve tests (setpoint) to Section XI, TableIWV-3510-1.

(IWV-3521)

(IWV-3521)

(IWV-3522)

(IWV-3416)

(IWV-3510)

Page 13 of 81

Page 20: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PNOMENCLATURE FOR TEST METHO

USED IN COLUMNS FOR PRIMARY TEST REQUIRED ANDTEST PERFORMED UNDER ASME SECTION XI

Revision No'. 3

Date: 2-5-90

Figure 3

SLT-1

SLT-2

3 CATEGORY A or AC VALVES

Seat leakage test valve in accordance with requirements ofparagraph IWV-3420 of ASME Code, Section XI, at refueling outagefrequency but not less than once every two years.- Permissibleleakage values for each category A or AC valve are listed inAttachment — »A«.

Seat leakage test valve in accordance with 10CFR 50, Appendix J, inlieu of ASME Code Section XI except for paragraphs IWV-3426 andIWV-3427 which are applicable. This is consistent with the NRCposition described in GL-89-04, Attachment A, Item gl0.Permissible leakage values for each category A or AC valve arelisted in Attachment-»A».

SLT-2A In lieu of the requirements of ASME Code Section XI, paragraphsIWV-3423 and IWV-3424, valves are seat leakage tested as part ofthe Appendix »J» containment isolation test by imposing a statichead of water on the downstream side of the valve and verifyingthat the leakage within the specified value of Attachment »A» foreach category valve. This testing method demonstrates that thecontainment spray and RHR Check Valve leakage over 30 days islimited to the water resident in the containment spray headersdownstream of the check valves. The leakage specified would notdeplete the water inventory so as to expose these valves to apost-LOCA environment for a minimum of 30 days in the event that aspray system must be shut down and drained. This testing method isas stated in Response to Question 22.15(5) of the original FSARAppendix »Q», Amendment 81, dated August 1978.

Page 14 of 81

Page 21: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5105D-2

Revision No: 3

Date: 2-5-90

NOTE 1: FW-118-1 thru -4 Code Relief : These check valves are normallyopen during power operation to pass main feedwater flow to thesteam generators. Their safety function (close) prevents auxiliaryfeedwater backflow into the main feedwater system. These valvescannot be exercised during power operation because closing of thesevalves would require securing feedwater flow to the steamgenerators. Main feedwater to the steam generators cannot beisolated on a loop basis because three loop operation is notallowed per Donald C. Cook Nuclear Plant Technical Specification3.4.1.1. For these category "C" check valves, backflow cannot bequantified at cold shutdown due to system configuration. The onlypractical method to verify valve closure is by disassembly. Due tosize, weight and close proximity to physical barriers (whiprestraints); valve disassembly at cold shutdown would imposeconstraints on the manpower and scheduling that may delay essentialcold shutdown related activities and the plant start-up. Thevalves are not equipped with position indicators. There has beenno operational or maintenance adverse trend noted. Therefore, thevalves will be disassembled (bonnet removed) and verified closed(disc against seat) on a. sampling basis (one of- four) at refuelingoutage frequency.

Page 15 of 81

Page 22: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 23: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLAN

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5105D-2

-Revision No: 3

Date: . 2-5-90

NOTE 2:

NOTE 3:

MRV-210 -220 -230 and -240 Cold Shutdown Justification : Thesesteam generator stop valves cannot be full stroke exercised duringpower operation because this would require securing steam from asteam generator which could result in a reactor trip. Three loopoperation is not allowed for D. C. Cook per Technical Specification3.4.1.1. Valves MRV-211, -221, -231, -241, -212, -222, -232, and-242 which activate MRV-210, -220, -230, and -240 are testedquarterly in accordance with INV-3410. MRV-210, -220, -230 and-240 are part stroke tested quarterly by use of hydraulics attachedto valve operators. and full stroke tested during hot standby (Mode3 with RCS temperature > 541 F) at cold shutdown frequency.

MS-108-2 and 108-3 Code Relief : These check valves are locatedin the steam supply lines to the Auxiliary Feedwater Pump Turbine.These valves are part stroke tested during normal IST feedwaterpump testing at least on a quarterly basis at approximately 700 gpmbecause flow is restricted to a maximum of approximately 700 gpmthrough the 3" test line used during pump test. The valves will befull stroke tested to open position. at a cold shutdown frequency.The valve is not equipped with position indicator. In addition,due to the plant design, the only method available to verify thevalve closure is disassembly. The valve will be disassembled(bonnet removed) and verified closed (disc against seat) andvisually examined in accordance with GL-89-04, Attachment A, ItemN2 on a sampling basis (one of two) once every other refuelingfrequency.

Page 16 of 81

Page 24: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 25: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES.

Flow Diagram No: 2-5106-34

Revision No: 3

Date: 2-5-90

NOTE 1 0 FMO-201 -202 -203 -204 & FRV-210 -220 -230 -240 ColdShutdown Justification : The function of these valves is toprovide feedwater flow from the feedwater pumps to the steamgenerators. These valves cannot be exercised (part or full stroke)during power operation because closing these valves would requiresecuring feed flow to the steam generator which may causeinstability of steam generator water level which could result inreactor trip. Further, three loop operation is not allowed perDonald C. Cook Nuclear Plant Technical Specification 3.4.1.1.These valves will be full stroke- exercised and timed during unitstart-up or shutdown at cold shutdown frequency.

Page 17 of 81

Page 26: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR .P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5106A-41

Revision No: 3

Date: 2-5-90

NOTE 1:

NOTE 2

FW-132-1 -2 -3 -4 Cold Shutdown Justification : Theseauxilzary feedwater (AFW) check valves function to supply AFW tothe steam generators whenever the AFW System is caused to operate.These check valves cannot be full or partial stroke exercisedduring power operation without energizing the AFW System anddelivering cold water to the steam generators.. This would resultin thermal shock to the steam generator nozzles. These, valves arefull stroke exercised during startup. The valves will be verifiedclosed quarterly by monitoring temperature of Auxiliary Feed Lineas required by the plant procedure during shift inspection tours.FW-134 6 FW-135 Cold Shutdown Justification : These valves arelocated on the suction and discharge lines of the turbine drivenauxiliary feedpump. The maximum flow rate through the turbinedriven auxiliary feedpump during IST is approximately 700 gpm usingthe pump test line. Passing the design flow of 900 gpm throughthese valves would require delivering cold auxiliary feedwater tothe steam generators. This would result in thermal shock to the-steam generator nozzles. Therefore, these valves will be partstroke exercised quarterly and full stroke exercised (passingdesign flow of 900 gpm through the valves) at cold shutdownfrequency.

page 18 of 81

Page 27: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5106A-41

Revision No: 3

Date: 2-5-90

NOTE 3: FW-138-1 -2 -3 -4 Cold Shutdown Justification : Theseauxiliary feedwater (AFW) check valves function to supply AFW tothe steam generators whenever the AFW System is caused to operate.These check valves cannot be full or partial stroke exercisedduring power operation without energizing the AFW System anddelivering cold water to the steam generators. This would resultin thermal shock to the steam generator nozzles. The valves willbe verified closed quarterly by monitoring temperature of AuxiliaryFeed Line as required by the plant procedure during shiftinspection tours. These valves are full stroke exercised when theplant is returned to power after cold shutdown.

NOTE 4 FW-149 and 150 Comment : The required full stroking of thesecheck valves is satisfied when Turbine Driven Auxiliary Feedpumpcompletes its required testing.

NOTE 5: FW-153 and 160 Comment : These check valves installed on theEmergency Leak Off (ELO) lines open when the Motor Driven AuxiliaryFeedwater Pumps (MDAFP) start. This can be established when theMDAFP pump is operating through the test line. -A pressure decreasein the pump discharge line is verified by a local pressureindicator when the parallel path ELO is opened. The pressuredecrease indicates that flow is established through the ELO lineand that the check valve is opened..

Page 19 of 81-

Page 28: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5113-36

Revision No: 3

Date: 2-5-90

NOTE 1

NOTE 2:

ESW-141 -142 -143 -144 Comment;: These valves are full strokeexercised quarterly as required by IWV-3520. In addition, they aredisassembled and inspected internally in accordance with IEB 85-03at refueling outage frequency.

ESW-145 -240 -243 Cold Shutdown Justification :- These valvesare normally closed and are required to be open when the condensatestorage tank is exhausted. Exercising the valves could cause lakewater contamination of the steam generators. Lake water chemistrycan potentially impact steam generator tube integrity. Therefore,the valves will be full stroke tested at a cold shutdown frequency.Since the valves are manual, stroke timing is not required.

Page 20 of 81

Page 29: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTESr

Flow Diagram No: 2-5113-36

Revision No: 3

Date: 2-5-90

NOTE 3: WRV-722 -724 -726 -728 Code Relief : These valves are locatedin the essential service water supply lines to the emergency dieselgenerators air after coolers. These three-way valves regulatewater flow to maintain the temperature at which the after coolerair discharge thermostatic controller has been set. Water flow isregulated by passing a portion of the flow through the air coolersand bypassing the excess flow around the air after coolers. Coderelief is being requested from the testing requirements since (1),these valves function only as regulating valves and not open/closedvalves (2), these valves are demonstrated operable during dieselgenerator testing= (diesel generators are tested per TechnicalSpecification 4.8.1.1.2); and (3), these valves are demonstratedoperable during diesel generator 24 hour runs performed eachrefueling outage. The valves will be "fail-safe" tested usingtheir control scheme that will remove air from the valve operatorscausing them to direct all ESW flow to the air after coolers. Thisproposed test for each valve will be performed at refuelingfrequency. The valves cannot be stroke timed because they arethermostatic valves whose position is controlled by process fluidtemperature. There is no external control available.

Page 21 of 81

Page 30: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

II'

Page 31: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR.P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5114A-27

Revision No: 3

Date: 2-5-90

NOTE 1:= HCR-900 throu h -915 -920 throu h -935 -941 throu h 948 -951throu h -958 and 960 throu h -967 Code 'ReliefSee "Attachment-A" for permissible seat leakage values.

Page 22 of 81

Page 32: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 33: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLAN

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5124-20

Revision No: 3

Date: 2-5-90

NOTE 1: DCR-600 6 -601 and NS-357 Code Relief : See «Attachment-A« forpermissible seat leakage values.

NOTE-2: NS-357 Code Relief : This check valve is located on the return- line of the post accident sampling system inside the containment.Since the line is,open-ended inside the containment and the checkvalve is not equipped with the position indication, the valve willbe full stroke exercised in the open position by performing a flowtest quarterly and will be confirmed closed in conjunction withAppendix J seat leakage testing at refueling frequency.

Page 23 of 81

Page 34: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

'1

'I

Page 35: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5128-19

Revision No: 3

Date: 2-5-90

NOTE 1: NSO-021 -022 -023 & -024 Cold Shutdown Justification : Thesefour one-inch solenoid operated .isolation valves are installed (twoin each leg in series) in the reactor head vent. These valvescannot be tested during power operation, hot standby, or hotshutdown because the valve design is such that testing of eithervalve can cause "burping" (momentary opening) of the second valve,resulting in the release of radioactive fluid and create anairborne situation in containment. Therefore, the valves will befull stroke exercised and timed at cold shutdown frequency.

Exercising the solenoid operated valves for verification of valveposition (valve stem movement) will be performed at refuelingfrequency by a flow test through each valve because the valve stemis completely enclosed and cannot be observed. The reactor coolantdischarged during the flow testing of the valves is collected in acontainer to minimize liquid contamination. spill, radiation, andpotential airborne situation in deference of ALARA considerationand personnel protection. The above tests are consistent withTechnical Specification requirements.

Page 24 of 81

Page 36: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 37: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5128A-34

Revision No: 3

Date: 2-5-90

NOTE 1: CS-442-1 thru 4 Code Relief : These containment. isolation checkvalves are on the seal water supply line to the RC pumps. Thesevalves cannot be part or full stroke exercised to the closedposition during power operation because cooling flow is required tothe RCP seals. During cold shutdown, seal water must be maintainedto prevent backflow through the seals with possible damage fromdirt. The valves will be full stroke exercised in conjunction withAppendix J seat leakage testing at refueling frequency.

NOTE 2: GCR-301 NCR-252 NPX-151 RCR-100 & -101 CS-442-1 throu h 4SI-189 PW-275 and N-159 Code Relief : See Attachment-"A" forpermissible seat leakage values.

NOTE 3: NRV-151 -152 -153 Cold Shutdown Justification : Thesepressurizer power operated relief valves are normally closed duringpower operation. The valves cannot be exercised at power withoutinducing an RCS pressure transient which could result in reactortrip. The valves will be full stroke exercised and timed at coldshutdown frequency.

Page 25 of 81

Page 38: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5128A-34

Revision No: 3

Date: 2-5-90

NOTE 4:

NOTE 5:

PW-275 Code Relief : This containment isolation check valve islocated in the primary water supply line to the pressurizer relieftank. The valve is not equipped with position indication. Thevalve cannot be full stroke tested to closed position during poweroperation or at a cold shutdown frequency due to lack of sufficientdifferential pressure to back seat the valve. The valve andnecessary test connections are located inside the containment. Dueto the plant design, the only method available to verify the valveclosure is leak testing. The valve will be verified closed inconjunction with Appendix J seat leakage testing at refuelingfrequency.

N-159 Code Relief : This containment isolation check valve islocated in the nitrogen supply line to the pressurizer relief tank.The valve is not equipped with position indication. The valvecannot be full stroke tested to closed position during poweroperation or at a cold shutdown frequency due to lack of sufficientdifferential pressure to back seat the valve. The valve andnecessary test connections are located inside the containment. Dueto the plant design, the only method available to verify the valveclosure is leak testing. The valve will be verified closed inconjunction with Appendix J seat leakage testing at refuelingfrequency.

Page 26 of 81

Page 39: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

0

Page 40: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5128A-34

Revision No: 3

Date: 2-5-90

NOTE 6: NSO-061 -062 -063 -064 Cold Shutdown Justification : Thesefour one-inch solenoid operated isolation valves are installed (twoin each leg in series) in the pressurizer vent. These valvescannot be tested during power operation, hot standby, or hotshutdown because the valve design is such that testing of eithervalve can cause "burping" (momentary opening) of the second valveresulting in the release of radioactive fluid and create anairborne situation in containment. The valves will be full stroketested and timed at cold shutdown frequency.

Exercising the solenoid operated valves for verification of valveposition (valve stem movement) will be performed at refuelingfrequency by performing a flow test through each valve because thevalve stem is completely enclosed and cannot be observed. Thereactor coolant discharged during flow testing of the valves iscollected in a container to minimize contaminated liquid spill,radiation, and potential airborne situation in deference of.ALARAconsideration and personnel protection. The above tests areconsistent with Technical Specification recpxirements.

Page 27 of 81

Page 41: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK.—NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5128A-34

Revision No: ,3

Date: 2-5-90

NOTE 7: SI-189 Code Relief : This check valve is located in the safetyvalves discharge (Emergency Core Cooling SVs, RHR, SVs, centrifugalcharging pump SVs, etc.) collection header leading to thepressurizer relief tank. Isolating this valve for testing wouldresult in dead heading all safety valves in the above systems.This would result in loss of overpressurization protection andcould put the plant in an unsafe condition. Therefore, the valvewill be part stroke exercised to open position using externalsource via test connection at a cold shutdown frequency. The valvewill be disassembled, manually full stroke tested and visuallyexamined in accordance with GL-89-04, Attachment 1, Item g2 atevery third refueling outage frecpxency. The valve will also beverified closed in conjunction with Appendix J seat leakage testingat refueling frequency.

Page 28 of 81

Page 42: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

l,

Page 43: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5129-32

Revision No: 3

Date: 2-5-90

NOTE 1: CS-292 Code Relief : This valve is in the emergency boration pathfrom the boric acid system to the charging pump suction header.Flow through this path is normally not provided at power because of

,the resultant large negative reactivity insertion. The valve willbe full stroke exercised in the open position at a cold shutdownfrequency. The check valve is not equipped with positionindication. Due to the plant design, the only methods available toverify the valve closure is either radiography or disassembly whichwill be performed at a refueling frequency when the system is notrequired to be operable. The radiography method is an acceptablemethod to verify the valve closure (disc against the seat) under noflow condition because it provides visual observation of the valvein the closed position. The flow testing of the valve verifiesthat it is open. This provides assurance that the disc is free tomove from the open position with flow to the closed position withno flow or reverse flow.

NOTE 2: CS-299E -299W Code Relief : These check valves located on thedischarge lines of the 'E'nd 'W'harging pumps function aspressure isolation valves to protect the low pressure charging pumpsuction lines. These valves cannot be full-stroke exercisedduring: (1) power operation because the charging pumps cannotachieve maximum flow rate with the reactor at full pressure, and(2) cold shutdown because the flow required could cause a lowtemperature overpressure condition. The valves will be part-strokeexercised quarterly and full stroke exercised at refuelingfrequency. The valves will also be verified closed in conjunctionwith seat leakage testing per IWV-3420 at refueling frequency.

Page 29 of 81

Page 44: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5129-32

Revision No: 3

Date: 2-5-90

NOTE 3: CS-321 QCR-300 and -301 Code Relief : See Attachment "A" forpermissible seat leakage values.

NOTE 4: CS-321 Code Relief : This containment isolation check valve'sfunction is to supply borated water from the volume control tank tothe regenerative heat exchanger through the charging pumps forchemical shim control and reactor coolant system makeup. Isolationof this system would result in loss of control of pressurizer levelwhich could result in reactor trip. This valve is tested in theopen direction quarterly and confirmed closed in conjunction withAppendix J seat leakage testing at refueling frequency.

NOTE 5:

NOTE 6:

CS-328Ll -329Ll -328L4 -329L4 Comment : These check valvesfunction to provide the interface point between the RCS and theCVCS. Since the discharge piping of the CVCS is designed to apressure rating higher than the RCS, these valves do not perform apressure isolation function. The higher pressure (RCS) to lowpressure (CVCS Suction) isolation is accomplished by other valveswhich are tested to category "A" requirements. The valves will befull stroke exercised to open position quarterly.QCR-300 -301 Cold Shutdown Justification : These air operatedcontainment isolation valves are located on the letdown returnline. Exercising these valves during power operation would resultin letdown isolation which could result in loss of pressurizerlevel control which could result in a plant shutdown. The valveswill be full stroke exercised, timed and fail safe tested at a coldshutdown frequency and seat leakage tested per Appendix J programat refueling frequency.

Page 30 of 81

Page 45: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

Flow Diagram No:

Revision No: 3

Date: 2-5-90

RELIEF REQUEST NOTESc

2-5129-32

NOTE 7:

NOTE 8:

QMO-200 -201 Cold Shutdown Justification : These motor operatedgate valves are installed on the CVCS charging line which provideborated water for RCS chemical shim control and reactor coolantsystem makeup. Isolation of this system would result -in loss ofcontrol of pressurizer level which could result in reactor trip.The valves will be full stroke tested and .timed at cold shutdownfrequency..

QRV-200 Code Relief : This air operated valve is used to regulatecharging header flow to the reactor coolant system and seal waterflow to the reactor coolant pump seals. The valve cannot be fullstroke exercised at power operation because it would interrupt theseal injection flow to the reactor coolant pumps which could resultin reactor coolant pump seal damage. The valve will be part strokeexercised during power operation and full stroke exercised at acold shutdown frequency. The valve cannot be stroke timed becausethere is no local or remote position indicator available and cycletimes are directly proportional to "how fast" the operator turnsthe control knob. Therefore, meaningful stroke times are notachievable. This valve has no fail safe position. The alternativetesting proposed is to locally observe the valve during full stroketesting for smooth operation and apparent problems which can affectthe valve opexation.

Page 31 of 81

Page 46: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5129-32

Revision No: 3

Date: 2-5-90

NOTE 9:

NOTE 10

QRV-251 Code Relief : This air operated valve is used to regulatecharging header flow to the reactor coolant system and seal waterflow to the reactor coolant pump seals. The valve cannot be fullstroke exercised at power operation because it would interrupt the .

RCP seal injection flow and would also upset pressurizer level.The valve will be part stroke exercised during power operation andfull stroke exercised at a cold shutdown frequency. The valvecannot be stroke timed because there is no local or remote positionindicator available and cycle times are directly proportional to"how fast" the operator can turn the control knob. Therefore,meaningful stroke times are not achievable. The control scheme ofthis valve functions .to remove air from the valve oeprator, whichduplicates the fail-safe condition, resulting in the valve going tofail-safe (open) position. Therefore, the alternative testingproposed will consist of locally observing the valve during fullstroke testing for smooth operation and apparent problems which canaffect the valve operation.

SI-185 Code Relief : This normally closed valve functions totransfer the suction source of the charging pumps to the refuelingwater storage tank. This valve cannot be full stroke exercisedduring: (1) power operation without introducing a highconcentration of boric acid in the RCS, and (2) cold shutdownbecause the only full flow path available is into the reactorcoolant system and the system does not have sufficient volume toaccommodate that flow without a possible low temperatureoverpressure condition. The valve will be full stroke exercised atrefueling frequency.

Page 32 of 81

Page 47: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR'LA

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5129-32

Revision No: 3

Date: 2-5-90

NOTE ll: CS-299E&W Comment : See Attachment "A" for permissible seatleakage values.

Page 33 of 81

Page 48: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 49: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

Flow Diagram No:

Revision No: 3

Date: 2-5-90

RELIEF REQUEST NOTES

2-5129A-20

NOTE 1: QCM-250 -350 Cold Shutdown Justification : These motor-operatedreactor coolant pump seal water return isolation valves cannot beexercised during power operation because it would interrupt reactor .

coolant pump seal water flow and could cause damage to the seals.Therefore, the valves are full stroke exercised and timed at cold .-

shutdown frequency.

NOTE 2:

NOTE 3:

QCM-250 and -350 Code Relief : See "Attachment-A" forpermissible seat leakage values..

QMO-451 -452 Cold Shutdown Justification : These motor-operatedgate valves function as volume control tank isolation valves.Exercising these valves during power operation could result in aloss of pressurizer level control which could cause a reactor trip.These valves are full stroke exercised and timed at cold shutdownfrequency.

Page 34 of 81

Page 50: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

IJ

Page 51: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5135-34

Revision No: 3

'Date: 2-5-90

NOTE 1 CCM-451 -452 -453 -454 -458 and -459 Cold Shutdown" '"ll

operation without securing cooling water to the reactor CoolantPumps (RCPs). Isolation of these valves could cause failure of theRCPs. The valves will be full stroke tested and timed at coldshutdown frecpxency.

NOTE 2

NOTE 3:

NOTE 4:

NOTE 5:

CCM-451 throu h -454 -458 -459CCR-455 throu h -457 -460 -462 and CCW-135 Code ReliefSee "Attachment-A" for permissible seat leakage values.

CCR-455 -456 and -457 Cold Shutdown Justification : Thesevalves cannot be tested during power operation without securingcooling water to the reactor support coolers. These valves mustremain open to prevent overheating of the concrete around thereactor supports during power operation. The valves will be fullstroke tested and timed at cold shutdown frequency.

CCW-135 Code Relief : This check valve cannot be tested duringpower operation without securing cooling water to the reactorsupport coolers. The valve must remain open to prevent overheatingof the concrete around the reactor supports during power operation.The valve will be verified closed in conjunction with Appendix Jseat leakage testing at refueling frequency.

CRV-470 Code Relief : This air operated valve is used to regulatecomponent cooling water (CCW) to the letdown heat exchanger. Thevalve is normally in service during power operation.

Page 35 of 81

Page 52: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 53: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5135-34

Revision No: 3

Date: 2-5-90

CRV-470 (continued)This valve is controlled by an auto/manual station with auto inputfrom the letdown heat exchanger outlet temeprature sensor(QTC-302). The valve also trips closed from an SI signal via asolenoid valve. The valve will be full stroke exercised quarterlyusing auto/manual station which will permit rapid cycling of thisregulating valve resulting in minimal impact on letdowntemperature. Meaningful stroke time data is not available sincethis valve does not have local or remote position indication.Fail safe testing this valve closed requires a longer period oftime than cycling the valve using the auto/manual station. Thevalve will be fail safe tested to its closed position at coldshutdown frequency with letdown flow out of service thus avoidinghigh letdown line temperatures that could cause flashing in theletdown heat exchanger and lifting of safety valves.

Page 36 of 81

Page 54: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5135A-30

Revision No: 3

Date: 2-5-90

NOTE 1: CMO-411 -412 -413 -414 -415 & -416 Comment : These valvesremain open during initial safety injection, but may be closedduring recirculation phase or passive failure. Therefore, thevalve time will be recorded from open to close position.

Page 37 of 81

Page 55: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 56: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5135B-14

Revision No: 3

Date: 2-5-90

NOTE 1: CCM-430 throu h -433 CCR-440 and -441; CCW-243-25 -243-72-244-25 and -244-72 Code Relief : See "Attachment-A" forpermissible seat leakage values.

NOTE 2: CCW-243-25 CCW-243-72 CCW-244-25 and CCW-244-72 Code Relief :These check valves are located xn the penetration cooling supplyheaders of the CCW System inside the containment. The valves areopen during power operation and cold shutdown to provide coolingwater to the main steam penetrations. These valves are notecpxipped with position indication. The valves will be confirmedclosed in conjunction with Appendix J seat leakage testing atrefueling frequency.

Page 38 of 81

Page 57: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5141-27

Revision No: 3

Date: 2-5-90

NOTE 1: ICR-5 -6 NCR-105 throu h -110 Code Relief : See "Attachment-A"for permissible seat leakage values.

Page 39 of 81

Page 58: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLA

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5141D-8

Revision"No: 3

Date: 2-5-90

NOTE 1:

NOTE 2:

ECR-10 throu h -29 and NS-283 Code Relief : See "Attachment-A"for permissible seat leakage values.

NS-283 Code Relief : This containment isolation check valve islocated in the. sample return line of the Post-Accident ContainmentHydrogen Monitoring System. The valve cannot be full strokeexercised to closed position quarterly or at a cold shutdownfrequency because the line is open ended in the containment. Thischeck valve is not equipped with position indicator. The onlymethod available to verify the valve closure is by seat leakagetesting. The valve will be full stroke exercised to the openposition by a flow test cpxarterly and will be confirmed closed inconjunction with Appendix Z seat leakage testing at refuelingfrequency.

Page 4'0 of 81

Page 59: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 60: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5142-28

Revision No: 3

Date: 2-5-90

NOTE 1: ICM-250 and ICM-251 Cold Shutdown Justification : These normallyclosed valves cannot be operated during normal plant operationwithout introducing Boron into a nonheat traced line: Boron couldcrystallize and plug the line. The valves will be full stroketested and timed at cold shutdown frequency.

NOTE 2: ICM-250 -251 -260 and -265 Code Relief : See "Attachment-A" forpermissible seat leakage values.

NOTE 3: IMO-261 Cold Shutdown Justification : This valve cannot be testedwhen SI pumps are required to be operable. Testing would result inisolation of the common suction line to both SI trains. This valvewill be stroke tested and timed at cold shutdown frequency.

NOTE 4: IMO-262 and -263 Cold Shutdown Justification : These motoroperated valves are located in series in the re-circulation line ofthe Safety Injection pumps. Exercising either of these valves willmake both SI pumps inoperable. These valves will be full-strokeexercised and .timed at cold shutdown frequency wheh SI pumps arenot required to be operable.

NOTE 5: SI-llON SI-llOS and SI-101 Code Relief : Safety Injection (SI)pump discharge valves, SI-110N and -llOS, cannot be exercisedduring power operation because the SI pumps cannot overcome reactorcoolant system pressure. Therefore, no flow path exists and,because minimum flow lines branch off upstream of these valves,they cannot be part-stroke tested during pump testing. The common(SI pumps) suction check valve, SI-101 is part-stroke exercised at

Page 41 of 81

Page 61: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR Pi

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5142-28

Revision No: 3

Date: 2-5-90

Note 5 (continued)power operation during pump testing. These valves cannot beexercised during cold shutdown because the SI pumps are required tobe inoperable by Technical Specification 3.5.3 to protect againstlow temperature overpressurization of the reactor. These valveswill be full-stroke exercised at refueling frequency.

NOTE 6: SI-142 Ll L2 L3 and L4 Code Relief : These check valves arelocated in the supply lines from the Boron Injection Tank to thereactor coolant cold legs (loop 1 through 4). These valves cannotbe tested during power operation because this would requireinjecting highly concentrated boric acid solution from the BoronInjection Tank into the Reactor Coolant System resulting inprobable plant shutdown.

These valves cannot be partially-stroke exercised using the BITbypass line because this could result in bypassing the BIT, therebynot achieving design flow through the BIT if an accident occurred.

These valves cannot be full-stroked exercised during cold shutdownbecause this would require injecting the BIT into the RCS whichcould significantly delay startup from cold shutdown condition (theBIT would have to be brought to the proper Boron concentration andthe RCS would have to be diluted sufficiently to allow startup).These valves will be full stroke exercised at refueling frequency.

Page 42 of 81

Page 62: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 63: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-35

Revision No: 3

Date: 2-5-90

NOTE 1: SI-151E&W -152N&S -158-Ll throu h L4 -161-Ll throu h L4 -166-1throu h 4 -170Ll throu h L4 RH-133 -134 and ICM-129 Comment :See "Attachment-A" for permxssible seat leakage values.

NOTE 2:

NOTE 3:

NOTE 4:

IMO-128 and ICM-129 Cold Shutdown Justification : These valvesfunction as the normal return from the RCS to the -RHR for heatupand cooldown. These valves are normally closed and cannot beoperated during normal plant operation because they are interlockedto remain closed at RCS pressure above 450 psig. The valves willbe full stroke exercised and timed prior to placing them intoservice at cold shutdown frequency.

IMO-310 -320 -314 -324 Comment : These valves remain openduring injection phase of a safety injection, but will be closedduring recirculation phase. Therefore, stroke timing will be fromopen to close position.IMO-315 -316 -325 -326 Cold Shutdown Justification : ValvesIMO-315 and -325 are normally closed valves, located in the RHR andSI Supply Header to RCS hot legs. Valves IMO-316 and -326 arenormally open valves located in the RHR and Sl Supply Header to RCScold legs. These valves should not be exercised during poweroperation because failure in a non-conservative position wouldresult in less than minimum number of injection flow path asrequired by the FSAR. The valves will be full stroke tested andtimed at cold shutdown frequency.

Page 43 of 81

Page 64: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 65: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-35

Revision No: 3

Date: 2-5-90

NOTE 5:

NOTE 6:

SI-166-1 throu h 4 Code Relief : These check valves function toprevent backflow from the RCS xnto the accumulators during normaloperation. These valves function to supply flow from theaccumulators to the RCS during an accident condition. These valvescannot be exercised during power operation because the accumulatorsdo not have sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because thiswould result in a possible low temperature overpressurization ofthe RCS. Full stroke testing during re'fueling outages is notpossible because of the resulting water surge into the reactor andthe potential for high airborne radiation contamination. Thesevalves will be part stroke exercised at refueling frequency. Thevalves will be disassembled, manually full stroke exercised andvisually examined on a sampling basis (one of four) per GL-89-04,Attachment, 1, Item g2, at refueling frequency.

SI-161 Ll L2 L3 L4 Code Relief : These check valves arelocated in the supply lines from the Residual Heat Removal andSafety Injection Pumps to the RCS cold legs (loop 1 through 4).These valves cannot be exercised during power operation because theRHR pumps and SI pumps do not develop sufficient head to overcomeRCS pressure. Full stroke of these valves (individually) cannot beverified at cold shutdown frequency because flow instrumentation isnot available downstream of the flow split. These valves will bepart stroke exercised at cold shutdown frequency and full strokewill be locally verified using portable instrumentation atrefueling frequency.

Page 44 of 81

Page 66: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-35

Revision No: 3

Date: 2-5-90

NOTE 7:

NOTE 8:

NOTE 9:

RH-108E W Cold Shutdown Justification : These valves cannot befull stroke exercised quarterly because it would require designmodification to existing instrumentation to accommodate the fullflow test measurements. The valves will be part stroke exercisedquarterly and full stroke exercised at cold shutdown frequency(during RHR operation).

SI-148 Code Relief : Check valve SI-148 is located in theRefueling Water Storage Tank (RWST) supply line to the RHR system.The design flow through the valve is 6000 gpm. Flow to the core isnot possible when the RCS pressure is above the shut-off pressureof the RHR pumps (195 psig). In order to full stroke exercise thisvalve, both RHR pumps must be operated and the RHR system manuallyaligned to recirculate flow back'to the RWST. This configurationplaces both RHR trains inoperable since neither train can providedesign flow to the core. In order to preclude placing the unit inan unsafe condition, a partial stroke test is performed quarterly.The valve cannot be full stroke exercised during cold shutdownsince the RCS cannot- accommodate the introduction of 6000 gpm fromthe RHR system. In addition, during cold shutdown, the RHR systemis required to be operable for RCS temperature control. The valvewill be full stroke exercised when the reactor cavity is beingflooded at refueling frequency.

SI-151 E W Cold Shutdown Justification : These check valves arelocated in the RHR supply lznes to either the hot or cold legs.These valves cannot be exercised during power operation because theRHR pumps do not develop sufficient head to overcome RCS pressure.These valves will be exercised at cold shutdown frequency.

Page 45 of 81

Page 67: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I,

Page 68: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-29

Revision No: 3

Date: 2-5-90

NOTE 10:

NOTE 11:

SI-152 N S Code -Relief : These check valves function to provideSafety Injection pump discharge to either the hot or cold legs.These valves cannot be exercised during power operation because theSI pumps do not develop sufficient pressure to overcome RCSpressure. These valves cannot be exercised during cold shutdownbecause the safety injection pumps are required to be inoperable byTechnical Specification Section 3.5.3, to protect against lowtemperature overpressurization of the reactor vessel. Also, duringcold shutdown, there may not be sufficient volume in the RCS toaccommodate the amount of water needed to full stroke. Thesevalves will be full stroke exercised at refueling frequency.

SI-158 Ll L2 L3 L4 Code Relief : Check valves SI-158 arelocated zn the supply lines from the Residual Heat Removal andSafety Injection Pumps to the RCS hot legs (loop 1 through 4).These valves cannot be exercised during power operation because theRHR and SI pumps do not develop sufficient head to overcome RCSpressure. Full stroke of these valves (individually) cannot beverified at cold shutdown frequency because flow i'nstrumentation isnot available downstream of the flow split. These valves will bepart stroke exercised at cold shutdown frequency. Full stroke will'.be verified using portable instrumentation at refueling frequency.

Page 46 of 81

Page 69: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I 'j

4

Page 70: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-35

Revision No: 3

Date: 2-5-90

NOTE 12 SI-170 Ll L2 L3 and L4 Code Relief : These valves are locatedon the RCS cold leg (loops 1 through 4) injection lines from theaccumulators, RHR, and SI systems. They cannot be exercised duringpower operations because the RHR and SI pumps do not developsufficient head to overcome RCS pressure. The valves will bepart-stroke exercised at a cold shutdown frequency. Due to theplant design, the valves are sized such that full stroke testingcannot be attained without discharging the accumulators andoperating SI and RHR pumps simultaneously. The only methodavailable to verify the full stroke is by disassembly. The valvesare not equipped with position indicators. The valves will bedisassembled, manually full stroke exercised and visually examinedon a sampling basis (one of four) per GL-89-04, Attachment 1, ItemN2, at refueling frequency.

NOTE 13: N-102 Code Relief : This check valve is located in the nitrogensupply header to the accumulators for blanketing purposes. Thevalve cannot be full stroke tested to the closed position duringpower operation or cold shutdown because, due to the plant design,the only method available to verify the valve closure is leaktesting. The valve and necessary test connections are locatedinside the containment. The valve is not equipped with a positionindicator. The valve will be verified closed in conjunction withAppendix Z seat leakage testing at refueling frequency.

NOTE 14: GCR-314 ICM-305 and -306 N-102 SI-171 -172 and -194 CodeR~elref : See "Attachment-A" for permissible seat leakage values.

page 47 of 81

Page 71: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~t

Page 72: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5143-35

Revision No: 3

Date: 2-5-90

NOTE 15: IMO-340 and -350 Code Relief : Valves IMO-340 and IMO-350 arelocated in east and west RHR discharge headers to the suction ofcharging and SI pumps, respectively. These valves are normallyclosed during power operation, and'ould be opened during therecirculation phase of a LOCA to allow the RHR pumps to providewater from the containment recirculation sump to charging and SIpumps. These valves cannot be full stroke exercised during poweroperation because they are interlocked with valves IMO-262 and-263, located in series, in the SI pump miniflow (recirculation)line to RWST. Closing of IMO-262 and -263 would render both SIpumps inoperable and, thus, places the unit in T/S 3.0.3, whichallows one hour to restore the SI pumps to operable status or begina unit shutdown. The complicated valve and equipment lineup toperform the valve testing in one hour is highly unlikely. Therefore,the valves will be full stroke exercised and timed on a cold shutdownfrequency. (For additional details, refer to Code Relief granted by theNRC dated 1-30-89, AEP:NRC:09690.)

Page 48 of 81

Page 73: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

IK

Page 74: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST'PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5144-29

Revision No: 3

Date: 2-5-90

NOTE 1:

NOTE 2:

CTS-138E & W Code Relief : These check valves are located in thelines which supply water from the RWST to the containment spraypumps. The valves cannot be full stroke exercised during poweroperation, cold shutdown or refueling without spraying thecontainment. The valves are part stroke exercised duringcontainment spray pump testing on a quarterly basis. The onlypractical method available to verify full stroke of these valves isby disassembly. These valves are not equipped with positionindicators. The valves will be disassembled, manually full strokeexercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1, Item 52, once every other refuelingfrequency.

CTS-103 E & W Code Relief : These check valves are located in thedischarge lines of containment spray pumps to the spray ring.headers in the containment. These valves cannot be full strokeexercised during power operation, cold shutdown or refuelingwithout spraying the containment. The valves are part strokeexercised during containment spray pump testing on a quarterlybasis. The only practical method available to verify full strokeof these valves is by disassembly. The valves are not equippedwith position indicators. The valves will be disassembled;manually full stroke exercised and visually examined on a samplingbasis (one of two) per GL-89-04, Attachment 1, Item g2, once everyother refueling frequency.

Page 49 of 81

Page 75: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

4

Page 76: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5144-29

Revision No: 3

Date: 2-5-90

NOTE 3:

NOTE 4

CTS-131E & W Code Relief : These check valves are located in thesupply lines to the (upper compartment) containment spray ringheaders. These valves are in closed position during normal plantoperation. The valves are exposed.to containment atmosphere on thedownstream side and are isolated from fluid pressure in theupstream side by the closed motor operated valves. The valvescannot be part or full stroke exercised during power operation,cold shutdown or refueling because flow through these valves wouldresult in spraying the containment. This could cause problems withwet lagging, corrosion of components inside the containment, etc.The only practical method available to exercise these valves is bydisassembly. The valves are not equipped with position indicators.The valves will be disassembled, manually full stroke exercised andvisually examined on a sampling basis (one of two) per GL-89-04,Attachment 1,. Item g2, once every other refueling frequency.

CTS-127E & W Code Relief : These check valves are located in thesupply lines to the (lower compartment) containment spray ringheaders. These valves are in closed position during normal plantoperation. The valves are exposed to containment atmosphere on thedownstream side and are isolated from fluid pressure in theupstream side by the closed motor operated valves. The valvescannot be part or full stroke exercised during power operation,cold shutdown or refueling because flow through these valves wouldresult in spraying the containment. This could cause problems withwet lagging, corrosion of components inside the containment, etc.The only practical method available to exercise these valves is by

Page 50 of 81

Page 77: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR IT

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5144-29

Revision No: 3

Date: 2-5-90

NOTE 5

NOTE 6:

Note 4 (continued)disassembly. The valves are not equipped with position indicators.The valves will be disassembled, manually full stroke exercised andvisually examined on a sampling basis (one of two) per GL-89-04,Attachment 1, Item g2, once every other refueling frequency.

RH-141 & -142 Code Relief : These check valves are located in thesupply lines to the (upper compartment) containment spray ringheaders from the RHR Heat Exchangers. These valves are in closedposition during normal plant operation. The valves are exposed tocontainment atmosphere on the downstream side and are isolated fromfluid pressure in the upstream side by the closed motor operatedvalves. The valves cannot be part or full stroke exercised duringpower operation, cold shutdown or refueling because flow throughthese valves would result in spraying the containment. This couldcause problems with wet lagging, corrosion of components inside thecontainment, etc. The only practical method available to exercisethese valves is by disassembly. The valves are not equipped withposition indicators. The valves will be disassembled, manuallyfull stroke exercised and visually examined on a sampling basis(one of two) per GL-89-04, Attachment 1, Item g2, once every otherrefueling frequency.

CTS-109 and -110 Cold Shutdown Justification : These check valvesfunction as vacuum breakers for spray additive tank. The checkvalves are closed during normal plant operation to maintain thetank pressurized. The valves will be verified closed quarterlyduring power operation and will be verified open at. cold shutdownfrequency.

Page 51 of 81

Page 78: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5144-29

Revision No: 3

Date: 2-5-90

NOTE 7: CTS-127E&W CTS-131E&W RH-141 -142 Code Relief : These valvesare to be seat leakage tested in accordance with the unique testingmethods established in the FSAR because of the configuration atD.C. Cook Plant. The permissible seat leakage values of thesevalves are listed in Attachment "A".

Page 52 of 81

Page 79: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 80: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5145-20

Revision No: 3

Date: 2-5-90

NOTE 1: CA-181-N&S Code Relief : See "Attachment-A" for permissible seatleakage values.

Page 53 of 81

Page 81: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5146B-23

Revision No: 3

Date: 2-5-90

NOTE 1: R-156 and R-157 Code Relief : These check valves are installed inparallel lines to the glycol main supply and return lines torelieve glycol thermal expansion. These valves and necessary testconnections are located inside the. containment. Due to the plantdesign, the only method available to verify valve closure is leaktesting. The valves are not equipped with position indicators.The valves will be full stroke exercised in the open directionquarterly and verified closed in conjunction with Appendix J seatleakage testing at refueling frequency.

NOTE 2: R-156 and -157 VCR-10 -ll -20 and -21 Code Relief :See "Attachment-A" for permissible seat leakage values.

Page 54 of 81

Page 82: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5147A-35

Revision No: 3

Date: 2-5-90

NOTE 1: SM-4 -6 -8 and -10 VCR-101 throu h -107 and VCR-201 throu h -207x"

Page 55 of 81

Page 83: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5149-23

Revision No: 3

Date: 2-5-90

NOTE 1: VRV-325 -315 Code Relief : These thermostatically controlledvalves are located at the outlet of the control room airconditioner water pump. These three-way valves function tomodulate water flow through the air handler package based oncooling requirements. These valves are normally in an intermediateposition based on control room -cooling load. These valves can notbe full stroke exercised because there is no provision to fullyclose the valves. The valves will be part stroke exercised from anintermediate position in conjunction with fail safe testing onquarterly basis. These valves are demonstrated operable duringnormal control room air conditioning operation. The valves cannotbe stroked timed because they are not equipped with positionindicator and stroke times are not repeatable.

Page 56 of 81

Page 84: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5151A-26

Revision No: 3

Date: 2-5-90

NOTE 1: DF-108A -109A -114A -115A DL-114A -116A -126A -132A -158AW Ifsatisfied when the diesel generator successfully completes itsrequired testing per Technical Specification 4.8.1.1.2.

NOTE 2: QT-114-2AB Code Relief : This valve is located at the dischargeof the engine driven lube oil pump (diesel-generator). Thisthree-way thermostatic valve functions to maintain the correct lubeoil temperature by maintaining the correct proportion of oilflowing through the lube oil cooler and bypassing the lube oilcooler to maintain a preset lube oil temperature. Ne arerequesting exemption from testing requirements since (1) this valvefunctions only as a regulating valve and not opened/closed; (2)this valve is demonstrated operable during diesel generatortesting. Diesel generators are tested basis per TechnicalSpecification 4.8.1.1.2. The valves will be verified operable byobserving proper temperatures during diesel testing.

Page 57 of 81

Page 85: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5151B-27-

Revision No: 3

Date: 2-5-90

NOTE 1: DG-102A -104A -128A 130A -146A -152A and -154A CommentThe required full stroking of the check valves is satisfied whenthe diesel generator successfully completes its required testingper Technical Specification 4.8.1.1.2.

NOTE 2:

NOTE 3:

QT-132-2AB Code Relief : This valve is located at the dischargeof the emergency diesel engine jacket water pump. This three-way .thermostatic valve functions to maintain the correct proportion ofwater flowing through the diesel engine water cooler and bypassingthe diesel engine jacket water cooler to maintain a preset jacketwater temperature. We are requesting exemption from the testingrequirements since (1) this valve functions only as a regulatingvalve and not open/closed valve; (2) this valve is demonstratedoperable during diesel generator testing. Diesel generators aretested per Technical Specification 4.8.1.1.2. The valve will beverified operable by observing proper temperatures during dieseltesting.XRV-221 and -222 -Startin Air Code Relief : The starting airvalves are installed on parallel air supply lines to the emergencydiesel generator (EDG). The valves are not equipped with position-indication devices to directly measure valve stroke times. Thevalves function to provide starting air which rolls the EDG. Thevalves are functionally redundant to each other. These valves fail"as is," and, therefore, they have no fail safe position.Successful starting of the EDG in accordance with TechnicalSpecification 4.8.1.1.2 (i.e., slow start at least quarterly andfast start once every 184 days within 10 seconds) will verify thevalve performance. The valve stroke timing will be verified by

Page 58 of 81

Page 86: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5151B-27

Revision No: 3

Date: 2-5-90

NOTE 4:

Note 3 (continued)measuring diesel starting times during fast start testing of EDG.The valves on a staggered basis will be valved out one at a time toverify the operability of the opposite valve during slow start ofEDG at least quarterly. Position indication will be confirmedduring the above testing when only one starting air train is usedto start the diesel generators.

XRV-220-Jet Assist Code Relief : This valve's function is tofacilitate the EDG fast start by providing an air boost to theturbo charger to assist in starting the EDG in its TechnicalSpecification 4.8.1.1.2 time limitation of 10 seconds. The valveis not equipped with position indication devices; therefore,meaningful stroke times are not achievable. The valves will befull stroke and fail safe tested by verifying EDG starting timeonce per 184 days in accordance with Technical Specification4.8.1.1.2 ~ v

Page 59 of 81

Page 87: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5151C-26

Revision No: 3

Date: 2-5-90

NOTE 1: DL-114C -116C -126C -132C and -158C Comment : The requiredfullstroking of the check valves is satisfied when the diesel generatorsuccessfully completes its required. testing per TechnicalSpecification 4.8.1.1.2.

NOTE 2: QT-114-2CD Code Relief : This valve is located at the dischargeof the engine driven lube oil pump (diesel-generator). Thisthree-way thermostatic valve functions to maintain the correct lubeoil temperature by maintaining the correct proportion of oilflowing through the lube oil cooler and bypassing the lube oilcooler to maintain a preset lube oil temperature. We arerequesting exemption from testing requirements since (1) this valvefunctions only as a regulating valve and not opened/closed valve;(2) this valve is demonstrated operable during diesel generator

- testing. Diesel generators are tested per Technical Specification4.8.1.1.2. The valves will be verified operable by observingproper temperatures during diesel testing.

Page 60 of 81

Page 88: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I'

1

e

Page 89: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 2-5151D-27

Revision No: 3

Date: 2-5-90

NOTE. 1: DG-102C -104C -128C -130C -146C -152C and -154C Comment :The required full stroking of the check valves is satisfied whenthe diesel generator successfully completes its required testingper Technical Specification 4.8.1.1.2.

NOTE 2

NOTE 3:

QT-132-2CD Code Relief : This valve is located at the dischargeof the emergency diesel engine jacket water pump. This three-waythermostatic valve functions to maintain the correct proportion ofwater flowing through the diesel engine water cooler and bypassingthe diesel engine jacket water cooler to maintain a preset jacketwater temperature. We are requesting exemption from the testingrequirements since (1) this valve functions only as a regulatingvalve and not open/closed valve; (2) this valve is demonstratedoperable during diesel generator testing. Diesel generators aretested on a staggered basis, every 31 days per TechnicalSpecification 4.8.1.1.2. The valve will be verified operable byobserving proper temperatures during diesel testing.XRV-226 and -227 -Startin Air Code Relief : The starting airvalves are installed on parallel air supply lines to the emergencydiesel generator (EDG). The valves are not equipped with positionindication devices to directly measure valve stroke times. Thevalves function to provide starting air which rolls the EDG. Thevalves are functionally redundant to each other. These valves fail"as is," and, therefore, they have no fail safe position.Successful starting of the EDG in accordance with TechnicalSpecification 4.8.1.1.2 (i.e., slow start at least quarterly andfast start once every 184 days within 10 seconds) will verify thevalve performance. The valve stroke timing will be verified by

Page 61 of 81

Page 90: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

'ELIEFREQUEST NOTES,

Flow Diagram No: 2-5151D-27

Revision No: 3

Date: 2-5-90

NOTE 4:

Note 3 (continued)measuring diesel starting times during fast start testing of EDG.The valves on a staggered basis will be valved out one at a time toverify the operability of the opposite valve during slow start ofEDG at least quarterly. Position indication will be confirmedduring the above testing when only one starting air train is usedto start the diesel generators.

0XRV-225 -Jet Assist Code Relief : This valve's function is tofacilitate the EDG fast start by providing an air boost to theturbo charger to assist in starting the EDG in its TechnicalSpecification 4.8.1.1.2 time limitation of 10 seconds. The valveis not equipped with position indication devices; therefore,meaningful stroke times are not achievable. The valves will befull stroke and fail safe tested by verifying EDG starting timeonce per 184 days in accordance with Technical Specification4.8 ~ 1 ~ 1 ~ 2 ~

Page 62 of 81

Page 91: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 12-5115A-41 — Unit-2

Revision No: 3

Date: 2-5-90

NOTE 1: QCR-919 and -920 Code Relief : See "Attachment-A" for permissibleseat leakage values.

Page 63 of Sl

Page 92: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 12-5120B-22 — Unit-2

Revision No: 3

Date: 2-5-90

NOTE 1: PA-342 Code Relief : This check valve is located in themaintenance air supply line into the containment. The valve cannotbe tested during power operation and cold shutdown because: 1)this line is generally isolated by removing a spool piece andinserting a blind flange, and 2) the valve and test connections arelocated inside the containment. The valve is not equipped withposition indicator. Due to the plant design, the only methodavailable to verify the valve closure is leak testing. The valvewill be verified closed in conjunction with Appendix J seat leakagetesting at refueling frequency.

NOTE 2: PA-342 PCR-40 XCR-100 throu h -103 Code Relief :See "Attachment-A" for permissxble seat leakage values.

NOTE 3 XCR-100 -101 -102 -103 Cold Shutdown Justification : These airoperated containment isolation valves located in the control airsupply lines to the containment. These valves cannot be fullstroke tested during power operation without causing a loss ofcontainment control air. Testing of these valves can potentiallycause: 1) disruption of air flow to air operated valves in thecontainment; as a result, they would go to their fail safeposition, e.g., close position for containment isolation valves, 2)systems from performing their design function, i.e, termination ofsystem flow and change in RCS pressure and temperature, and 3)challenge to system safeguard protection which may result .in a unittrip. The valves will be full stroke exercised and timed at coldshutdown frequency.

Page 64 of 81

Page 93: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PX~VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 12-5131-19 — Unit-2

Revision No: 3

Date: 2-5-90

NOTE 1: CS-427S Cold Shutdown Justification : This valve is located inthe emergency boration path. Thxs valve cannot be tested duringpower operation without inserting large negative reactivity whichwould result in unit shutdown. The valve will be full strokeexercised at cold shutdown frequency.

Page 65 of 81

Page 94: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 12-5136-25 - Unit 2

Revision No: 3

Date: 2-5-90

NOTE 1: SF-152 and -154 Code Relief : See "Attachment-A" for permissibleseat leakage values.

Page 66 of 81

Page 95: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 96: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

— Flow Diagram No: 12-5137A-21 — Unit 2

Revision No: 3

Date: 2-5-90

NOTE 1:

NOTE 2:

DCR-201 throu h -207 -610 -611 -620 and -621 N-160 SF-159 and-160 Code Relief : See "Attachment-A" for permissible seatleakage values.

N-160 Code Relief : This containment isolation check valve islocated in the Nitrogen Supply line to Reactor Coolant Drain Tank.This valve cannot be part or full stroke exercised due to lack ofsufficient differential pressure to back seat the valve duringpower operation or cold shutdown. Due to the plant design, the onlymethod available to verify the valve closure is leak testing. Thevalve is not equipped with position indicator. This valve will beverified closed in conjunction with Appendix J seat leakage testingat refueling frequency.

Page 67 of 81

Page 97: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 98: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

Flow Diagram No:

Revision No: 3

Date: 2-5-90

RELIEF REQUEST NOTES

12-5141C-8 — Unit 2

NOTE 1: ECR-416 -417 -496 -497 -535 and -536 Code ReliefSee "Attachment-A" for permissible seat leakage values.

A

Page 68 of 81

Page 99: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

VALVE TEST PROGRAM

RELIEF REQUEST NOTES

Flow Diagram No: 12-5141F-6 — Unit 2

Revision No: 3

Date: 2-5-90

NOTE 1:

NOTE 2:

NOTE 3:

ECR-36 Cold Shutdown Justification : This valve, located in thecommon sample return line of the lower containment radiationmonitors, cannot be part or full stroke exercised during poweroperation or refueling because closure of the valve would isolateboth radiation monitors, which are required to be operable(Technical Specification Table 3.3-6) during power operation (Mode1 through .4) and refueling (Mode 6). The valve will be full strokeexercised at cold shutdown frequency.

ECR-31 -32 -33 -35 -36 and SM-1 Code ReliefSee "Attachment-A" for permissible leakage values.

SM-1 Code Relief : This containment isolation check valve for thecontainment radiation monitors'sample return cannot be full orpart stroke exercised during power operation because these monitorsare required to be operable in Modes 1, 2, 3, 4, and 6. The valveis not equipped with position indication. The valve is located inthe open ended return line inside the containment. The only methodavailable to verify the valve closure is leak testing. The valvewill be verified closed in conjunction with Appendix J seat leakagetesting at refueling frequency.-

Page 69 of 81

Page 100: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 101: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P T

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2

ATTACHMENT-A

Revision No: 3

Date: 2-5-90

1. CONTAINMENT ISOLATION VALVES Cate o A or AC =

Testing Method: (SLT-2) Seat leakage test the valve in accordance with10CFR50, Appendix J, in lieu of ASME Code Section XI except forparagraphs IWV-3426 and IWV-3427, which are applicable (refer to Figure3., Item N3) .

Valve No

WCR-920,-922

WCR-921,-923

WCR-932,-934

WCR-933,-935

WCR-941,-945

WCR-944,-948

WCR-951,-955

WCR-954,-958

WCR-924,-926

WCR-925,-927

WCR-928,-930

FlowDiaciram Size

5114A 3

5114A

5114A

5114A

5114A

5114A

5114A

5114A 3

5114A 3

5114A 3

5114A

~TeDA

DA

DA

DA

DA

DA

DA

DA

DA

DA

DA

Permissible Leakage

900

900

900

900

900

'900

900

900

900

900

900

Page 70 of 81

Page 102: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42

ATTACHMENT-A

Revision No: 3

Date: 2-5-90

Valve No.

WCR-929,-931

WCR-942,-946

WCR-952,-956

WCR-943,-947

WCR-953,-957

WCR-960,-962

WCR-961,-963

WCR-964,-966

WCR-965,-967

ECR-10,-20

ECR-11,-21

ECR-12,-22

ECR-13,-23

ECR-14,-24

5114A

5114A

5114A

5114A

5114A

5114A

5114A

5114A

5114A

5141B

5141B

5141B

5141B

5141B

0 '00.50

0.50

0.50

0.50

Flow~Dia ram Size ~Te

DA

DA

DA

DA

DA

DA

DA

DA

DA

GL

GL

GL

GL

Permissible . Leakage

900

900

900

900

900

750

750

750

750

750

750

750

750

750

Page 71 of 81

Page 103: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P T

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2

ATTACHMENT-A

Revision No: 3

Date: 2-5-90

Valve No.

ECR-15,-25

ECR-16,-26

ECR-17,-27

ECR-18,-28

ECR-19,-29

CS-442-1

CS-442-2

CS-442-3

CS-442-4

SI-189

SM-1

N-102

N-159

PW-275

FlowDiaciram

5141B

5141B

5141B

5141B

5141B

5128A

5128A

5128A

5128A

5128A

5141F

5143

5128A

5128A

Size

0 '00.50

0.50

0 '00.50

0.75

~TeGL

GL

GL

GL

GL

CK

CK

.CK

CK

CK

CK

CK

CK

CK

Permissible Leakage

750

750

750

750

750

750

750

750

750

1200

750

750

750

900

Page 72 of 81

Page 104: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2

ATTACHMENT-A

Revision No: 3

Date: 2-5-90

Valve No.

CS-321

VCR-10,-11

VCR-20,-21

DCR-203,-207

N-160, DCR-201

DCR-610,-611

DCR-620,-621

DCR-205,-206

DCR-600,-601

QCR-300,-301

QCM-250,-350

QCR-919,-920

5146B

5146B

5137A

5137A

5137A

5137A

5137A

2.50

5124

5129

5129A

5115A

FlowDiaciram Size

5129

~TeCK

DA

DA

DA, GL

CK, DA

DA

DA

DA

DA

GL

DA

Permissible Leakage

1800

1200

1200

750

1125

750

750

1200

900

750

1200

750

SF-152,-154

SF-159,-160

5136

5137A

2.50 DA,GL

DA

750

900

Page 73 of 81

Page 105: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 52

Revision No: 3

Date: 2-5-90

Valve No.

NCR-105,-106

NCR-107,-108

NCR-109,-110

RCR-100,-101

DCR-202,-204

ICR-5,-6

ECR-33,-35

ICM-260

ICM-265

ECR-31,-32

XCR-100,-101

XCR-102,-103

GCR-301

GCR-314

* Double Discs

FlowDiaciram

5141

5141

5141

5128A-

5137A

5141

5141F

5142

5142

5141F

5120B

5120B

5128A

5143

ATTACHMENT-A

Size

0.50

0.50

0.50

0.375

~TeGL

- GL

GL

GL

GL

GL

0.75 DA

GL

0 '5 DA

0 '0 GL

0.75,2 GL,DA

GA (DD) *

GA(DD) *

GL

Permissible Leakage

750

750

750

750

750

750

750

'00600

750

750

750

375

375

Page 74 of 81

Page 106: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C ~ COOK NUCLEAR, P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2

Revision No: 3

Date: 2-5-90

ATTACHMENT-A

Valve No.Flow

Diaciram

SI 171 g 172 g 194 5143

Size

0.75

~TeGL

Permissible Leakage

NCR-252

CCR-460,-462

CCR-457,CCW-135

CCR-455,-456

SM-4,-6

ICM-251

ICM-250

CA-181S

CA-181N

SM-8,-10

CCW-243-25

CCW-244-25

* Double Discs

5128A

5135

5135

5135

5147A

5142

5142

5145

5145

5147A

5135B

5135B

GL

0.50 GL

0.50

0 '00.50

GA(DD) *

~ GA(DD) *

CK

CK

ND

CK

CK

3 GL

2,2.50 GL,CK

GL

450

900

1125

750

750

600

600

750

750

750

750

750

Page 75 of 81

Page 107: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

l (

Page 108: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42

ATTACHMENT-A

Revision No: 3

Date: 2-5-90

Valve No.

CCW-243-72

CCW-244-72

CCM-430

CCM-431

CCR-440

CCR-441

CCM-432

CCM-433

— R-156

R-157

NS-357

ECR-496,-497

ECR-416

ECR-417

ECR-535

FlowDiaciram

5135B

5135B

5135B

5135B

513B

5135B

5135B

5135B

5146B

5146B

5124

5141C

5141C

5141C

5141C

Size

1.50

1.50

1.50

1.50

1.50

1.50

0 '750.375

0.50

0 '00.50

0.50

0 '0

~TeCK

CK

GL

GL

GL

GL

GL

GL

CK

CK

CK

GL

GL

GL

GL

Permissible Leakage

750

750

375

375

375

375

375

375

750

750

750

750

375

375

375

Page 76 of 81

Page 109: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 110: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P T

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 02

Revision No: 3

Date: 2-5-90

ATTACHMENT-A

Valve No.Flow

Diaciram Size ~TePermissible Leakage

ECR-536

ECR-36

PCR-40

PA-342

NS-283

NPX-151

WCR-900,-902

WCR-901,-903

WCR-912,-914

WCR-913,-915

WCR-904,-906

WCR-905,-907

WCR-908,-910

WCR-909,-911

VCR-101,-201

5141C

5141F

5120B

5120B

5141D

5128A

5114A

5114A

5114A

5114A

5114A

5114A

0.50

0.50

0.50

5147A 14

5114A

5114A " 6

GL

DA

GA

CK

CK

GL

DA

DA'A

DA

DA

DA

DA

DA

BF

375

375

375

750

750

375

1800

1800

1800

1800

1800

1800

1800

1800

4200

Page 77 of 81

Page 111: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 112: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR NT

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42

Revision No: 3

Date: 2-5-90

ATTACHMENT-A

Valve No.Flow

Diaciram Size T~ePermissible Leakage

VCR-102,-202

VCR-103,-203

VCR-104,-204

VCR-105,-205

VCR-106,-206

VCR-107,-207

ICM-305

ICM-306

5147A 14

5147A

5147A

5147A

5147A

5147A

24

30

30

24

14

5143 18

5143 18

8,4,8

8,4,8

CCM 452 g 454 I 458 5 1 35

CCM 45 1 I 453 g 459 5135

* Double Discs

BF

BF

BF

BF

BF

BF

GA(DD) *

GA(DD) *-

BF,GL,BF

BF,GL,BF

4200

7200

9000

9000

7200

4200

2700

2700

3000

3000

Page 78 of 81

Page 113: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2

Revision No:. 3

Date: 2-5-90

ATTACHMENT-A

2. CONTAINMENT SPRAY VALVES Cate or A or AC

Testing Method: As described in "SLT-2A," Figure 3, Item N3.

Valve No.

CTS-131W

CTS-131E

CTS-127W

CTS-127E

RH-141

RH-142

FlowDiaciram Size

5144

5144

5144

5144

5144

5144

~TeCK

CK

CK

CK

CK

CK

Permissible Leakage

35.00

35.00

22.55

21. 21

20.70

23.00

Page 79 of 81

Page 114: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 115: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR T

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2

Revision No: 3

ATTACHMENT-A

Date: 2-5-90

3. PRESSURE ISOLATION VALVES Cate o A or AC

Testing Method: (SLT-1) Seat leakage test the valve per ASME CodeSection XI (refer to Figure 3, Item N3).

Valve No.

CS-299E

CS-299W

SI-152-N

SI-152-S

ICM-129

SI-161-L1,-L4

SI-161-L2,-L3

SI-170-Ll

SI-170-L2

SI-170-L3

* Double Discs

FlowDiaciram

5129

5129

5143

5143

5143

5143

5143

5143

5143

5143

Size

14

10

10

10

CK

CK

CK

CK

GA(DD) *

CK

CK

CK

CK

CK

Permissible Leakage

2.0

2.0

5.0

5.0

10.0

10.0

10.0

5.0

1.0

1.0

Page 80 of 81

Page 116: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 117: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR P T

ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2

Revision No: 3

Date: 2-5-90

ATTACHMENT-A

Valve No.

SI-170-L4

SI-158-Ll,-L4

SI-158-L2,-L3

SI-151-E

SI-151-N

SI-166-Ll

SI-166-L2

SI-166-L3

SI-166-L4

RH-133,-134

FlowDiaciram

5143

5143

5143

5143

5143

5143

P3.43

5143

5143

5143

Size

10

10

10

10

10

~TeCK

CK

CK

CK

CK

CK

CK

CK

CK

CK

Permissible Leakage

5.0

10.0

10.0

5 '

5.0

5.0

5.0

5.0

5.0

1.0

Page 81 of 81

Page 118: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0SYSTEM NAME: HAKE UP 8 PRIMARY-HATER UNIT 2

DONALD C. COOK. NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHMARY SHEET - UNIT 2FLON DIAGRAM: 12-5115A-41

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-QCR-919 3 DA 2 A D/7 0/C C 2 A A EF1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT-2

P NO

NOP NOP NO

R YESp NOTE 1

2-QCR-920 3 DA 2 A D/7 0/C C 2 A A EF1E F-5EF-7ET-XXXSLT-1

EF-2EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR 'ESp NOTE 1

Page 119: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

U

0

e e e e o e e e e o e o e e e 0

Page 120: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: COMPRESSED AIR SYSTEM-UNIT 2

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SURIARY SHEET - UNIT 2FLON DIAGRAM: 12-5120B-22

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-PA-342 3 CK 2 SA K/7 0/C C 2 A AC CF-1SLT-1

CF-2SLT"2

R YESp HOTE 1R YESp NOTE 2

2-PCR-60 3 GA 2 A M/7 0/C C 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5.EF-7ET-XXXSLT"2

P NONO

P NOP NOR YESp NOTE 2

2-XCR-100 3 GL 1 A L/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 3NO

C NOp CSJ 3C NOp CSJ 3R YESp NOTE 2

2-XCR-101 3 GL 1 A L/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 3NO

C NOp CSJ 3C NOp CSJ 3R YESp NOTE 2

2-XCR-102 3 GL 1 A L/2 0 2 A A EF"1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C HOp CSJ 3NO

C NO, CSJ 3C NOp CSJ 3R YESp NOTE 2

2-XCR-103 3 GL 1 A L/2 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 3NO

C NOp CSJ 3C NOp CSJ 3R YESp NOTE 2

I I

e ~

Page 121: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0, 0 0 0

I

o e e e e o e e e e e e o e e 0

Page 122: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: CVCS — BORON HAKE-UP - UNIT 2

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHMARY SHEET — UNIT 2FLON DIAGRAM: 12-5131-19

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SI2E ACT F.D. I POHER SAFETY )CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE

2-CS-415"3 3 CK 2 SA K/6 0/C 0 3 A C CF1 CF-1 P NO

2-CS-415-4 3 CK 2 SA L/6 0/C 0 A C CF-1 CF-1 P NO

2-CS-426-S . 3 CK 1 SA M/6 0/C 0 A C CF1 CF-1

2-CS-427-S 3 CK 2 SA H/5 C 3 A C CF1 CF2 C NO) CSJ 1

2"QHO-420 3 GA 2 HO L/5 C A B EF1EF 5ET-XXX

EF"1EF"5ET-XXX

P NONO

P NO

2-QRV-421 3 GL 2 A H/6 0/C 0 3 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-QRV-422 3 GL 2 A H/7 0 3 A B EF1EF-5EF"7ET-XXX

EF-1EF"5EF-7ET-XXX

NO

P NO

Page 123: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e o e e o e e e o e e e 0/

8

0

0 0 0 0 0 0 0 0

Page 124: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2SYSTEM NAHE: SPENT FUEL PIT COOLING 8 CLEANUP U2 FLON DIAGRAH: 12-5136-25

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION Xl

NUMBER REV TYPE SIZE ACT F D I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-SF-152 .3 DA 2.5 H K/9 C 2 P A SLT-1 SLT"2 R YES> NOTE 1

2-SF-154 3 GL 2.5 H K/9 C 2 P A SLT-1 SLT-2 R YES> NOTE 1

Page 125: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 o o o e o e e e o e a o 0

Page 126: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NDS VENTS & DRAINS-UNIT 2

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 12-51'37A-21

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F D t PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2DCR201 3 DA 1 A E/0 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2"DCR-202 3 DA 0.75 A E/5 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-DCR-203 "3 DA 1 A F/0 C 2 .P A EF-1

EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF-7ET-XXXSLT-2

P NONO

P NO

P NOR YES> NOTE 1

2-DCR-204 3 DA 0.75 A F/5 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-DCR-205 3 GL A E/7 0/C C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NO

NOP NOP NOR YES> NOTE 1

Page 127: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o o e e e e e e e e e e e e 0

Page 128: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: WDS VENTS 8 DRAINS

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUNDRY SHEET - UNIT 2FLOW DIAGRAM: 12-5137A-21

RUN DATE AND TIME: 15FEB90s16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F-D. I POWER SAFETY ICD A/P CATTYPE COORD I OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-DCR-206 3 GL A E/B 0/C C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF"7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-DCR-207 3 DA 1 A F/4 0 2 A A EF-1E F-5EF-7ET-XXXSLT-1

EF-1EF-5EF"7ET-XXXSLT-2

NOP NO

HOR YES> NOTE 1

2"DCR-610 3 DA 2.5 A M/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NO

R YES> NOTE 1

2-DCR-611 3 DA 2.5 A N/9 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-DCR-620 3 DA 1 A M/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P NOP NOR YES> NOTE 1

Page 129: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e a e e e e e

0 0 0 0 0 0 0

Page 130: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

iver

SYSTEH NAHE: NDS VENTS & DRAINS

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET — UNIT 2FLON DIAGRAH: 12-5137A-21

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SI2E ACT F.D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-DCR-621 3 DA 1 A N/9 0 2 A A EF1EF-5EF"7ET-XXXSLT-1

EF-1EF"5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-N-160 3 CK 1 SA F/4 0 2 A AC CF1SLT-1

CF-2SLT-2

R YES> NOTE 2R YES> NOTE 1

2-SF-159 DA H E/5 C 2 P A SLT-1 SLT-2 R YESp NOTE 1

2"SF-160 3 DA 3 H F/5 C 2 P A SLT-1 SLT-2 R YESi NOTE 1

Page 131: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

(0 0 ~ ~ 0 ~ 0 ~ ~ 0 ~ ~ ~ 0 ~ 0 0

Page 132: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: PAS LIQUID 8 GAS - UNIT-2

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET - UNIT 2FLON DIAGRAH: 12-5141C-8

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. t PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIH TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED NODE

2-ECRW16 3 GL 0.5 A H/6 C 2 P A EF-1EF-5EF"7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-ECR-417 3 GL 0.5 A H/6 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NO

P NOP NOR YES'OTE 1

2-ECR-496 3 GL 0.5 A H/8 C 2 P A EF-1EF-5EF-7ET"XXXSLT-1

EF"1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2"ECR"497 3 GL 0.5 A H/8 C 2 P A EF"1 = EF-1EF-5 EF-5EF-7 EF-7

P NONO

P NOET-XXXSLT-1

ET-XXXSLT-2

P NOR YES> NOTE 1

2-ECR-535 3 GL 0.5 A H/2 C 2 P A EF-1EF-5EF"7ET-XXXSLT-1

EF-1Ef-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

Page 133: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 134: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: PAS LIQUID & GAS - UNIT-2

-DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET —UNIT 2FLOW DIAGRAM: 12-5141C-8

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUt&ER REV TYPE SI2E ACT F.D. I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-ECR-536 3 GL 0.5 A L/2 C 2 P A EF1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESi NOTE 1

Page 135: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o e e e e e e e e e e e e e

0

0 o o e o e e e e o o e e.o e e 0

Page 136: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: PAL SAMPLING 2 INST. PANELS - U-2

DONALD C. COOK NUCLEAR PLANTSECOND TEH YEAR INTERVAL

VALVE SUiiARY SHEET - UNIT 2FLOW DIAGRAM: 12-5141F-6

RUN DATE AND TIME: 15FEB9D:16:14

VALVE I VALVE POSITION I ASME SECTION XI

Ql$3ER REV TYPE SIZE ACT F.D. I POWER SAFETY ICD A/P CATTYPE COORD I OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MiODE

2-ECR-31 3 GL 1 A B/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 2

2-ECR-32 "GL 1 A B/5 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF"7ET-XXXSLT-2

P NONO

P NO

P NOR YESp NOTE 2

2-ECR-33 GL 0.75 A B/2 0 2 A A EF-1EF-5EF-7ET"XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 2

2-ECR-35 3 GL 1 A B/2 0 2 A A EF-1 'F-1EF"5 EF-5EF-7 EF-7

P NONO

P HOET-XXXSLT-1

ET-XXXSLT-2

P NOR YESp NOTE 2

2-ECR-36 3 GL 1 A B/3 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 1NO,

C NOp CSJ 1C YESp CSJ 1R YESp NOTE 2

Page 137: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o a e

Page 138: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VAlVE SUiiARY SHEET - UNIT 2SYSTEM NAME: PAL SAMPLING & INST. PANELS -UNIT 2 FLON DIAGRAM: 12-5141F-6

RUN DATE AND TZHE: ISFEB90:16:10

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-SH-1 3 CK 1 SA A/3 0 2 A AC CF 1SLT-1

CF-2SLT-2

R YESp NOTE 3R YES> NOTE 2

Page 139: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 e e e e e e e e e e e o e e e 4

Page 140: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: HAIN STEAM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-51058-42

RUN DATE AND TIHE: ISFEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I PONER SAFETY !CD A/P CAT PRIH TEST TEST TEST RELIEF REQUESTERS)TYPE COORDI OPER FUNCT ICL '- REQUIRED PERFORMED MODE

2-DCR-310 3 GL 2 A B/3 0 2 A B EF1EF-5EF-7ET-XXX

EF"1EF-5EF-7ET-XXX

P NONO

P NOP NO

T

2-DCR-320 . 3 GL 2 A B/2 0 2 A B EF-1Ef-5EF-7ET"XXX

EF-1E F-5EF-7ET-XXX

P NONO

P NO

P NO

2-DCR-330 3 GL 2 A B/1 0 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-DCR-340 3 GL 2 A B/2 0 2 A B EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NO

P NO

2-QT-506 3 GL 4 HO A/8 C A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

Page 141: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0

Page 142: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: STEAM GENERATING SYSTEM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5105D "2

RUN DATE AND TIME: 15FEB90:16:14

VALVE VALVE POSITION I ASHE SECTION XI

NOSER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-FN"118-1 3 = CK 14 SA B/9 0 2 A C CF1 CF"2 R YES> NOTE 1

2-FH"118"2 3 CK 14 SA K/8 0 2 A C CF1 CF-2 R YES> NOTE 1

2-FN-118-3 3 CK 14 SA J/3 0 2 A C CF1 CF-2 R YES) NOTE 1

2-FH-ll8-4 3 CK 14 SA C/3 0 2 A C CF1 CF-2 R YES> NOTE 1

2-HCM"221 3 GL HO K/4 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-HCH-231 3 GL HO K/4 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-HRV-210 3 GA 28 PO B/7 0 2 A B EF1EF-5EF-7ET-XXX

EF-3EF-5EF-8ET-XXX

P NO> CSJ 2NO

C NOp CSJ 2C NOp CSJ 2

2-HRV"211 3 AG 2 A A/5 C 2 A B EF 1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-HRV-212 3 AG 2 A A/5 C 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NO

P NO

Page 143: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 e e e e o e o e o o e o e e e 0

Page 144: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: STEAM GENERATING SYSTEM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

~ VALVE SUMMARY SHEET - UNIT 2FLOW DIAGRAM: 2-5105D-2

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POWER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-MRV-220 3 GA 28 PO L/7 0 2 A B EF-1EF-5EF-7ET-XXX

EF-3EF"5EF-8ET-XXX

P NO> CSJ 2NO

C NOp CSJ 2C NOy CSJ 2

2-HRV-221 3 AG 2 A H/5 C 2 A B EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONONO

P NO

2-MRV-222 3 AG 2 A M/5 C 2 A B EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2"HRV-230 3 GA 28 PO H/3 0 2 A B EF-1EF-5EF-7ET-XXX

EF-3EF-5EF-8ET-XXX

P NO) CSJ 2NO

C NO> CSJ 2C NO> CSJ 2

2-MRV-231 3 AG 2 A H/1 'C 2 A B EF-1EF-5EF-7ET-XXX

EF-1EF"5EF-7ET-XXX

P NONO

P NOP NO

2-HRV-232 3 AG 2 A H/1 C 2 A B EF"1EF-5EF-7ET-XXX

EF-1Ef-5EF-7ET-XXX

P NONO

P NO

P NO

Page 145: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

J4

Page 146: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: STEAM GENERATING SYSTEM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-5105D-2

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUMBER REV TYPE SIZE ACT F.D. t POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-HRV-240 3 GA 28 PO 8/3 0 2 A 8 EF1EF-5EF-7ET-XXX

E F-3EF-5EF-8ET-XXX

P NOp CSJ 2NO

C NOp CSJ 2C NOp CSJ 2

2-HRV-241 3 AG A A/1 C 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-HRV-242 3 AG 2 A A/1 C 2 A 8 EF1EF-5EF-7ET-XXX

EF-1EF-5EF"7ET-XXX

P NONO

P NOP NO

2-HS-108-2 3 CK 4 SA K/4 C 0/C 3 A C CF-1 CF-2 R YESp NOTE 3

2-HS-108-3 3 CK 4 SA K/4 C 0/C 3 A C CF1 CF-2 R YESp NOTE 3

2-SV-1A-1

2-SV-1A-2

3 REL 6

3 REL 6

SA C/5 C

SA K/5 C

0 ' A C TF-1

2 A C TF1

TF-1

TF-1

R NO

2-SV-1A-3 3 RfL 6 SA K/1 C 2 A C TF-1 TF-1 R NO

2-SV-1A-4 3 REL 6 SA C/1 C 2 A C TF"1 TF-1 R NO

Page 147: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e e o o e o e e e e e o e e N

Page 148: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: STEAM GENERATING SYSTEM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMHARY SHEET - UNIT 2FLON DIAGRAM: 2-5105D-2

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV . TYPE SIZE ACT F.D ~ I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDl OPER FUNCT ICL REQUIRED PERFORMED MODE

2-SV-1B"1 3 REL 6 SA B/5 C 2 A C TF-1 TF"1

2-SV-1B-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1

2-SV-1B-3 3 RE L 6 SA L/1 C 2 A C TF-1 TF-1

2-SV-1B-4 3 REL 6 SA B/1 C 2 A C TF1 TF"1 R NO

2-SV-2A-1 3 REL 6 SA B/5 C 2 A C TF-1 TF-1

2-SV-2A-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1

2"SV-2A-3 3 REL 6 SA L/1 C 2 A C TF-1 TF-1 R NO

2-SV-2A-4 3 REL 6 SA B/1 C 2 A C TF-1 TF-1

2-SV"2B-1 3 REL 6 SA B/5 C 2 A C TF-1 TF-1

2-SV-2B-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1 R NO

2"SV-2B-3 3 REL 6 SA L/1 C 2 A C TF1 TF-1

2-SV"2B-4 3 REL 6 SA B/1 C 2 A C TF1 TF-1 R NO

Page 149: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e o e o e e e - o e e

0 o o e e e e e e e e e o e o e 0

Page 150: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAME: STEAM GENERATING SYSTEM

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLON DIAGRAM: 2-5105D-2

RUN DATE AND TIME: )5FEB90:)6:)4

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F D t PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE

2-SV-3-1 3 REL 6 SA B/5 C 2 A C TF1 TF-1 R- NO

2-SV-3-2 3 REL 6 SA H/5 C 2 A C TF-1 TF-1

2-SV-3-3 3 REL 6 SA H/1 C 2' C TF1 TF-1 R NO

2-SV-3-4 REL 6 SA B/1 C 2 A C TF-1 TF-) R NO

Page 151: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o o o e o e o o o e e e o e 0

Page 152: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~SYSTEM NAME: FEEDHATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUYHARY SHEET - UNIT 2FLON DIAGRAM: 2-5106-34

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F ~ D. I PONER SAFETY )CD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-FHO"201 3 GA 14 HO G/5 0 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1

2-FHO-202 3 GA 14 HO E/9 0 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1

2-FHO-283 3 GA 14 HD F/9 0 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1

2-FHO-204 3 GA 14 HO H/5 0 2 A 8 EF-1E F-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1

2-FRV"210 3 AG 14 A G/5 0 2 A B EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1C NOp CSJ 1

" 2-FRV-220 3 AG 14 A E/9 0 2 A B EF-1EF-5EF-7ET-XXX

EF-2EF-5EF"8ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1C NOp CSJ 1

2-FRV-230 3 AG 14 A F/9 0 2 A B EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

C NOp CSJ 1NO

C NOp CSJ 1C NOp CSJ 1

Page 153: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 154: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: FEEDWATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHMARY SHEET - UNIT 2FLOW DIAGRAM: 2-5106-Wt

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F D I POWER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED, PERFORMED MODE

2-FRV-260 3 AG 10 A , M/5 0 2 A B EF1EF-5EF-7ET-XXX

EF"2EF-5EF-8ET-XXX

C NO> CSJ 1NO

C NO> CSJ 1C NO> CSJ 1

Page 155: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o 0 o i o a e e e e e 0

0 e e o e e e e e e e o o e e

Page 156: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEH NAHE: FEEDNATER

DONALD C COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET " UNIT 2FLON DZAGRAH: 2-5106A-41

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION ) ASHE SECTION XZ

NUiiBER REV TYPE SI2E ACT F ~ D ) POHER SAFETY )CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST( S )TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HiODE

2-FHO-211 3 GL HO 8/4 0 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-FHO-212 3 GL HO 8/4 0 3 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-FHO-221 3 GL 4 HO C/5 0 3 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

NONO

P NO

2-FHO-222 3 GL 4 HO C/5 0 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-FHO-231 3 GL HO C/5 0 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P- NO

2-FHO"232 3 GL 4 HO C/5 0 3 A 8 EF1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

P NO

2"FHO-241 3 GL 4 HO 8/4 0 0 3 A 8 EF1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

Page 157: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o e o e e o e e e e

T

Page 158: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

ill

SYSTEM NAME: FEEDHATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2FLOH DIAGRAM: 2-5106AWl

RUN DATE AND TIHE: 15FEB90:16:14

VALVE VALVE POSITION I ASHE SECTION XZ

NUHBER REV TYPE SIZE ACT F ~ D I POHER SAFETY I CD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-FHO-242 3 GL MO B/4 0 3 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-FRV-247 3 GL 1 A H/9 0 C/0 3 A B EF-1EF"5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

5

2-FRV-257 3 GL 1 A H/9 0 C/0 3 A B EF-1EF"5EF-7ET-XXX

EF-1EF-5EF«7ET-XXX

P NONO

P NOP NO

2-FRV-258 3 GL 1 A E/9 0 C/0 3 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-FH-124 CK 8 SA F/7 C 3 A C CF1 CF-1 P NO

2"FH-128 3 CK 6 SA H/7 C 3 A C CF-1 CF-1 P NO

2-FN-132-1 3 CK SA C/4 C 0/C 2 A C CF-1 CF-2 NOp CSJ 1

2-FN-132-2 3 CK 4 SA D/5 C 0/C 2 A C CF-1 CF-2 NO> CSJ 1

Page 159: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 160: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEN NAHE: FEEDHATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET - UNIT 2FLOH DIAGRAH: 2-5106A-41

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUNBER REV TYPE SIZE ACT F AD. I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE

2-FH"132 "3 3 CK SA D/5 C 0/C 2 A C CF-1 CF-2 NOp CSJ 1

2-FH-132-4 3 CK 4 SA C/4 C 0/C 2 A C CF-1 CF-2 NOy CSJ 1

2-FH-134 3 CK 10 SA 8/9 C 3 A C CF1 CF-3 C NO> CSJ 2

2-FH-135 3 CK 8 SA E/8 C 3 A C CF1 CF-3 C NOp CSJ 2

2-FH-138-1 3 CK SA C/4 C 0/C 2 A C CF-1 CF-2

2-FH-138-2 3 CK 4 SA D/5 C 0/C 2 A C CF-1 CF-2 NO> CSJ 3

2-FH-138"3 3 CK SA D/5 C 0/C 2, A C CF-1 CF-2 NOp CSJ 3

2-FH-138-4 3 CK 4 SA C/4 C 0/C 2 A C CF-1 CF-2 NO> CSJ 3

2-FH-149 3 CK 0.75 SA D/2 C 3 A C CF-1 CF-1 P NOr NOTE

2-FH-150 3 CK 0.75 SA D/3 C 3 A C CF1 CF-1 P NO~ NOTE 4

2-FH-153 3 CK 1 SA N/9 C 0/C 3 A C CF-1 CF-1 P NO> NOTE 5

2-FH"159 3 CK 6 SA L/7 C 3 A C CF1 CF-1 P" NO

Page 161: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o o o o o o e e o o e e e o e

Page 162: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: FEEDNATER

DOHALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UHIT 2FLOH DIAGRAM: 2-5106A-41

RUH DATE AHD TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XZ

NUMBER REV TYPE SIZE ACT F ~ D. I POHER SAFETY }CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-FN-160 CK 1 SA M/9 C 0/C 3 A C CF-1 CF-1 P NO> NOTE 5

2-FN-161 3 CK 8 SA J/7 C 3 A C CF-1 CF-1

2-SV-140-1 3 REL 0.75 SA E/1 C 3 A C TF1 TF-1 R NO

2-SV-140-2 REL 0.75 . SA D/1 C A C TF-1 TF"1 R NO

2"SV-169"A 3 RE L 0. 75 SA K/9 C A C TF-1 TF-1 R HO

2-SV-169-B 3 REL 0.75 SA G/9 C 3 A C TF1 TF-1 R NO

Page 163: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e 0 o 0 o e 0 0

0

0

e e e o e e.e e e o e e e 0

Page 164: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-5113-36

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION Xl

NUMBER 'EV TYPE SIZE ACT F ~ D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-ESH-102-2E 3 CK 20 SA M/8 C A C CF-1 CF-1

2-ESH-102-2H 3 CK 20 SA M/8 C 3 A C CF1 CF-1

2-ESH-141 3 CK 6 SA K/6 C 3 A C CF1 CF-1 P NO> NOTE 1

2"ESH-142 3 CK 6 SA L/6 C 3 A C CF1 CF-1 P - NO> NOTE 1

2-ESH-143 3 CK 6 SA M/6 C 3 A C CF1 CF-1 P NO> NOTE 1

2-ESH-144 3 CK 6 SA M/6 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-ESH-145 3 BF 4 M J/6 C 3 A B EF1 EF-2 C NO> CSJ 2

2-ESH-168-N 3 BF M H/I C 3 A B EF1 EF-1

2-ESH-168-S 3 BF 3 M M/I C 3 A B EF1 EF-1 P NO

2-ESH-169-N 3 BF M G/1 0 3 A B EF1 EF-1

2-ESH-169-S 3 BF 3 M G/1 0 3 A B EF1 EF"1 P NO

2-ESH-170-N 3 BF M F/1 0 3 A B EF1 EF"1 P NO

Page 165: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 166: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5113-36

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-ESW-170-S 3 BF 3 H F/1 0 3 A 8 EF1 EF-1 P NO

2-ESN-171-N 3 BF 3 H F/1 C A 8 EF1 EF-1

2-ESH-171-S 3 BF 3 H F/1 C 3 A 8 EF-1 EF-1 P NO

2-ESN-240 3 BF 6 H H/5 C 3 A 8 EF-1 EF-2 C NOp CSJ 2

2-ESN"243 3 BF 4 H J/7 C 3 A 8 EF"1 C NO> CSJ 2

2-SV-14-2E 3 REL 1 SA L/1 C 3 A C TF1 TF-1

2-SV-14-2N 3 REL 1 SA H/1 C 3 A C TF1 TF-1 R NO

2-SV-15-2E 3 REL 0. 75 SA G/3 C 3 A C TF1 TF"1

2-SV-15-2W 3 RE L 0. 75 SA J/4 C A C TF-1 TF-1 R NO

2-SV-16-AB 3 RE L 1 SA L/8 C A C TF-1 TF-1

2-SV-16-CD 3 REL 1 SA L/8 C 3 A C TF1 TF-1 R NO

2-l00-703-2E 3 BF 20 HO N/8 C 3 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

Page 167: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0 0 0 0 0 4 0

Page 168: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLOW DZASH: 2"5113-36

RUN DATE AND TIME: 15FEB90:16:10

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-WHO-704-2H 3 BF 20 HO H/8 C 3 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-WHO-706 3 BF 20 HO G/8 0 0/C 3 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-WHO-708 3 BF 20 MO G/6 0 0/C 3 A B EF"1EF-5ET"XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-WHO-714 3 BF 12 HO H/5 C 3 A B EF1EF-5ET-XXX

EF-1EF "5ET-XXX

P NONO

P NO

2-WHO-718 3 BF 12 HO N/5 C 3 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2"WHO-722 3 BF 6 HO H/6 C 3 A B EF1 EF"1EF"5 EF-5ET-XXX ET-XXX

P NONO

P NO

2-WHO-724 3 BF 6 MO H/6 C 0 3 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

Page 169: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e a e e 0 o e .0 e e 0

Page 170: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLON DIAGRAH: 2-5113-36

~ ~RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. t PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE

2-HHO-726 3 BF 6 HO K/6 C A B EF1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

P NO

2-lOO-728 3 BF 6 HO L/6 C 3 A 8 EF-1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

P NO

. 2"NHO-734 3 BF 16 HO H/3 0/C 0 3 A B EF-)EF-5ET-XXX

EF-'1EF-5ET-XXX

P NONO

2-NHO-738 3 BF 16 HO K/3 0/C 0 3 A B EF1 EF-1 P NOEF-5ET"XXX

EF-5ET-XXX

NOP NO

2-NHO-744 3 BF HO J/6 C 3 A B EF1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

P NO

2-NHO-753 3 BF 6 HO H/5 C 3 A B EF1 EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

P NO

2-NHO-754 3 BF 4 HO K/6 C . 3 A B EF-1 „EF-1EF-5 EF-5ET-XXX ET-XXX

P NONO

Page 171: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o e e eI

0

0 0 0 0 0 0 0 0 0

Page 172: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: ESSENTIAL SERVICE HATER

tDONALD C. COOK NUCLEAR PLANT

SECOND TEN YEAR INTERVALVALVE SUMMARY SHEET - UNIT 2

FLOH DIAGRAM: 2-5113-36

VALVE I VALVE POSITION I ASME SECTION XZ

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-HRV-722-CD 3 3W A K/8 0 A B EF1EF-7ET-XXX

NOTE 3EF-8NOTE 3

P YES> NOTE 3R YES'OTE 3

YESp NOTE 3

2-HRV-724-CD 3 3H 4 A M/8 0 3 A B EF1EF-7ET-XXX

NOTE 3EF-8NOTE 3

P YES> NOTE 3R YESi NOTE 3

YES> NOTE 3

2-HRV"726-AB 3 3H A K/8 0 3 A B EF1EF-7

NOTE 3EF-8

P YES> NOTE 3R YES> NOTE 3

ET-XXX NOTE 3 YES> NOTE 3

2-HRV-728-AB 3 'H A M/8 0EF-7ET-XXX

EF-8NOTE 1

3 A B EF1 NOTE 3 P YESp NOTE 3R YESi NOTE 3

YESp NOTE 3

Page 173: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o e e e e e o e e o e e e e 0

Page 174: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEN NAME: NON-ESSENTIAL SERVICE HATER

tDONALD C. COOK NUCLEAR PLANT

SECOND TEN YEAR INTERVALVALVE SLMARY SHEET - UNIT 2

FLON DIAGRAN: 2-5114A-27

VALVE I VALVE POSITION I ASNE SECTION XI

HURLER REV TYPE SIZE ACT F.D- I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUHCT ICL

PRIH TEST TEST TEST RELIEF REQUEST(S)REQUIRED - PERFORNED NODE

2-WCR-900-1 3 DA 6 A J/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P NOP NOR YESi NOTE 1

2-HCR-901-1 3 DA 6 A K/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP HOP NOR YES> NOTE 1

, 2-NCR"902-1 3 DA 6 A J/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YES> NOTE 1

2-NCR-903-1 3 DA 6 A K/4 0 2 A A EF"1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HONO

P HOP NOR YES> NOTE 1

2-NCR-904-2 3 DA 6 A J/9 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> HOTE 1

Page 175: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o e e e e o e e e e 0

Page 176: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEH NAHE: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUYiiARY SHEET - UNIT 2FLOW DIAGRAH: 2-5114A-27

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUHBER REV TYPE SIZE ACT F ~ D I POWER SAFETY I CD A/P CATTYPE COORDI OPER FUNCT ICL

PRZH TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED NODE

2-HCR-905-2 3 DA 6 A K/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF.-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-HCR-906-2 3 DA 6 A J/4 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP NOP NOR YES1 NOTE 1

2-HCR-907 3 DA 6 A K/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NOR YES> NOTE 1

2-HCR-908-3 3 DA 6 A J/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT"2

P NONO

P NOP NOR YES> NOTE 1

2-HCR"909-3 3 DA 6 A K/9 0 C„ 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YES> NOTE 1

Page 177: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0(

0 o e o e e e e e e e e e o e e 0

Page 178: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEM NAME: NOH-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5114A-27

RUH DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTIOH XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CATTYPE COORD I OPER FACT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2"NCR-910-3 3 DA 6 A J/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF"7ET-XXXSLT-2

P NOHO

P NOP HOR YES> NOTE 1

2-NCR-911-3 3 DA 6 A K/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP NOP HOR YES> NOTE 1

2-NCR-912-4 3 DA 6 A J/9 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P NO'P NOR YES> NOTE 1

2-NCR-913-4 3 DA 6 A K/9 0 2 A A EF-1EF-5EF-7ET"XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P NOP HOR YES> NOTE 1

2-NCR-914 "4 3 DA 6 A J/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NO

HO

P HOP HOR YES'OTE 1

Page 179: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e a 0 o e 0

~,

0

Page 180: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEN NAHE: HON-ESSENTIAL SERVICE HATER

tDONALD C. COOK NUCLEAR PLANT

SECOND TEN YEAR INTERVALVALVE SWARY SHEET - WIT 2

FLON DIAGRAN: 2-511%A"27

RUN DATE AND TINE: 15FEB90tl6:14

VALVE I VALVE POSITION I ASNE SECTION XI

HUNBER REV TYPE SIZE ACT F.D. I PONER SAFETY |CD A/P CATTYPE COORD I OPER FUNCT ICL

PRIN TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORNED NODE

2-HCR-915-0 3'A 6 A K/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF"7

„,

ET-XXXSLT-2

P NOHO

P HOP hOR YESi NOTE 1

2-HCR-920-1 3 DA A J/6 0 2 A A EF-1EF-5EF"7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P HOP NOR YES> NOTE 1

2-HCR-921-1 3 DA A K/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P HOP NOR YES> NOTE 1

2-HCR-922-1 - 3 DA 3 A K/2 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-NCR-923-1 3 DA 3 A J/2 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1 P HOEF-5 HOEF-7 P NOET-XXX P HOSLT-2 R YES@ NOTE 1

Page 181: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e e e o e o e o o e o o e e ~

Page 182: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SURtARY SHEET - UNIT 2FLOH DIAGRAM: 2-5114A-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUYBER REV TYPE SIZE ACT F.D. I POHER SAFETY tCD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-HCR-924-2 3 DA 3 A J/6 0 2 A A EF-1 EF-1EF-5 EF-5EF-7 EF-7ET-XXX ET-XXX

P NONO

P NOP NO

SLT-1 SLT-2 R YES> NOTE 1

2-HCR-925-2 3 DA 3 A K/6 0 2 A A EF-1 EF-1 P NOEF"5 EF-5EF-7 EF-7ET-XXX ET-XXXSLT-1 SLT-2

NOP NOP NOR YESp NOTE 1

2-HCR-926-2 3 DA A K/2 0 2 A A EF-1 EF-1EF-5 EF"5

P NONO

EF-7ET"XXXSLT-1

EF-?ET-XXXSLT-2

P NO

P NO

R YES> NOTE 1

2-HCR-927-2 3 DA A J/2 0 2 A A EF-1 EF-1EF"5 EF-5EF-7 EF-7

P NO

NOP NO

ET-XXXSLT-1

ET"XXXSLT-2

P NO

R YESp NOTE 1

2"HCR-928"3 3 DA 3 A J/6 0 2 A A EF-1 EF-1EF-5 EF"5EF-7 EF-7ET-XXX ET-XXXSLT-1 SLT-2

P NONO

P NOP NOR YESp NOTE 1

Page 183: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o o e e o e e e e e e e e o e 0

Page 184: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2FLOH DIAGRAM: 2-5114A-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.DE I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM 'TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-HCR-929-3 3 DA 3 A K/6 0 2 A A EF-1EF-5EF"7ET-XXXSLT-1

EF-1EF"5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-HCR-930-3 3 DA 3 A K/2 0 2 A A EF-1EF-5EF"7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NO

P NO

P NOR YESp NOTE 1

2-HCR-931-3 3 DA 3 A J/2 0 2 A A EF"1EF-5EF"7ET-XXXSLT-1

EF"1EF-5EF-7ET"XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-HCR"932% 3 DA 3 A J/6 0 2 A A EF-1EF-5EF-7ET-XXX .

SLT-1

EF-1-EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YESp NOTE 1

2-HCR"933 3 DA 3 A K/6 0 2 A A EF-1EF-5EF-7ET-XXX

'LT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

Page 185: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

, e o e e e e e e a e e

0 o o e e e o e o o e o e o e a

Page 186: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-5114A-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POWER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT lCL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-HCR-934 3 DA 3 A K/2 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF"5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-HCR-935 3 DA' A J/2 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP NOP NOR YES> NOTE 1

2-HCR-941-1 3 DA 3 A J/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF "1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NO

R YES> NOTE 1

2-HCR-942-2 3 DA 3 A J/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-HCR-943-3 3 DA 3 A J/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF"7ET-XXXSLT"2

P NO

NO

P NOP NOR YES> NOTE 1

Page 187: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o e e 0 o e a e e o e e

Page 188: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

]II

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

'ALVE SUMMARY SHEET - UHIT 2FLOW DIAGRAM: 2-5114A-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITZOH I ASME SECTION XI

HUYBER REV TYPE SIZE ACT F.D. t POWER SAFETY ICD A/P CATTYPE COORDI OPER FUHCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-WCR-944-4 3 DA 3 A J/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P HOP NOR YES> NOTE 1

2"WCR-945 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

HOP NOP NOR YES> NOTE 1

2-WCR-946-2 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NOR YES> NOTE 1

2-HCR-947"3 3 DA 3 A J/3 0 2 A A EF"1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-mSLT-2

P NOHO

P HOP NOR YES> NOTE 1

2-WCR-948-4 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P NOP HOR YES> NOTE 1

Page 189: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 190: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH HAHE: NON-ESSENTIAL SERVICE WATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUGARY SHEET — i%IT 2FLOW DIAGRAH: 2-511%A-27

RUH DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUNBER REV TYPE SIZE ACT F AD t POWER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIN TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED NODE

2-WCR-951 3 DA 3 A K/6 0 2 A A EF"1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-WCR-952-2 3 DA 3 A K/6 0 2 A A EF-1EF"5EF"7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NO

P. NO

P HO

R YESp NOTE 1

2-WCR-953-3 3 DA A K/6. 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NO

R YES'OTE 1

2-WCR-954-4 3 DA 3 A K/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

2-WCR-955 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HO

HOP NOP NOR YES> NOTE 1

Page 191: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 a a 0 o a e a

0 e o o e e e e o o e e e e e 0

Page 192: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

-

SYSTEN NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE 'SUWRY SHEET - UNIT 2FLOH DIAGRAN: 2-5114A-27

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY !CD A/P CATTYPE COORDI OPER FUNCT ICL

PRIN TEST TEST TEST RELIEF REQUEST(S)REQUIRED PER FORHED VADE

2-HCR-956-2 3 DA A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT-2

P HONO

P NOP HOR YES> NOTE 1

2-HCR-957-3 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF-7ET-XXXSLT-2

P NOHO

P HO

P NOR YES'OTE 1

2-HCR-958-4 3 DA 3 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOP NO

R YES> NOTE 1

2-HCR-960 3 DA 2 A J/7 0 2 A A EF-1Ef-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NOR YES> NOTE 1

2-NCR-961 3 DA 2 A J/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P NOP HOR YES> NOTE 1

Page 193: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 a o N e o e 0 e 0 e

Page 194: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5114A-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE VALVE POSITION ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-HCR-962 3 DA 2 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES) NOTE 1

2-NCR-963 3 DA 2 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP HO

,P HOR YESi NOTE 1

2-HCR"964"3 3 DA 2 A J/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P NO

P HOR YESp NOTE 1

2-NCR-965-3 3 DA 2 A J/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF"1EF-5EF-7ET-XXXSLT-2

P HONO

P NOP HOR YES> NOTE 1

2-NCR-966-3 3 DA 2 A J/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOND

P HOP NOR YES7 NOTE 1

Page 195: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e e 0 e o e e a e .0

0 0 0 0 0 0 0 0

Page 196: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

lll

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SmDlARY SHEET - UNIT 2FLON DIAGRAM: 2-5116A-27

RUN DATE AND TIME: 15FEB90l16l10

VALVE I VALVE POSITION I ASHE SECTION XZ

NUMBER REV TYPE SIZE ACT F.D. I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-HCR-967-3 3 DA 2 A J/3 0 2 A A EF1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

Page 197: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ 0 ~ ~ 0 0 0 0 ~ ~ ~ 0 ~ ~ ~ 0 ~

Page 198: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: STATION DRAINAGE - CONTAINMEHT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SRQRRY SHEET - UNIT 2FLOH DIAGRAM: 2-5124-20

RUN DATE AND TIME: 15FEB90:16:14~ ~

VALVE I VALVE POSITION i ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE

2-DCR-600 3 DA A N/6 0 2 A A EF1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P NOP NOR YESp NOTE 1

2-DCR-601 3 DA 3 A N/6 0 2 A A EF1EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF-7ET-XXXSLT-2

HOP HOP HOR YESp NOTE 1

2-NS-357 3 CK 0.5 SA K/9 C 0/C A 2 A AC CF-1SLT-1

CF-2SLT-2

R YESp NOTE 2R YES> HOTE 1

Page 199: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e 0 e e e e e e e e e e

0

0 o e o e e e e e o e e e e e e 0

Page 200: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: REACTOR COOLANT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUYHARY SHEET — UNIT 2FLON DIAGRAH: 2-5128-19

RUN DATE AND TINE: 15FEB90:16:10

VALVE I VALVE POSITZON I ASHE SECTION XZ

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE

2-NSO-021 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2EF-5 EF-5EF-7 EF-8ET-XXX ET-XXX

C NOp CSJ 1NOp CSJ 1„

C NOp CSJ 1C NOp CSJ 1

2-NSO-022 3 GL 1 SO J/6 C 0/C ,2 A B EF-1 EF-2EF-5 EF-5

NOp CSJ 1NOp CSJ 1

EF-7ET"XXX

EF-8ET-XXX

C NOp CSJ 1C NOp CSJ 1

2-NSO-023 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2EF-5 EF-5EF"7 EF-8ET-XXX ET-XXX

C NOp CSJ 1NOp CSJ 1

C NOp CSJ 1C NOp CSJ 1

2-NSO-024 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2EF-5 EF-5

C NOp CSJ 1NOp CSJ 1

EF-7ET-XXX

EF-8ET-XXX

C NOp CSJ 1C NOp CSJ 1

Page 201: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

0 0- 0 0 0 0 0

Page 202: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: REACTOR COOLANT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5128A-34

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUM3ER REV - TYPE SIZE ACT F.D. I PONER SAFETY I CD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

Z-CS-442-1 3 CK 2 SA B/4 0 A AC CF-1SLT-1

CF"2SLT-2

R YES> NOTE 1R YES> NOTE 2

2"CS~Z-2 3 CK 2 SA B/4 0 2 A AC CF-1SLT-1

CF-2SLT-2

R YES> NOTE 1R YES'OTE 2

2-CS-44Z-3 3 CK 2 SA B/4 0 2 A AC CF-1SLT-1

CF-2SLT-2

R YES> NOTE 1R YES> NOTE 2

2-CS-442-4 3 CK 2 SA B/4 0 2 A AC CF-1SLT-1

CF-2SLT-2

R YES> NOTE 1R YES> NOTE 2

2-GCR-301 3 DA 0. 75 A B/8 0 2 A A EF-1 EF-1EF-5 EF-5EF-7 EF"7ET-XXX ET-XXXSLT-1 SLT-2

P NONO

P NOP NOR YES> NOTE 2

2"N-159 CK 0.75 SA C/8 0/C C 2 A AC CF-1SLT-1

CF-2—SLT-2

R YES> NOTE 5R YES'OTE 2

2-NCR-252 3 GL A B/9 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NOR YES> NOTE 2

2-NHO-151 3 GA 3 HO K/7 0 1 A B EF-1 EF-1EF-5 EF-5ET-XXX ET-XXX

Page 203: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o e o e a

, 0 0 0 0 0 0 0 0 0 0

Page 204: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Ill

0

SYSTEH NAME: REACTOR COOLANT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMHARY SHEET - UNIT 2FLOH DIAGRAM: 2-5128A-34

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F AD I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-%)0-152 3 GA 3 MO K/7 0 1 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-HYA)-153 3 GA MO K/6 0 1 A B EF"1EF"5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-NPX-151 3 GL 0 5 H N/8 C 2 P A SLT-1 SLT-2 R YES> NOTE 2

2"NRV-151 3 GL 3 A K/7 C C/0 1 A B EF-1EF-5EF-7ET-XXX

EF"2Ef-5EF-8ET-XXX

NO> CSJ 3NONO> CSJ 3NO> CSJ 3

2-NRV-152 3 GL 3 A K/7 C C/0 . 1 A B EF-1EF-5EF"7ET-XXX

EF-2EF-5EF-8ET-XXX

NO> CSJ 3NONOp CSJ 3NO> CSJ 3

2-NRV-153 3 GL A K/6 C C/0 1 A B EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

NO> CSJ 3NONO> CSJ 3NO> CSJ 3

2-NSO-061 3 GL 1 SO H/6 C 0/C 2 A B EF-1EF"5EF-7ET-XXX

EF-2EF-5EF-8ET"XXX

C NO> CSJ 6NO> CSJ 6

C NO> CSJ 6C NO> CSJ 6

Page 205: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0 0 0 0 0 0 0

Page 206: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: REACTOR COOLANT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUYMARY SHEET - UNIT 2F LON DIAGRAH: 2-5128A-Wt

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIH TEST TEST TEST RELIEF REQUEST<S)REQUIRED PERFORHED NODE

2-NSO-062 3 GL 1 SO H/6 C 0/C 2 A 8 EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

C NOp CSJ 6NOp CSJ 6

C NOp CSJ 6C NOp CSJ 6

2"NSO-063 3 GL 1 SO H/6 C 0/C 2 A 8 EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

C NOp CSJ 6NOp CSJ 6

C NOp CSJ 6C NOp CSJ 6

2-NSO-064 3 GL 1 SO H/6 C 0/C , 2 A 8 EF-1EF-5EF-7ET-XXX

EF-2EF-5EF-8ET-XXX

C NOp CSJ 6NOp CSJ 6

C NOp CSJ 6C NOp CSJ 6

2-PN-275 3 CK 3 SA 8/9 0/C C 2 A AC CF-1SLT-1

CF-2SLT-2

R YESp NOTE 0R YESp NOTE 2

2-RCR-100 GL 0.375 A 8/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 2

2-RCR"101 3 GL 0.375 A 8/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 2

Page 207: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 '

0 0 0 0 0 0 0 0 0 0 0 0

Page 208: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAHE: REACTOR COOLANT

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUKIARY SHEET - UNIT 2FLON DIAGRAM: 2-5128A-34

RUN DATE AND TIME? 15FEB90:16:14

VALVE I VALVE POSITION t ASHE SECTION XI

tilPSER REV TYPE SI2E ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST REL1EF REtQESTlS)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE

2-SI-189 3 CK SA D/7 C 0/C 2 A AC CF-1SLT-1

CF-2SLT-2

R YES> NOTE 7R YES> NOTE 2

2-SV-45A 3 REL 6 SA K/6 C 1 A C TF-1 TF-1 R NO

2-SV-45B 3 REL 6 SA J/6 C 1 A C TF1 TF-1 R NO

2-SV-45C 3 REL 6 SA N/6 C 1 A C TF1 TF-1 R NO

2-SV-50 3 REL 2 SA 6/3 C A C TF-1 TF-1 R NO

Page 209: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 210: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: CVCS - LETDOHN 8 CHARGING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLOH DIAGRAH: 2-5129-32

RUiN DATE AND TINE: 15FE890:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUiiBER REV TYPE SIZE ACT F ~ D ~ f POHER SAFETY (CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUiNCT ICL REQUIRED PERFORHED NODE

2-CS-292 3 CK 2 SA H/6 C 0/C 2 A C CF-1 CF-2 C YESi NOTE 1

2-CS"297-E 3 CK 2

, 2-CS"297-H 3 CK 2

SA H/7 0/C 0

SA F/7 0/C 0

2 A C CF-1

2 A C CF1

CF-1

CF-1 P NO

2-CS-299-E 3 CK SA H/7 0 0/C 2 A AC CF-1SLT-1

CF-3SLT-1

P YESi NOTE 2R NOi NOTE ll

2-CS-299-H . 3 CK 4 SA F/7 0 0/C 2 A AC CF-1SLT"1

CF-3SLT-1

P YESi NOTE 2R NOi NOTE 11

2-CS-321 3 CK SA E/3 0 C/0 2 A AC CF-1SLT-1

CF-2SLT-2

YESi NOTE 4R YESi NOTE 3

2-CS"328-Ll 3 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P NOi NOTE 5

2-CS-328-L4 3 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P NOi NOTE 5

2-CS-329-Ll 3 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P 'oi NOTE 5

2-CS-329-L4 3 CKi 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P Noi NOTE 5

2-IHO-360 3 GA HO J/6 C 2 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NO

NOP NO

Page 211: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 212: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Ill

0

SYSTEH NAME: CVCS — LETDOHN 8 CHARGING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5129-32

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XZ

'" NUMBER REV TYPE SIZE ACT F.D. I PONER SAFETY )CD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED MODE

2-ZMO-910 3 GA 8 MO L/5 C 2 A B EF-1EF"5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IMO-911 ~ 3 GA 8 MO L/6 C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-QCR-300 3 GL 2 A E/1 0 = C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 6NO

C NOp CSJ 6C NOp CSJ 6R YESp NOTE 3

" 2-QCR-301 3 GL 2 A E/1 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 6NO

C NOp CSJ 6C NOp CSJ 6R YESp NOTE 3

2-QMO-200 3 GA 3 MO J/3 0 0/C 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 7NO

C NOp CSJ 7

2-QHO-201 3 GA 3 MO J/3 0 0/C 2 A B EF-1EF-5ET-XXX

EF"2EF-5ET-XXX

C NOp CSJ 7NO

C NO, CSJ 7

2-QHO-225 3 GA 2 MO J/7 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

Page 213: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e e e e e e e e o e 0

Page 214: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: CVCS - LETDOHN 8 CHARGING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET — UNIT 2FLOH DIAGRAM: 2-5129-32

RUN DATE AND TIME: 15FEB90:16:10

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SI2E ACT F AD I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-QMO-226 3 GA 2 MO G/7 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2=QRV-200 3 GL 3 A H/3 0 2 A B EF1EF-5EF-7—ET-XXX

EF-3EF-5NOTE 8NOTE 8

P NO> NOTE 8YES> NOTE 8YES~ NOTE 8YES NOTE 8

2-QRV-251 3 GL 3 A N/5 0 2 A B EF1EF-5EF"7ET-XXX

EF-3EF-5EF-8NOTE 9

P NO> HOTE 9YES NOTE 9YES> NOTE 9YES> NOTE 9

2-QRV-61 3 GL A C/2 C 0 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NO

2-QRV-62 3 GL 3 A C/2 0/C 0 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-$EF-7ET-XXX

P NOHO

P NO

P NO

2-SI-185 3 CK 8 SA K/5 C 2 A C CF-1 CF-2 R YES> NOTE 10

2-SV-51 REL 2 SA E/2 C 2 A C TF-1 TF-1

Page 215: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o e e e 0

E (

0 e o o e e e o e o o a e o e e 0

Page 216: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEH NAHE: CVCS - LETDOHN 8 CHARGZNG

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

- VALVE SUYNARY SHEET .- UNIT 2FLON DZAGRAH: 2-5129"32

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

tiVHBER REV TYPE SI2E ACT F ~ D I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST< S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE

2"SV-52 REL 2 SA K/1 C 2 A C TF1 TF-1 R NO

2-SV-55 3 REL 0.75 SA K/7 C 2 A C TF-1 TF-1

2-SV-56 3 REL 0.75 SA L/6 C 2 A C TF1 TF-1 R NO

Page 217: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0 0 0 ~ 0 0 0 0

Page 218: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: CVCS - LETDONH 8 CHARGING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE Sly4ARY SHEET — UHIT 2FLON DIAGRAM: 2-5129A-20

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE

2-QCH-250 3 GA MO C/8 0 2 A A EF-1EF-5ET-XXXSLT-1

EF"2EF-5ET-XXXSLT-2

C NOp CSJ 1HO

C NOp CSJ 1R YESp NOTE 2

2-QCM-350 3 GA HO D/8 0 2 A A EF1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1HO

C NOp CSJ 1R YESp NOTE 2

2-QMO-451 3 GA HO J/5 0 2 A B EF1EF-5ET"XXX

EF-2EF-5ET-XXX

C HOp CSJ 3NO

C NOp CSJ 3

2-QMO-452 3 GA MO J/5 0 2 A B EF1EF-5ET-XXX

EF-2EF-5ET-XXX

C HOp CSJ 3HO

C NOp CSJ 3

2-QRV-400 - 3 GL 2 A K/4 C 2 A B EF-1EF-5EF-7ET"XXX

EF-1EF-5EF-7ET-XXX

P NOP NO

2"SV-53 REL 3 SA M/2 C 2 A C TF-1 TF-1

2-SV-54' REL 2 SA E/4 C 2 A C TF-1 TF-1 R NO

Page 219: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e 0 o e o

Page 220: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: COHPONENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLON DIAGRAH: 2-5135"34

RUN DATE AND TINE: 15FEB9D:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY (CD A/P CATTYPE COORDI OPER FUiiCT ICL

PRIH TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED NODE

2-CCH-451 3 BF 8 HO E/4 0 2 A A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-CCH-452 3 BF 8 HO E/5 0 2 A A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-CCH-453 3 GL HO E/4 0 2 A A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-CCH-454 3 GL HO E/5 0 2 A A EF"1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-CCH-458 3 BF 8 HO A/2 0 2 A A EF-1EF-5ET"XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-CCH-459 3 BF 8 HO B/2 0 2 A A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

Page 221: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 222: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: COMPONENT COOLIHG

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UHIT 2FLOH DIAGRAM: 2-5135-34

RUH DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUYBER REV TYPE SIZE ACT F-D ~ I POHER SAFETY ICD A/P CATTYPE COORD I OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-CCRW55 3 GL ' A B/3 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 3NO

C HOp CSJ 3C NOp CSJ 3R 'ES NOTE 2

2-CCR-456 3 GL 2 A D/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-2EF-5EF-8ET-XXXSLT-2

C HOp CSJ 3NO

C NOp CSJ 3C HOp CSJ 3R YESp NOTE 2

2-CCR-457 3 GL 2 A D/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF"2EF-5EF-8ET-XXXSLT-2

C NOp CSJ 3NO

C NOp CSJ 3C HOp CSJ 3R YESp NOTE 2

2-CCR-460 3 GL 3 A C/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOHO

P HOP NO

R YESp NOTE 2

2-CCR-462 3 GL 3 A A/4 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 2

Page 223: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o e o e o e e e o e e e e e 0

Page 224: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEM NAME: COMPOHENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2F LOH DIAGRAM: 2-5135-34

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUiiBER REV TYPE SIZE ACT F.D ~ I PONER SAFETY ICD A/P CAT PRIM TEST TEST . TEST RELIEF REQUEST(S)TYPE COORD I OPER FUHCT ICL REQUIRED PERFORMED MODE

2-CCH-135 3 CK 2.5 SA B/3 0 2 A AC CF-1SLT-1

CF-2SLT"2

R YES) NOTE 4R YESp NOTE 2

2-CRV-445 3 BL 6 A L/5 0 C/0 3 A B EF-1 EF-1EF-5 EF-5EF-7 EF-7ET-XXX ET-XXX

P NONO

P NOP NO

2-CRV-470 3 GL 6 A G/1 0 3 A B EF1E F-5EF-7ET"XXX

EF-1NOTE 5HOTE 5NOTE 5ii

P NO> NOTE 5YES> NOTE 5YES'OTE 5YESp NOTE 5

2-CRVW85 3 BF 10 A B/7 0 A B EF1 EF-1EF"5 EF-5EF-7 EF-7ET-XXX ET-XXX

P NOHO

P NOP HO

2-SV-122 3 REL 1 SA D/3 C , 0 3 A C TF1 TF-1

'-SV-62-1 3 REL 1 SA D/3 C

2-SV-62-2 3 REL 1 SA D/3 C

A C TF 1

A C TF-1

TF-1

TF-1 R HO

2-SV-62-3 3 REL 1 SA D/3 C 3 A C TF-1 TF»l R HO

2-SV-62< 3 REL 1 SA D/3 C A C TF1 TF-1 R HO

Page 225: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0 0

Page 226: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEM NAME: COMPONENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-5135-34

RUN DATE AND TIME: 15FE890:16:14

VALVE VALVE POSITION ASME SECTION XZ

W

NUMBER REV TYPE SIZE ACT F ~ D I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-SV-63 REL 1 SA E/3 C A C TF-1 TF-1 R NO

2-SV-64 REL 1 SA C/3 C 3 A C TF-1 TF-1 R NO

2-SV-65 3 REL 1 SA K/I C 3 A C TF-1 TF-1

2-SV-68 3 REL 1 SA J/2 C A C TF1 TF-1

2-SV-71 3 'EL 1 SA L/3 C 3 A C TF-1 TF-1 R NO

Page 227: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e

0 0 0 0 0 0 0 0 0 0

Page 228: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

"

SYSTEM NAHE: COMPONENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHMARY SHEET - UNIT 2FLON DIAGRAM: 2-5135A-30

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY )CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED 'ERFORMED MODE

2-CCH-176-E 3 CK 16 SA L/4 C/0 0 3 A C CF1 CF-1

2-CCN-176-N 3 CK 16 SA K/4 C/0 0 A C CF1 CF-1

2-CHO-410 3 BF 16 HO M/4 C/0 0 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-CHO-411 3 BF 18 HO H/5 0 3 A B EF-1EF-5ET-XXX

EF-1E F-5ET-XXX

P NONO

P NO> NOTE 1

2 CHO 412 3 BF 16 HO L/3 0 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO> NOTE 1

2-CHOW13 3 BF 18 HO L/5 0 3 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P

P

NONONOp NOTE 1

2-CHO &14 3 BF 16 HO K/3 0 3 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX P NO> NOTE 1

2-CHO-415 3 BF 16 HO M/5 0 3 A B EF-1EF-5ET-XXX

EF-1EF-5ET"XXX

P NONO

P NOi NOTE 1

Page 229: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 230: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: COHPONENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5135A-30

RUN DATE AND TINE: 15FEB90:16:14

VALVE t VALVE POSITION I ASHE SECTION XI

HUiiBER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

'2-CHO-416 3 BF 16 HO G/5 0 3 A 8 EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO> NOTE 1

2-CHO-419 3 BF 14 HO E/5 C 3 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NO

NOP NO

2-CHO-420 3 BF 16 HO H/4 C/0 0 3 A 8 EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-CMO-429 3 BF 14 HO E/5 C 0 3 A 8 EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

NOP NO

2-CRV-412 3 GL A K/1 0 A 8 EF-1EF-5EF"7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-SV-60 3 REL 3 SA L/1 C 3 A C TF"1 TF-1 R NO

2-SV-72 REL 1 SA E/5 C 3 A C TF-1 TF-1

Page 231: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o e e e e e e e e o e e e e a

Page 232: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 233: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o e e e e e e 0

*I

II

0

0 o e e o e e o o e e e o o e e

Page 234: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

ill~ ~

SYSTEM NAME: COMPONENT COOLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2FLOH DIAGRAM: 2-5135B-14

RUN DATE AND TIME: 15FEB9Dp16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SI2E ACT F.D. I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-CCH-243"25 3 CK 1 SA C/5 0 2 A AC CF-1 CF-2SLT-1 . SLT-2

R YESp NOTE 2R YESp NOTE 1

2-CCH-Kt3-72 3 CK 1 SA C/5 0 2 A AC CF-1 CF-2SLT-1 SLT-2

R YESp NOTE 2R YESp NOTE 1

2-CCH-ZVt-25 3 CK 1 SA C/6 0 2 A AC CF-1SLT-1

CF-2SLT-2

R YES) NOTE 2R YESp NOTE 1

2-CCH-WA-72 3 CK 1 SA C/6 0 2 A AC CF 1SLT"1

CF-2SLT-2

R YESp NOTE 2R YESp NOTE 1

2-SV-122-25B 3 RE L 1. 5 SA B/6 C 3 A C TF-1 TF-1 R NO

2-SV-122-72B 3 REL 1.5 SA B/6 C 0 3 A C TF-1 TF-1 R NO

Page 235: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e e e

0

0 0 0 0 0 0

Page 236: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NUCLEAR SAMPLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5141-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

,

NUHBER REV TYPE SIZE ACT F D. I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-ZCR-5 3 GL 0.5 A C/5 0 C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES NOTE 1

2-ICR-6 3 GL 0.5 A . D/5 0 C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-NCR-105 3 GL 0.5 A C/7 0 C 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YES> NOTE 1

2-NCR "106 GL 0.5 A C/7 0 C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES'OTE 1

2-NCR"107 3 GL 0.5 A D/6 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YESp NOTE 1

Page 237: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 238: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I I I

SYSTEM NAME: NUCLEAR SAMPLING

DONALD CD COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET —UNIT 2FLOH DIAGRAM: 2-5101-27

RUN DATE AHD TIME: 15FEB90:16:10

VALVE I VALVE POSITION I ASME SECTION XZ

NUMBER REV TYPE SIZE ACT F AD. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-NCR"108 3 GL 0.5 A D/6 0 2 A A EF1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES'OTE 1

2-NCR-109 3 GL 0.5 A D/5 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF-7ET-XXXSLT-2

HOP HO

P HOR YES> NOTE 1

2-HCR-110 3 GL 0.5 A D/6 0 2 A A EF1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT"2

P HO

P HO

R YES> NOTE 1

Page 239: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 0 0 0 0 0 0 0 0

Page 240: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NUCLEAR SAMPLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLOH DIAGRAM: 2-5141A-30

RUN DATE AND TIME: 15FE890:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT lCL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED MODE

2-DCR-301 3 GL'.5 A 8/2 0 2 A 8 EF-1EF-5EF-7ET-XXX

EF"1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-DCR-302 3 GL 0.5 A 8/3 0 2 A 8 EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2"DCR-303 3 GL 0.5 A 8/3 0 2 A 8 EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

NONO

P NOP NO

2-DCR"304 3 GL 0.5 A 8/3 0 2 A 8 EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-MCR-251 3 GL 0.5 A 8/2 0 2 A 8 EF-1EF-5EF"7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NOP NO

2-HCR"252 GL 0.5 A 8/2 0 2 A 8 EF-1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NO

P NO

Page 241: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e e 0 e e e e e e e o o e e

0 e a e e o o o o o e e o e e 0

Page 242: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: NUCLEAR SAMPLING

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2"5141A-30

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. t PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-HCR-253 3 GL 0.5 A B/1 0 2 A B EF1EF-5EF-7ET-XXX

EF-1 P NOEF-5 NOEF-7 — P NOET-XXX P NO

2-MCR-254 3 GL 0.5 A 8/1 0 2 A 8 EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NONO

P NO

P NO

Page 243: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e e e 0 «a e o e o e e e e

0

o ~ e o o o e ~ ~ ~ e ~ ~ o o e~

Page 244: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: PAS CONTAINMENT HYDROGEN

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUKULRY SHEET - UNIT 2FLOH DIAGRAM: 2-51410-8

RUH DATE AHD TIME: 15FE890:16:10

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CATTYPE COORD I OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST[ S)REQUIRED PERFORMED MODE

2"ECR"10 GL 0.5 A C/8 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF"5EF-7ET-XXXSLT-2

P NONO

P HOP- NOR YES> NOTE )

2-ECR-ll 3 GL 0.5 A A/2: C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

HO

P NO

P NOR YESp NOTE 1

2-ECR"12 3 GL 0.5 A A/2 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NOP HO

R YES> NOTE 1

2-ECR-13 GL 0.5 A A/1 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YES> NOTE 1

2"ECR-10 3 GL 0.5 A A/3 C 0/C 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP HOR YES> NOTE 1

Page 245: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

, e a 0 e e e e

0

Page 246: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

-

SYSTEM NAME: PAS CONTAINMENT HYDROGEN

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUSRY SHEET — UNIT 2FLON DZAGRAH: 2-5141D-8

RUN DATE AND TZHE: 15FEB90:16:14

VALVE VALVE POSITION ASME SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY I CD A/P CATTYPE COORD I OPER FUNCT ICL

PRIH TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED MODE

2-ECR-15 3 GL 0 5 A A/1 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES'OTE 1

2-ECR-16 3 GL 0.5 A A/3 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-ECR-17 3 GL 0.5 A A/3 C 0/C 2 A A EF-1EF-5

EF"1EF-5

P NONO

EF-7ET"XXXSLT-1

EF-7ET-XXXSLT-2

PPR

NONO

YES> NOTE 1

2"ECR"18 GL 0 5 A A/4 C 0/C 2 A A EF"1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NOR YES> NOTE 1

2-ECR-19 3 GL 0.5 A A/4 C 0/C 2 A A EF-1EF-5EF-7ET"XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

Page 247: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0 0 0

Page 248: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: PAS CONTAINMENT HYDROGEN

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-51010-8

VALVE I VALVE POSITION I ASME SECTION XI

NUTTER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

'2-ECR-20 3 GL 0.5 A C/8 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES>, NOTE 1

2-ECR-21 GL 0.5 A B/2 C 0/C 2 A A EF-1E F-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET"XXXSLT"2

P NONO

P NO

P NOR YES'OTE 1

2-ECR-22 3 GL 0.5 — A B/2 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NO

P NO

R YES> NOTE 1

2-ECR"23 3 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-1EF-5 EF-5EF-7 EF-7

P NONO

P NOET-XXXSLT-1

ET-XXXSLT-2

P NO

R YESp NOTE 1

2 "ECR-Vt 3 GL 0.5 A B/3 C 0/C 2 A A EF-1 EF"1EF-5 EF-5EF-7, EF-7ET-XXX ET-XXX

SLT-2SLT-1

P NONO

P NONO

R YES> NOTE 1

Page 249: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o e o e e e e e e e e e 0

Page 250: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NANE: PAS CONTAINMENT HYDROGEN

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUGARY SHEET - UNIT 2FLOH DIAGRAN: 2"5141D-8

VALVE I VALVE POSITION I ASNE SECTION XI

HUNBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIN TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORNED NODE

2-ECR-25 GL 0.5 A B/1 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP HO

R YES'OTE 1

2-ECR-26 3 GL 0.5 A B/3 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1E F-5EF-7ET-XXXSLT-2

NOP NOP NOR YES'OTE 1

2-ECR-27 3 GL 0.5 A B/3 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET"XXXSLT-2

P NOP NO

R YES> NOTE 1

g* 2-ECR-28 GL 0.5 A B/4 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF"5EF-7ET-XXXSLT"2

P NONOP'O

P NOR YES'OTE 1

2-ECR-29 3 GL 0.5 A B/4 C 0/C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NOR YES) NOTE 1

Page 251: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o e e 0 e e e o e e e e e e e 0

0

0 0 0 0 0 0

Page 252: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEH NAME: PAS CONTAIt&ENT HYDROGEN

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SLRKARY SHEET - UNIT 2FLON DIAGRAM: 2-51%ID-8

RUN DATE AND TIME: 15FEB90:16.14

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE

2-NS-283 3 CK 0.5 SA C/8 C 0/C 2 A AC CF1SLT-1

CF-2SLT-2

R YES> NOTE 2R YESp NOTE 1

Page 253: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

H 4

0 e e e o e 0 e o a e 0

Page 254: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAME: EMERGENCY CORE COOLING - SIS

DONALD C COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - IPiGT 2FLON DIAGRAM: 2-5142-28

Rll4 DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XZ

%NBER REV TYPE SIZE ACT F AD. I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUiiCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED MODE

2-ICM-250 3 GA HO H/2 C 0/C 2 A A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-ICH-251 3 GA 4 'O H/3 C 0/C 2 A A EF-1EF-5ET-XXXSLT-,1

EF-2EF-5ET-XXXSLT-2

C NOp CSJ 1NO

C NOp CSJ 1R YESp NOTE 2

2-ZCM-260 3 GA MO C/9 0 0/C 2 A A EF-1EF-5ET-XXXSLT-1

EF-1EF-5ET-XXXSLT-2

P

PR

NONONOYESp NOTE 2

2-ICH-265 3 GA 4 MO C/8 0 0/C 2 A A EF-1EF-5ET-XXXSLT-1

EF-1EF-5ET-XXXSLT"2

P NONO

P NOR YESp NOTE 2

2-IHO"255 3 GA 4 HO J/7 C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IHO-256 3 GA 4 HO J/6 C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IHO-261 3 GA 8 HO H/8 0 0/C 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NOp CSJ 3NO

C NOp CSJ 3

Page 255: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 o o e e e o o e o o e e e e e 0

Page 256: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: EHERGEHCY CORE COOLING - SIS

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET — UNIT 2FLOW DIAGRAH: 2-5142-28

RUH DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

HUHBER REV TYPE SIZE ACT F.D. I POWER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE

2-IHO-262 3 GL 2 HO L/8 0 0/C 2 A B EF-1EF-5ET-XXX

EF"2EF-5ET-XXX

C NO> CSJ 4NO

C NOp CSJ 4

2-IHO-263 3 GL 2 HO L/8 0 0/C 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C HOp CSJ 4NO

C NO> CSJ 4

2-IHO-270 3 GA HO E/9 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P HOHO

P HO

2-IHO-275 3 GA HO E/8 0 0/C 2 A B EF-1EF-5ET"XXX

EF-1EF-5ET-XXX

P NOHO

P NO

2-IHO-361 3 GA HO G/9 C C/0 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2"IHO-362 3 GA HO G/9 C C/0 ' A B EF-1/ EF-5

ET-XXX

EF-1EF-5ET-XXX

P HOHO

P NO

2-IRV-251 3 GL 1 A H/5 0 2 A B EF1EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P HONO

P HOP NO

Page 257: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 258: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EMERGENCY CORE COOLING — SIS

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOH DIAGRAM: 2-514'2-28

RUH DATE AND TIMEt 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SI2E ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-IRV-252 3 GL 1 A J/5 0 3 A B EF)EF-5EF-7ET-XXX

EF-1EF-5EF-7ET-XXX

P NOHO

P NOP NO

2-IRV-255 3 GL 1 A H/6 0 2 A B EF1 EF-1EF-5 EF-5

P NONO

EF-7ET"XXX

EF-7ET-XXX

P HO

P HO

2-SI-101 CK 8 SA M/8 C 2 A C CF-) CF-3 R YES> NOTE 5

2-Sl-104-N 3 CK 0. 75 SA E/9 C 2 A C CF-1 CF-1

2-SI-104-S 3 CK 0. 75 SA J/9 C 2 A C CF1 CF-1

2"SI-110-N 3 CK SA E/9 C 2 A C CF1 CF-2 R YES> NOTE 5

2-SI-))O-S 3 CK SA H/9 C 2 A C CF) CF-2 R YES'OTE 5

2-SI-126 3 CK 1 SA H/6 0 2 A C CF) CF-1

2"SI-142-Ll 3 CK 1.5 SA C/) C 1 A C CF1 CF-2 R YES> NOTE 6

2-SI-142-L2 3 CK 1.5 SA C/2 C 1 A C CF1 CF-2 R YES> NOTE 6

Page 259: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 0 0 0

Page 260: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

III

0

SYSTEM NAME: EMERGENCY CORE COOLING - SIS

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SKEET - UNIT 2FLON DIAGRAM: 2-5142-28

RUN DATE AND TIME: 15FEB90:16t14

VALVE I VALVE POSITION I ASME SECTION XI

HOYBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE

2-SZ-142-L3 3 - CK 1. 5 SA C/2 C 1 A C CF-1 CF-2 R YES) NOTE 6

2-SI-142-L4 3 CK 1.5 SA C/1 C 1 'A C CF1 CF-2 R YES'OTE 6

2-SV-96 REL 0.75 SA J/8 C A C TF-1 TF-1

2-SV"97 3 REL 0.75 SA J/4 C 2 A C TF-1 TF-1, R NO

2-SV-98-N 3 REL 0.75 SA C/9 C 2 A C TF"1 TF-1 R NO

2-SV-98-S 3 REL 0.75 SA E/8 C 2 A C TF1 TF-1

Page 261: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 262: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAME: EMERGENCY CORE COOLING - RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET " UNIT 2FLON DIAGRAM: 2-5143-35

RUN DATE AND TIME: 15FEB90:16:14~ ~

VALVE I VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F.D ~ I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUESTERS)REQUIRED PERFORMED MODE

2-GCR-314 3 GL 1 A G/2 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF"5EF-7ET-XXXSLT-2

P NO

NOP NOP NOR YES'OTE 14

2-ZCH-1'29 3 GA 14 HO E/8 C 1 P A EF-1EF-5ET-XXXSLT-1

EF-2EF-5ET-XXXSLT-1

C NO> CSJ 2NO

C NOp CSJ 2R NO, NOTE 1

2-ICH-305 3 GA 18 HO D/9 C 2 A A EF-1EF-5ET-XXXSLT-1

EF-1EF-5ET-XXXSLT-2

P NONO

P NOR YES NOTE 14

2-ZCH-306 3 GA 18 HO 0/9 C 2 A A EF-1EF-5ET-XXXSLT-1

EF-1EF-5ET-XXXSLT-2

P NONO

P NOR YESp NOTE 14

2-ZHO-128 3 GA 14 HO B/8 C 1 P B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NO> CSJ 2NO

C NO> CSJ 2

2-IMO-310 3 GA 14 HO H/9 0 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO> NOTE 3

Page 263: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

a e e e e e e

0 o e o o e e e e e e e e e o e

Page 264: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

III

SYSTEM NAME: EMERGENCY CORE COOLING - RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMHARY SHEET - UNIT 2FLON DIAGRAM: 2-5143-35

RUN DATE AND TIHE: 15FEB90:16:14

VALVE l VALVE POSITION I ASHE SECTION XI

NUMBER REV TYPE SIZE ACT F-D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE

2-IHO-312 3 GL 2 HO J/5 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF"5ET"XXX

P NONO

P NO

2-IMO-314 3 GA 8 HO K/6 0 2 A B EF-1EF-5ET-XXX

EF-1EF"5ET-XXX

P NONO

P NO> NOTE 3

2-IHO-315 3 GA 8 HO C/7 C C/0 1 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NO> CSJ 4NO

C NOp CSJ 4

2-IMO-316 3 GA 8 HO C/7 0 0/C 2 A B EF-1EF-5ET-XXX

EF"2EF-5ET-XXX

C NO> CSJ 4NO

C NO> CSJ 4

2-IHO-320 3 GA 14 MO L/9 0 2 A B EF-1EF-5ET-XXX

EF"1EF-5ET"XXX

P NONO

P NOp NOTE 3

2-IHO"322 3 GL 2 HO H/5 0 0/C 2 A B EF"1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IHO"324 3 GA 8 MO H/6 0 2 A B EF1EF-5ET-XXX

EF-1EF-5ET"XXX

P NONO

P NOp NOTE 3

Page 265: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 0 0 0 0 0 0 0 0 0 0 0 0 0

Page 266: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EHERGENCY CORE COOLING — RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UiNIT 2FLON DIAGRAM: 2-5143-35

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NVK3ER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

—2-IHO-325 3 GA 8 HO C/7 C C/0 1 A B EF-1EF-5ET-XXX

EF"2EF"5ET"XXX

C NO> CSJ 4NO

C NO> CSJ 4

2-ZHO-326 x', 3 GA 8 HO C/7 0 0/C 2 A B EF-1EF-5ET-XXX

EF-2EF-5ET-XXX

C NO> CSJ 4NO

C NO> CSJ 4

2-IHO-330 3 GA 8 HO G/4 C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IHO-331 3 GA 8 HO L/5 C 2 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

2-IHO-340 3 GA 8 HO H/5 C 2 A B EF1EF"5ET-XXX

EF-2EF-5ET-XXX

C YES> NOTE 15NO

C YES> NOTE 15

2-IHO-350 3 GA 8 MO L/5 C 2 A B EF1EF-5ET-XXX

EF-2EF-5ET-XXX

C YES> NOTE 15NO

C YESp NOTE 15

2-N-102 3 CK 1 SA F/5 0/C C 2 A AC CF-1SLT-1

CF-2SLT-2

R YES> NOTE 13R YES> NOTE 14

2-RH-108E 3 CK 8 SA K/9 C 2 A C CF-1 CF-3 C NOp CSJ 7

Page 267: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

r

0 o e e o e e e e e e e' o e 0

Page 268: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EMERGEHCY CORE COOLING ; RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET " UNIT 2FLOH DIAGRAM: 2-5143-35

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XZ

NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE

2-RM-108M 3 CK 8 SA N/9 C 2 A C CF1 CF-3 C NOp CSJ 7

2-RH-133 3 CK 8 SA C/5 C 1 P AC SLT-1 SLT-1 R NO» NOTE 1

2-RH-134 3 CK 8 SA C/5 C 1 P AC SLT-1 SLT-1 R NOp NOTE 1

2-SI-148 CK 12 SA G/7 C 2 A C CF1 CF-3 YESp NOTE 8

2-SI-151-E 3 CK 8 SA D/7 C 2 A AC CF-1SLT-1

CF-2SLT-1

C NOp CSJ 9R HOp NOTE 1

2-SI-151"H 3 CK 8 SA 0/7 C A AC CF-1SLT-1

CF-2SLT-1

C NOp CSJ 9R NOp NOTE 1

2-SZ-152-N 3 CK ' SA D/8 C 2 A AC CF-1SLT"1

CF-2SLT-1

R YESp NOTE 10R NOp NOTE 1

2-SI-152-S 3 CK 4 SA D/7 C 2 A AC CF-1SLT-1

CF-2SLT-1

R YESp NOTE 10R HOp NOTE 1

2-SI-158-Ll 3 CK 6 SA B/8 C 1 A AC CF-1SLT-1

CF-2SLT"1

YESp NOTE llR HOp NOTE 1

2-SI-158-L2 3 CK 6 SA B/7 C 1 A AC CF-1SLT-1

CF-2SLT-1

YESp NOTE llR NOp HOTE 1

Page 269: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 270: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: EHERGEKCY CORE COOLING - RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SmARY SHEET — UNIT 2FLON DZAGRAH: 2-5143-35

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NASSER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-SI-158-L3 3 CK 6 SA B/7 C 1 A AC CF-1SLT"1

CF-2SLT-1

YESp NOTE llR NOp NOTE 1

2-SI-158-L4 3 CK 6 SA B/7 C 1 A AC CF-1SLT-1

CF-2SLT-1

YESp NOTE llR NOp NOTE 1

2-SI-161-Ll 3 CK 6 SA B/6 C 1 A AC CF-1SLT-1

CF-2SLT-1

YESp NOTE 6R NOp NOTE 1

2-SZ-161-L2 3 CK 6 SA B/5 C 1 A AC CF1SLT-1

CF-2SLT-1

YESp NOTE 6R NOp NOTE 1

2-SI-161-L3 3 CK 6 SA B/5 C 1 A AC CF 1SLT-1

CF-2SLT-1

YESp NOTE 6R NOp NOTE 1

2"SI-161-L4 3 CK 6 SA B/6 C 1 A AC CF-1SLT-1

CF-2SLT"1

YESp NOTE 6R NOp NOTE 1

2-SZ-166-1 3 CK 10 SA C/4 C 1 A AC CF-1SLT-1

CF-2SLT-1

R YESp NOTE 5R NOp NOTE 1

2-SI-)66-2 3 CK 10 SA C/4 C 1 A AC CF 1SLT"1

CF-2SLT"1

R YESp NOTE 5R NOp NOTE 1

2-SI-166-3 3 CK 10 SA C/4 C 1 A AC CF-1SLT-1

CF-2SLT-1

R YESp NOTE 5R NOp NOTE 1

Page 271: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e e e o e e e e e e e e e e e 0

Page 272: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: EHERGENCY CORE COOLING - RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUSRY SHEET - UNIT 2FLON DIAGRAH: 2-5143-35

RUN DATE AND TZHE: 15FEB90:16:14

VALVE VALVE POSITION ASHE SECTION XZ

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDl OPER FUNCT ICL REQUIRED PERFORHED HODE

2-SZ-166M 3 CK 10 SA C/4 C 1 A AC CF-1SLT-1

CF-2SLT-1

R YESp NOTE 5R NOp NOTE 1

2-SZ-170-Ll 3 CK 10 SA A/4 C 1 A AC CF-1SLT-1

CF-3SLT-1

R YESp NOTE 12R NOp NOTE 1

2-SZ-170-L2 3 CK 10 SA A/5 C 0/C 1 A AC CF-1SLT-1

CF-3SLT-1

R YESp NOTE 12R NOp NOTE 1

2-SI-170-L3 3 CK 10 SA A/5 C 0/C 1 A AC CF-1'LT-1

CF-3SLT-1

R YESp NOTE 12R NOp NOTE 1

2-SZ-170-L4 3 CK 10 SA A/4 C .1 A AC CF-1SLT-1

CF-3SLT-1

R YESp NOTE 12R NOp NOTE 1

2-SI-171 3 GL 0.75 H H/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14

2-SI-172 3 GL 0.75 H H/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14

2-SI-194 3 GL 0.75 H G/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14

2-SV-100-1 3 REL 1 SA D/1 C 2 A C TF"1 TF-1

2-SV-100 "2 3, REL 1 SA D/1 C 2 A C TF-1 TF-1

Page 273: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 274: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

tll

0

SYSTEH NAHE: EHERGENCY CORE COOLING - RHR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLON DIAGRAH: 2-5143-35

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

HRBER REV TYPE SI2E ACT F D I PONER SAFETY tCD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE

2-SV-100-3 3 RfL 1 SA D/1 C 2 A C TF-1 TF-1 R NO

2-SV-100 "4 3 REL 1 SA 0/1 C 2 A C TF1 TF-1 R NO

2-SV-102 3 REL 0.75 SA E/5 C 2 A C TF-1 TF-1

2-SV-103 3 REL 3 SA F/8 C 2 A C TF-1 TF-1

2-SV-104E 3 RE L 2 SA G/4 C 2 A C TF1 TF-1 R NO

2-SV-104N 3 REL 2 SA K/4 C 2 A C TF1 TF-1 R NO

2-SV-105E 3 REL 2 SA D/9 C 2 A C TF-1 TF-1 R NO

2-SV-105N 3 REL 2 SA D/9 C 2 A C TF-1 TF-1 R NO

Page 275: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 0 0 0 0 0 0 0 .0 0 0

Page 276: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: CONTAINHENT SPRAY

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUii'SARY SHEET UNIT 2FLOW DIAGRAH: 2-5144-29

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUHBER REV TYPE SI2E ACT F.D. I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-CTS-103-E 3 CK 10 SA J/9 C 2 A C CF1 CF-3 YESp NOTE 2

2-CTS-103-W 3 CK 10 SA L/9 C 2 A C CF1 CF-3 YESp NOTE 2

2-CTS-109 3 VB 1 SA H/6 C 2 A C CF-1 CF-2 C NOp CSJ 6

2-CTS-110 3 VB 1 - SA H/6 C 2 A C CF1 CF-2 C NOp CSJ 6

2-CTS-120-E 3 CK 2 SA H/8 C 2 A C CF1 CF-1

2-CTS-120-W 3 CK 2 SA K/8 C 2 A C CF-1 CF-1

2"CTS"127-E 3 CK'

SA E/5 C 2 A AC CF-1SLT-1

CF-2SLT-2A

R YESp NOTE 4R YESi NOTE 7

2"CTS"127-W 3 CK 6 SA E/4 C 2 A AC CF-1SLT-1

CF-2SLT-2A

R YESp NOTE 4R YES1 NOTE 7

2-CTS-131-E 3 CK 8 SA E/2 C 2 A AC CF"1SLT-1

CF-2SLT-2A

R YESp NOTE 3R YESp NOTE 7

2-CTS-131-W 3 CK 8 SA E/2 C 2 A AC CF-1SLT-1

CF-2SLT-2A

R YESp NOTE 3R YESp NOTE 7

2-CTS-138-E 3 CK 12 SA G/9 C 0/C 2 A C CF-1 CF-3 YESp NOTE 1

Page 277: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~ o e e e e e e e o e e o e e ~

Page 278: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: CONTAINMENT SPRAY

tDONALD C ~ COOK NUCLEAR PLANT

SECOND TEN YEAR INTERVALVALVE SUMHARY SHEET - UNIT 2

FLON DIAGRAM: 2-51&1-29

RUN DATE AND TIME: 15FEB90:16:10

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-CTS-138-N 3 CK 12 SA J/9 C 0/C 2 A C CF-1 CF-3 YES) NOTE 1

2-IHO-202 3 GA 2.5 MO H/7 C 2 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-ZHO-204 3 GA 2.5 MO H/7 C 2 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NO

NOP NO

2"ZHO-210 3 GA 10 HO J/8 C 2 A B EF1EF-5ET-XXX

EF"1EF-5ET-XXX

P NONO

P NO

2-ZHO-211 3 GA 10 MO J/8 C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET"XXX

P . NONO

P NO

2-ZHO-212 3 GA 2 HO H/8 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P .NO

2-ZMiO-215 3 GA 12 HO G/9 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-ZHO"220 3 GA 10 HO L/8 C 2 A B EF1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

Page 279: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

4

0

0 e e o o e e o o e o o e e e e

Page 280: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: CONTAIHMENT SPRAY

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2F LON DIAGRAM: 2-5144-29

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION ASME SECTION XZ

NUMBER REV TYPE SI2E ACT F.D. I POMER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUESTERS)TYPE COORDI OPER FUNCT ICL RMUIRED PERFORMED MODE

2-ZMO"221 3 GA 10 MO L/8 C 2 A B EF-1EF"5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-IMO-222 3 GA 2 MO L/9 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P HO

2-IMO-225 3 GA 12 MO J/9 0 0/C 2 A B EF-1EF-5ET-XXX

EF-1EF-5ET-XXX

P NONO

P NO

2-RH-141 3 CK 8 SA E/3 C 2 A AC CF 1SLT-1

CF-2SLT-2A

R YES> NOTE 5R YESp NOTE 7

2-RM-142 CK 8 SA E/3 C 2 A AC CF-1SLT-1

CF-2SLT-2A

R YES> NOTE 5R YES> NOTE 7

2-SV-107 REL 1 SA H/5 C 2 A C TF-1 TF-1 R HO

Page 281: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 282: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH NAHE: CPN/HELD CHAFCIEL PRESSURI2ATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLON DIAGRAH: 2-5145-20

RUN DATE AND TZHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SZ2E ACT F.D. l POHER SAFETY ICD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-CA"181-N 3 CK 0.5 SA F/2 C 2 P AC SLT-1 SLT-2 R YES> NOTE 1

2-CA-181-S 3 CK 0.5 SA F/3 C 2 P AC SLT-1 SLT-2 R YES> NOTE 1

Page 283: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

e o e e 0 e

Page 284: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

III

SYSTEM NAME: ICE CONDENSER REFRIGERATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLOW DIAGRAM: 2-5166B-23

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F ~ D ~ I POWER SAFETY I CD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2"R"156 3 CK 0. 375 SA L/0 C 0/C 2 A AC CF"1SLT-1

CF-2SLT-2

R YES'OTE 1R YES'OTE 2

2-R-157 CK 0.375 SA L/6 C 0/C 2 A AC CF-1SLT-1

CF"2SLT-2

R YES> NOTE 1R YES> NOTE 2

2-VCR-10 DA A M/5 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 2

2-VCR-ll 3 DA A L/5 0 2 A A EF-1EF"5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

HOP NOP HOR YES> NOTE 2

2-VCR-20 3 DA cj A M/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HOHO

P NOP HOR YES'OTE 2

2-VCR"21 3 DA A L/7 0 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HONO

P HOP NOR YES'OTE 2

Page 285: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o e e e o o e o o e e o o o e 0

Page 286: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: CONTAINMENT VENTILATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHMARY SHEET - UNIT 2FLOH DIAGRAM: 2-5147A-35

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION ASME SECTION XI

NOSER REV TYPE SIZE ACT F.DE I POMER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORMED MODE

2-SH-10 3 GA 0.5 H A/4 C 2 P A SLT-1 SLT-2 R YES> NOTE 1

2-SH-4 3 GA 0.5 H A/2 C C 2 P A SLT-1 SLT-2 R YES> NOTE 1

2-SH-6 3 GA 0.5 H A/2 C 2 P A SLT"1 SLT-2 R YES> NOTE 1

2"SH"8 3 GA 0.5 H A/4 C 2 P A SLT-1 SLT-2 R YES> NOTE 1

2-VCR-101 3 BF 14 A J/8 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT"2

P NONO

P NOP NOR YES> NOTE 1

2-VCR-102 3 BF 14 A J/9 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP NOP NOR YES> NOTE 1

2-VCR-103 3 BF 24 A J/5 C 2 P A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT"2

P NONO

P NOP NO

R YES> NOTE 1

2-VCR-104 3 BF 30 A J/6 C 2 P A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT"2

P NONO

P NOP NOR YES> NOTE 1

Page 287: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 e e e o e e e e e e o e e e e 0

Page 288: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEH HAHE: CONTAINHENT VENTILATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VAlVE SUHHARY SHEET - UNIT 2FLON DIAGRAH: 2-5147A-35

RUN DATE AND TINE: 15FE890:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NUHBER REV TYPE SIZE ACT F ~ DE I PONER SAFETY ICD A/P CATTYPE COORDI OPER FUNCT lCL

PRIH TEST TEST TEST RELIEF REQUEST(S)REQUIRED PERFORHED NODE

2-VCR-105 3 BF 30 A J/3 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NO

HOP NOP NOR YES7 NOTE 1

2-VCR-106 3 BF 24 A J/3 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

NOP NOP NOR YES> NOTE 1

2-VCR"107 3 BF 14 A J/4 0/C C 2 A A EF-1EF-5EF-7ET-XXXSLT"1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NOR YES1 NOTE 1

2-VCR-201 3 BF 14 A J/8 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P HO

NOP NOP HOR YES> NOTE 1

2-VCR-202 3 BF 14 A J/9 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P HOP NOR YES'OTE 1

Page 289: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 290: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAHE: CONTAINMENT VENTILATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMHARY SHEET - UNIT 2FLON DIAGRAM: 2-5147A-35

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUMBER REV TYPE SIZE ACT F ~ D ~ I PONER SAFETY I CD A/P CATTYPE COORD I OPER FUNCT ICL

PRIM TEST TEST TEST RELIEF RE@JEST(S)REQUIRED PERFORMED MODE

2-VCR-203 3 BF 24 A J/5 C 2 P A4,

EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-VCR-204 3 BF 30 A J/6 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF«lEF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-VCR-205 3 BF 30 A J/3 C 2 P A EF-1EF-5EF"7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NO

R YES> NOTE 1

2-VCR-206 3 BF 24 A J/3 C 2 P A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P NOP NOR YES> NOTE 1

2-VCR-207 3 BF 14 A J/4 0/C C 2 A A EF-1EF-5EF-7ET-XXXSLT-1

EF-1EF-5EF-7ET-XXXSLT-2

P NONO

P N)P NOR YES NOTE 1

Page 291: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o e 0 e -o e N 0

, 0 0 0 0 0 0 0 0 0 0 0

Page 292: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

III

SYSTEH NAHE: CONTROL ROOH VENTILATION

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET - UNIT 2FLOW DZAGRAH: 2-5149-23

RUN DATE AND TINE: 15FEB90:16:10

VALVE VALVE POSITION ASHE SECTION XZ

NUHBER REV TYPE SI2E ACT F AD I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-DW-163-N 3 GA 2.5 H F/2 0 0/C 3 A B EF-1 EF-1

2-DW-163-S 3 GA 2.5 H G/2 0 0/C 3 A B EF-1 EF-1 P NO

2-DW"166-N 3 GA 2.5 H E/5 0 0/C 3 A B EF-1 EF-1 P NO

2-DW"166-S 3 GA 2.5 H J/5 0 0/C 3 A B EF-1 EF-1 P NO

2-VRV-315 3 3W 2.5 A F/5 0 3 A B EF-1EF-7ET-XXX

NOTE 1EF"7NOTE 1

P YES> NOTE 1P NOp NOTE 1

YES> NOTE 1

2-VRV-325 3 3W 2.5 A G/5 0 A B EF1EF-7ET-XXX

NOTE 1EF-7NOTE 1

P YESp NOTE 1P NOi NOTE 1

YES NOTE 1

Page 293: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o e o e e e e e e e e o e e e

Page 294: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EMERGENCY DIESEL GENERATOR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2FLON DIAGRAM: 2-5151A-26

RUN DATE AND TIHE: I5FEB90:16:14

VALVE I VALVE POSITION I ASME SECTION XI

NUHBER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-DF-108A 3 CK 1.5 SA L/3 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-DF-109A 3 CK 1.5 SA K/3 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-D F-114A 3 CK 1.5 SA J/3 C 3 A C CF-1 CF"1 P " NOR NOTE 1

2-DF-115A 3 CK 1.5 SA H/3 C 3 A C CF-1 CF-1 P NOiNOTE 1

2-DL-114A 3 CK 1.5 „SA B/9 0 3 A C CF-1 CF-1 P NO>NOTE 1

2-DL-116A 3 CK 1.5 SA B/9 C 3 A C CF1 CF-1 P NOp NOTE 1

2-DL-126A 3 CK 2.5 SA E/9 0 3 A C CF1 CF-1 P NO> NOTE 1

2"DL-132A 3 CK 1 SA F/9 0 3 A C- CF 1 CF-1 P NOp NOTE 1

2-D L-158A 3 CK 6 SA G/6 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-QT-114-2AB 3 3H 6 SA H/5 0 3 A B EF1 NOTE 2 P NOp NOTE 2

Page 295: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 296: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

SYSTEH NAHE: EHERGENCY DIESEL GENERATOR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUHHARY SHEET " UNIT 2FLOH DZAGRAH: 2-51518-27

RUN DATE AND TZHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE

2-DG-102A 3 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NOi NOTE 1

2-DG-104A 3 CK 1.5 SA G/4 0 0/C 3 A C CF-1 CF-1 P NOp NOTE 1

2-DG-128A 3 CK 1 SA C/4 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-DG-130A 3 CK 1 SA C/4 C 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-140A CK 0.5 SA a F/1 Cf

0/C 3 A C CF-1 CF-1

2-DG-142A 3 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1

/

2-DG-146A 3 CK 2 SA A/8 0 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-152A 3 CK 4 SA D/8 C 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-154A 3 CK SA C/8 C A C CF-1 CF-1 P NO> NOTE 1

2-QT-132-2AB 3 3N 6 SA E/8 0 3 A B EF-1 NOTE 2 P NOp NOTE 2

J

2-SV-120-AB 3 REL 0. 25 SA G/2 C 3 A C 7F1 TF-1

2-SV-139-AB 3 REL 1 SA B/2 C 3 A C TF1 TF-1

Page 297: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

Page 298: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0SYSTEH NAHE: EHERGENCY DIESEL GENERATOR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUGARY SHEET - UNIT 2FLOH DIAGRAH: 2-5151B-27

RUN DATE AND TINE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUHBER'EV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE

2-SV-61-AB 3 REL 1 SA A/8 C 3 A C TF-1 TF-1

2-SV-78-AB1 3 REL 1 SA E/3 C 3 A C TF-1 TF-1

2-SV-78-AB2 3 REL 1 SA D/3 C 3 A C TF-1 TF-1

2-SV-79-ABl 3 REL 0.5 SA E/1 C 3 A C TF-1 TF-1 R NO

2-SV-79-AB2 3 RE L 0. 5 SA E/1 C 3 A C TF-1 TF-1

2-XRV-220 3 GA 1 A B/3 CEF-7ET-XXX

EF-7NOTE 4

3 A B EF1 EF-1 YES> NOTE 4YES'OTE 4YES> NOTE 4

2"XRV-221 3 GL 3 A B/4 C 3 A B EF-1EF-7ET-XXX

EF-1NOTE 3NOTE 3

YESp NOTE 3YES> NOTE 3YES> NOTE 3

2"XRV-222 3 GL A B/4 C 3 A B EF1EF-7ET-XXX

EF-1NOTE 3NOTE 3

YES) NOTE 3YES> NOTE 3YES> NOTE 3

Page 299: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

~ 0 0 0 0 0 0 0 0

Page 300: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

0

SYSTEH NAME: EMERGENCY DIESEL GENERATOR

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUmRY SHEET - UNIT 2FLON DIAGRAM: 2-5151C-26

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XZ

NUiiBER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-DL-114C 3 CK 1.5 SA B/9 0 3 A C CF-1 CF-1 P NOs NOTE 1

2-DL-116C 3 CK 1.5 SA B/9 C 3 A C CF-1 CF-1 P NOp NOTE 1

2-D L-126C 3 CK 2.5 SA E/9 0 3 A C CF1 CF-1 P NO>NOTE 1

2-DL"132C 3 CK 1 SA F/9 0 3 A C CF1 CF-1 P NO> NOTE 1

2-DL-158C 3 CK 6 SA G/5 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-QT-114-2CD 3 3H 6 SA H/5 0 3 A B EF1 NOTE 2 P NOp NOTE 2

Page 301: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0 e o e e o o e e e e e o e e 0

Page 302: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EMERGENCY DIESEL GENERATOR "CD"

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET — UNIT 2FLOW DIAGRAM: 2-51510-27

RUN DATE AND TIHE: 15FEB90:16:14

VALVE I VALVE POSITION I ASHE SECTION XI

NRSER REV TYPE SIZE ACT F.D. I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE

2-DG"102C 3 CK 1. 5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NO> NOTE 1

2-DG-104C 3 CK 1.5 SA F/4 0 0/C 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-128C 3 CK 1 SA C/3 C 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-130C 3 CK 1 SA C/3 C 3 A C CF1 CF-1 P NOp NOTE 1

2DG140C 3 CK 05 SA F/1 C 0/C 3 A C CF-1 CF-1 P NO

2-DG-142C 3 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1

2-DG-146C 3 CK 2 SA A/9 0 A C CF1 CF-1 P NO> NOTE 1

2-DG-152C 3 CK SA D/9 C 3 A C CF1 CF-1 P NO> NOTE 1

2-DG-154C 3 CK 4 SA C/9 C 3 A C CF-1 CF-1 P NO> NOTE 1

2-QT-132-2CD 3 3N 6 SA E/8 0 A B EF1 NOTE 1 P NO> NOTE 2

2-SV-120-CD 3 REL .0. 25 SA N/2 C 3 A C TF1 TF-1

2-SV-139-CD 3 REL 1 SA B/2 C 3 A C TF1 TF-1

Page 303: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0

0t

e e o e e e o e o e e o e e e ;J

Page 304: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

SYSTEM NAME: EMERGENCY DIESEL GENERATOR "CD"

DONALD C. COOK NUCLEAR PLANTSECOND TEN YEAR INTERVAL

VALVE SUMMARY SHEET - UNIT 2FLON DIAGRAM: 2-5151D-27

RUN DATE AND TIME: 15FEB90:16:14

VALVE I VALVE POSITION l ASME SECTION XZ

NUMBER R V TYP ZE ACT F.DE I PONER SAFETY lCD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE

2-SV-61-CD 3 REL 1 SA A/8 C A C TF-1 TF-1 R NO

2-SV-78-CD1 3 REL 1 SA E/3 C 3 A C TF-1 TF-1

2-SV-78-CD2 3 REL 1 SA 0/3 C 3 A C TF1 TF-1

2-SV-79-CD1 3 REL 0.5 SA E/1 C 3 A C TF1 TF-1

2-SV-79-CD2 3 REL 0.5 SA E/1 C 3 A C TF1 TF-1 R NO

2-XRV-225 3 GA 1 A B/3 C 3 A B EF1EF-7ET-XXX

EF-1E F-7NOTE 4

YES'OTE 4YES> NOTE 4YES> NOTE 4

2"XRV-226 3 GL A B/4 C 3 A B EF-1EF-7ET-XXX

EF-1NOTE 3NOTE 3

YES'OTE 3YES> NOTE 3YES> NOTE 3

2-XRV-227 3 GL 3 A B/4 C A B EF-1EF-7ET-XXX

EF-1NOTE 3NOTE 3

P YES NOTE 3YES> NOTE 3

P YES~ NOTE 3

Page 305: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 e o e .0 e e e e o e e e e o e .,

'

a e o 0 o o e o e e

Page 306: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

@84 S

~ ~ ~ t

~ 4 ~ ~

4 ~

~ I

s$'

~

~ ~ ~ I

~ ~

~OS .

Wa~7aa

4

~ ~

~ ~ ~ ~ ~

~ ~

M~

4 4 ~

~ ~ .il'*

1 ~

~ ~

- .I~

~, ~

~ ~

~ ~

~ - ~

~ ~ I

~ ~ ~ ''~ c

~ . QI ~, t ~ ~ t.~ 4 '

~ 3

~ ~ ~ ~ ~ ~ ~

I '

Q 4

+iTtg

"

gt ~r+@V

14

~' ~ '

+ fg ~

~ 4

yg ~ ~

dh W%P ~

IIt t

t

~ ~ ~ 4 p t 4

r

~ ~ I ~ ~

~ ~

tmt~ A, 'gt. ~

~I'gttl 1 ~ ~

~ ' ~ ~

~ ~ ~ t'I~ ~ ~

Page 307: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Q ~

'L

I„ 0 0

Page 308: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

r ~

«' k~ I «i It I~ I~'tI ~ I ~ trI t I

ft« swd~W g8

I)II ~ I

gs gb

tjg > r+ ~ ~

V

V

« Ita ltt it« It« it

'+«wdgsm

p

t

RGae~~

t ~ ~ ~ ~

0 00

6 0

KRHNRSRK%1RRRKSIHR«IKIIRRKI~~WITZIttr~~~~~~&KKr~amzmm~~ma~m'md~~rrtrt~RRVIIÃKI~~~RRB~~rBD~

Page 309: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 ~

J

. ~I

Page 310: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except
Page 311: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

'

F'

C

Page 312: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

j, $

~ ~

~ ~

~maSH

Ct

~ \

~ ~

' ~

KK3KHXH~~RKRhM~W

~ ~ I ~ ~

%P~C

~ I

~ ~

~ ~'

e

- prinz~. RSM5%K&

-KQR?~%4mm Err"KM~al

Page 313: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

4

,, ff

fIf

1 e-

Page 314: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

~ ~

~'

~ ~

~ ~ ~

~ g ~

~ ~

~ ~

~ I

~ ~

~ I ' ~ ~

%F yT~ I ~

~ t' ~

~ l ~

II 4 ~

~ ~

4(ll wll~lll-.V

+ ~ ~ ~

~ ~

~' EJ

~ f~ ~

~ I ~

~ I ~

45 cZh

~ .' KeL

S

~ 0 ~ ~

m

g~ mrc

RW'oal 1 ~

~ ~

~ ~

~ I i i ~ i . ~:

Page 315: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 ~4

1- ~ A

"I

Page 316: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~ ~ ' ~ ~

~'

~ ~

~ ~

~ ~

Q ~

~ ~

~ ~

'

r~ '

'

Tk

I

cd/sr ~M r~a~ ~

~ r

~ ~ '

I I

~ ~ ~

gsml ee ~ arlaailRIIRNII

~ ~ ~

~ \

CRGKHHiIPim~M~RX~~~~ r

k JeCKh g g 84 AHAr~ m ~ ~ ~ ~ ~

~ ~

~ ~

~ '

R ~~amp%$~lgQ

Page 317: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Pl r

~f ~ > ~ ~Q> wl lllJ

/

3

rl

Page 318: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

gPb Cih

~ ~

~ ~ ~

~ ~

aa

WKLY

Ch ~

~ Q ~

~ ~

I ~

~ ~

pTI

~ ~

~ ~

1

o

~ ~

~ ~

TI ~

~ ~ ~

~ ~

T~ L t ~

~ t

i%J

gi

I 4 gyl@j

~1

~ ~'

tt ~ ~

~'KRSEIIZ~~EX~~

~ ~

. ~~ ~

~ ~

~ ~

~ ~~ ~ ~ ~ 4

~ ~ ~

~ ~

4.I ~g ~ ~

5~ '

~ e

~ ~ ~ ~

~ t ~

Page 319: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

0 I

0 I~ y

fI

Page 320: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

M.. II L~ Q I ~ D AK I F ( 9 I 0I1 J I

~ll 'te~Lttsk. v.a.>H ve va.sst lease olvle. Looby

~S,ei.>ts,ett,141,«11 V«>MS S44$ ehv~sorvN.D'v's e, srhrkce.

S.vrk TO Are >era skVer>S Saesvhs SSO>VSSD O4 arete>asIUAS.

~, eva sl lssD Ura,«$4«>4$ sasssvhs vovvtlo 04 cskssos~l 4 1st crsot ssssS

2 VCHT', 6'RflctDR coouNt+

STAND tltj STEAMG(14ERATOR

Ntb

FSSL>031 N

'5IIC20CSlst tnCskat 30CS Acts

KLctse

NDICS!I Ol Dsta akls i,li)NSTIsW~fae«toes1>inl save>seta>saeste Dketl«vsvas>as> avl rlara

L Ioa asvacsass I eesn kocakws JslfltSsesvvat Ielsvvs lekvo see>ress leassskvv s>oavast eesso «s>Sec l>lsUIIt kev Ir JSDQ t>ASUUD Sueatar)ah lvol>Seat CUSS av rksrc

).Pea CNCCAIS tletlelelek SSU>retel s'kswskat a>II>osteavs

4$ Iv4 Nasl ssvavasf csssskp fkssa

Ocl 24 tiler HO2Cu SOFVNP N23O.A lotltk H)4Csle3 40Cslcl 30

='K/ E//lsv Z 'INsNLkGEMD ~~ REACTOR

CDOLA)41 Pl/el)RS8YAUX. PIPINGINst e. ps ps ss e

fj/) BY WESTIMGNDUSE

'ALL VALVE5 AMP IMSTRU.MKMTLTIDMSY (9)FOR VALVE,INSTRust(MT,SAMPUNC, PIFK MATKRSlANO OTM(R SYMDDLS NOTCXP$J)NSD ON TM15 DWCUAMDFOR MARK MURDERCODES> 5EK DW05.165NSS

se4'40~3

/NPIIIO PESIGM To FOLLOWCRITERIA IMPICATEP IMSIAEW-)Zlt C AEW DIG.s(lsMIG cLA$5 2 ExcEPTAS INDICATED.

~ c/rOs)frt IS AMikaT tt Ab&VC TN(CCVMTOTRK RKA(fbt (00)ANTtollt.

goff 2, Flf, Mlf~O MAVK ffl(M5IOU ST(M16 6( OffRAT(D a&IS)DE Of tf(Otlf(K KMCKOSORE AT KLCIIIU:

IN7L3 ~ M/ISiott SFRAY tiff OONMtrllo Tottnfltf Wll(R SflL 6(TN(KMFt(SSORI((t AVD 5FRAY VALVKS.'OTE S, WC>>YC> K/6 ~

tllltO(TKCTORS Af boffos( 61tete

Nol(C> KlSIOFFKFK OOWNHIRO TO FROVIDC

WIT(K 5(AL OM RIUKF VAIYKISI'OT(T> 0/tr Jls)

ID~(II ttROIIMATKLTSIIDWAY6(t)YEKN lOOt AVD tR(SMItit(R.

Lot( & Aff> 4/f> 4ff/OAtQ5MITT(D5ANFLK 5(( OW

tsai,~f'5 E/2VALVE bONNET A'ND INTKRNALSARK TU bc REMOVED ANO bUNDMEAD INSTALLED EXCEPT WNEIIt(STINC VALVC \(16'3

'TK to Igt;g<g~NOT( I> 0/Sir, I

I

I

C5lC3 20au y CSNCS- K)Z

g SM

ssi

R

Cr

OQ i

2OLA 21 tstkt II22Ou SS PVMr set'6QLA ll tUMP Nt4~ jcczfRs

CSAC3 IICSKCS-D

Io

)F'VDIII

PRSSSTIRIZER

EI.EV.CSZ ffzPRIMARYMANE.UPI 5'EESKETCN G 4) Cls

~sssast a>trees>artCSAC3 SI

trlsv.lCskssrll~«lsv ttvisv ~ ORV U~ A ISO«

4at«CSlat II

~„8:8:k'I~w?N 3

en

2~4

QRY 21 PUMP M0.2QRV 31 PUMP MO.SQRV-41 I uMP Mol

s

vs ckvM Us cM'saesr srk'SI IUCPU'SINr IAttlJH CPU Si

all+

fz Cfl"

To REACTOR COOLANT'DRA64 TANK Ouf~r5EE DVNL515TAg6

410vs

41(3

<VCNT'PV20PUHPNGZ.

QRV-SOPUMP M0.5QRV-IO PUMP Molt

OAV-O f

Cl 4 lskclast.tcs I$1.1Csk IIWCsess

FROM pUMp Mat.FROM PVIIP ~4Qff.zo PUMp Ma 2QTI.SO PUMP Na SUII.40PISIP N0.4~I)ifLEAK Cff

2

TO PRESSURIZREUEC TANK

SEE SK G.5,DRADI IRON Elr(SSNK ICsc S(K SIZSIAfd

!

Caela.tCsesa.i

Dlt 10 tVNFVtt0114) DUNS VP)knit«otv

csassa

assi 1.tIsa 1th

CSeIHS

aa esl«I

csasa«caela. ~

s ~

~ MPUAIPNOSClair 1

ass

sse ssirt4 4 als ~ 3

SECONDARY SKA1.LKAKAC'E.ToREACTOR COOLANTDRAlM TANK.5E.kPS'0. SI ST*IA/Ssb/5>(Y/Je 9/3

assai ~ost )ID rs/set sext t assn scri Iln rvssr Hn s 0 1 csksi I0 1 II44 tvvt IC'

AIR IIt

r4$4$$

S>4

, nit2 ask')

0 R-2)puw NC42QIR 51 PUMP NCI5OCR 0 PUIIP MOA

!QDA 'ZO PUMP Mnt0 DA 30 f>UHDN43CDL40 FVMFNt4I- 10

I.I

II I g~ ef 2

SI. APERTURE

CARD

~ 4 ~ '1 v'«e>vvs fw

11 Note~ O ars

NVA m(ep I)NTI4e)TCU> t)NVA akKN>l)

Da VENTCSSISsca>seaCSksalCs>$ $4

KS'SU>SOSt tat I5)~

F

2

NQ.I LEAKWF ask

CVIScs all II)I'$

44$ i

hev e\vv 'hrI vs«4 Irs 4

~ je4r-"0~54-

~I~

ZV2< p

~ ~ 4~tge43CCCC

Rt>ICTOR2

F RQM QIHE'R REACTORCOOLAIII PUMPS

COMM.AJ fLOQ P~Mt 5ONLY

SPOOL,BIECK (TYK)

I't

5 LEAKOFF

2 U0U as

ps

0 4I4)

so CI4lt t43444 O

csea wcsall'ICSaal t

3 kss.a>N'i

se >«14 4hv>H sew

Sr>aS'l hs

NrsREACTORCOOlANTPVHPtlvk 1st (Ha I )

NVA iZZ(Me t)IVVA 14't (Ns 4)

CSAAOIChair 2each's

v 'e r555 TO vo(UNK coNTR0L

TAII~RU SEALWaTER FI(1(R. SEKOWG 5)29A,B/d.

0twslo

14 'l4QTK'220 PUMPMOf 01

QTI 250PUMP)f)5 zioOf). 240PIS4P M04

cskvpt Isa so.tcsaaa.t csa jo'tcsaka«cskHvl

ntl

eaare41441 lCSHIW

3/I

reve> «W3~ve ~ >

(Cvke-3)Oil ttn toast Nt 2Oil tlot&lltMel g»Dll tlotOW Vll

TO OTHER REACTO'RCOOLANT Pl)MPS

NCT4 NIXS NCLZ

Iso Available OnAperture Card~ sp

d

~e tRNU'4>rh«U

6's SEAL SVSI(M bf-P SS AT SIART UP

sitaPR(SSURIZRR u IRtaltt TAHsa ~ I

I(L.51d.s~ «o»rke

)/~ F.C. I (3

olso

l8

«>Ness>esse>re 6$ I RDIDI.II RO'OSO

20 osr««eea.e>ra DP.SDS«

Dl

CR 25 FIIMFNtt I 31 ~

011'l0 tvsft Ns 1 /4

~h >svvvtaDvsslh4«44141«w hsssvsl

011.40 FUHtMal

fROM OTHER'RE.ACTOR

COOLANT PUMP5

t41444 I

i csa«:t4144 ~ )

l Csaaaklease CS ~ 4$ >a

CSs« I I CSaal l4$ «ale I'$44$ 2cleas«csael I

I'lank

IMlesCaela IIMI~ 'I

~e$$

4

„"'0Cs IIIIcsa'Is« I

t~>S e

eke Ile

SKETCH LtcARRCT FOR ONE REACTOR COOLANT

LOOP IN CONTAINMENT Ntt(LOOP Mtb SHOWN)

(1N IICFN It tolltIPtCte U t&Mt

Nrl'FN

M tUMtMP4

w I aasa terket Seka vr P>4Isk vs sevacss

No. 4

cseea I41444 I4$4444csaaah

$44 vrlL0NAlll

1501AIIDSI VAIVf Tf

R v4rt crhtsehksol kcv essa>raov Dve. 1 1ste

WOM CNIRCING FDMIS5'(f twc. 5111, 6/I

I)OIITIDVVXIV( Tfst (calNFailas>se ~

ah OR ss

2$ 44>SsNfl

TD

vssrveskrr ttsfItkv12.>

PRESSURIZERRELIEF LINE,

ftoll l(IDONI"LINK RKLI(F.VIIVKSt( DWC. SU1e fg

RL51DUAL NEAt 'R'KMOVALMRAT 'KXCIL SAFETY VALVEDISCM. SEE DWG. 5143,L/5>G/3

EMERG..CORK COOLINGBYS. BKLIKP VA DISCM.SEE DWCC SIISZPC/5 J/8

, 0/5,(/6

No)I/si)II'53~HAND OV R~kt D 444~4

IDIH'tetsCA'lenv HUUSIRSO' 'Not( s,glSYISA

C ~ el+ see te vvee

MUD)5$ "')r eee 2

~~~K'1

SIN» iSZI NRV 152alsaerv. vs>err

VVSNV s

44

N'0'ff S,O/Is/4

3'FROM Sfll STIRK RKTVRM

2111(f tltst '1(f SC:I r;N/)

IRON t(SIDSIL N(AT.RfNOVI(LOOP tN Dvt Sill, t/t,fib

NDX

$1113SI ISD

SV<5)Nlk152

I Trht ski ~ ov

CCI)3ARG)MG PUMP

5UCTION SAFETYVALVKDISCll-SEEDllBi.Sl 29r L/Cs.

I Dhi.v 'sresovc vltvtHvssecRs'tttlR

ose 'tHIS DRAWV>C SCCSCPARAXC VALVK IDCN1SFKATNNLIST FDR fOVSVALZNXCCSICN

.14CRI NV46(RS.t. IAC NVSlOCRS NCDTFSKO FOR

DRkwtec Ust t'I FOLLOWS'C 1st'.NSW VOS'S

AttcAIIS As; laswNSwS.VSSXPSVkf Nt ROOT VALVI HARK

N4 $ SCINISPNse N Dse Dhkwvec IsztVkLVC eo(NletlcktsoN Ust)DCRTVCD Dt ADDTNC to'eSTRV«f Nt'NUNOtR;IXSI SSNCLC >TS>SASC.VSteel covnlt Taeshksc.vscpstistkNT

Ib'To tl STRAICHt SV.4(C5(CTION (tYPICAUv'2 f)s)

(astcavaas 2'AUX.SPRAYs 5(Katsssvav) DWGSM5 blS

ST(M LONCOFF PI 14

ISW CD>I 1)t'7 Isr», ~ sal ggt

055 t I

lOOP~sso Oa>

s

Z0I)

Ch. Cenr~|'hoH$41

I

0IJ

'St fob

I'' 5

sl, ~

INol( I,Dl3 ~ Cs frR)

tc0I/I

01

s

CarC)

C

sss ~,>>~>II Is~ SKE NOT(9.nfs 4(I

FCLC. ~ ~I

5(K ODT( R,cftI/I REVS

)4SI

5

PctsaVCIZ KR FUSTACCSD(sl'f VENT

SVSISVtfIll

3/I

Vl'l(I,Ltlfft, 1

PRAYCOT)fCICLVA,LVES

I SIIOS~ 4Ulm-.

Ctudl~~Ot «rave>IH MAIVS Sit,

v klrrSKW rICDV eke V«ac«C..NSItent)ROSTATI C

)5CLATNN VALVE+ rr YEAST TEST FLANGEZESTY CONNECTNH 3/

e

Mtf1$4)N51DE. ))4STRUMENTATION ROOM104~IM se'KIUORIRX INSR

FOR TENT FRCN R()CMRVKSSKL ISZID V(elf

IINfa 926>N/h.

TO VKMTMKIO(ILSIKOWC 5131),143 301

CI -. '/4

'C.

y h IRCR 101

RCR.XO wsiODX vs tn-s 'f

ISINITKNTA) )TIST CONk

SF 4 ~ Zptr 345(K ROTC &,C/5Nll5

OI(t .fL$3310)lj

s

es4ksc ve 4 >reer>4k

Ietl4CTCT, .,:0/4

ISLPISSVI

DTLPISSVCFDR A(VISOR DCSCRst)ON Stt

5(teUIAtt RCVISKITI RKCORDFOR lies ORAWSSN

atl

(IYIRAY LIMES

IS3ssICCIATIDVVllvjttST Coseltct

~ rIII

I NL

) is

Q SSKRIMVC

PRKS'SURIZERLbon Ff 24 ss t$1'cboF oealtco)~Nttilftl

I) 34 ~3/0tttt 3))~t te VO

~ FROM NITROGEN X~sg'KR)C) fyf sa kSUPPLY MANF01.0

tu fl

hvs ~ v ve vvvv er sv ever&assaser >veer see>he Cessvvevvee v>e v v v> v v vv«>evrvv v as ee vv«vvv vevve evvv e> sv ~ Ir esse>ca asser ee~v vr >vvv e>svvrsk «eve vsverave >TI>e «>rsvve vv«vs«

;ONU 4)3/4'SIAMD flfEMAR('Vt LIM($Sf( SXKTCR'0-'5 l6/2

St ~ SS 15I1st Tesacaka

MYPROCTAT)CTEST FLANCK.

N.PSEE PWG.Sllbb,C/3>)f/3 «» la C

244 C™gtF

C'RO'llPRIIIARY assfATER ' ff FVI t5S.E DWCa 5) IEA.J/5 Lcx ~

twltcNCR RSR)

~will 4 Nt~ss s tvII4 l 252

150IATIDM VALVtTKST, Cosbl~

F RON REACTORCOOLANT LOOPM($4 SEL(NGSR g'5 sssDIAHA N kssCHTCAN IlkrlNNcca

. Ã)(ALDCCOOK'UCIKARtuNT

FROM REACTORCOOLANT LOOPI)CI3.5EE DSIG.5)ZC)G/0

CITS-tuvi - NPAIK'51 )11

2

15

Hats se11C 5esstsssts

151 I

as SIllAMWAYAMD Rot(USE74 glSC.BURST PR(55VM5

100 PSI 04A FDR31244444

I..NRY.t'l

KUKCtg.3 DEAD Wk)GS(TCALIBRATOR

~ FLOW D)AGRAMhr~ . REACTOR COIANT;

UNlT 2 e r- SHEEl' OF 2 t ~

NCIIC

N

102PIPING K>Y)1>I) Stt Not6 5> OIS

Isl.seceoacsl'RE55URIZER5URGE

LINE FROM LOOP MES5EE DWG. 5)ZIS))VC

IRI (Oak&.o~y S, eaA sir 1 1 4

s. NEATERtl Sl

NOTE 2 Olla ~

E'IIA2 -512 S A-.OMI-5

0 NOTte~aks>F ttztsK TtsokskAro>I ecsst EACH

'evsrDUCNf SOCNT Se>KATrel SAtk&CCIS 'tr VTACS& Otssteev>SC seo)CO,

4OW PRESSURIZER RELIEF Tt NIC ~~

Ir&OOFTS IOO P51 54OF|'EISMICCLASS B

NTA Wsvs ~ 4

I ~

~r~ ~

DCV IF C.

~ A Ia

~ l.Lt.14 S

sela

OUTS)DE RECTOR s ~

CONTA)NMENT

Ss

)C E. T C 34 IG 94tufRANGENE14T. (3F PIPIMG..Af PR(55VRIZE<

PRVJ5URIZE'R REL'1( E TAMY

v s«e~st) tvtsnl 0«ci VAcg. VHIOVKFOR UIMT t

, A'0 sottast Des Dwc I t sel&ARcv tf a

0 REACTOR COOLANTDRAIN LINESES DWG. 515TA>QIS vtasckv acctvr tvvcv Nssrsct ckr»

lkoNsvlr',, sstst tetr'CHENATI 5

FIttlctot ccoiltf FDHFS . "--sL";h-)PP lb I ttealp 2FA kevs tt«5~ soK G'T GH 0-3

SCHEMATIC ARRANGEMENT OF REACTO'R COOLANT PUMPTIKRMALbktRTKR 5khL WATER 5Y5TEMCf (ONM.'

D . (($,4+i rr4rstkvv r.v~ i . ~

C I D ( ~ - E>r

Sr ~ r ~ « ~ ' r ~ rI F

0.3090183 - ~I ~ L I. M' 'M,": ~ ~

s s

Page 321: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

1o ll'

t

e

tC

C~

J'

Page 322: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I ~ ~ ~ ~

~, ~

~ ~

~ ~~

- gb %29~ ~

~ ~

I ~ ~ ~

~ ~

~ ~ 4'

~ ~ ~ ~ N8~ ~

~ ~~ ~ ~ ~

~ ~~ ~

I ' 0 ~

~ ~

tA VA t4~ c ~

~ ~

~ ~~

' ~ ~

~ ~

~ ' 0' ~

~ ~

EKES Rl~~ ~

0~ '~ ~

~ %

~ ~

t ~ ~ ~

KIIN' I~)

%35R@ggng

"-0t~

~ ~

Page 323: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

\I ~

'4

0

Page 324: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

YLEIC t

O'RV 1>4

tcftSS Lt't )X)r>uctOM LOOP At025115)SEC DWG ~ .c. Ot54>))aM) MSG/4~

LLI I CLE

$40CAPITO)Gl )cfCICXIVTFf441 PRf 1 /IF>ACER.$ 1~ED>r4.SltD,E/3

10 COMPOLPVT COCANG, 5TSTtM>4 Stc Dr>G Hi SISS>C/5

~1 vo c>~KL

1

Ol2RLI

l SICMILLELIOFgt

t> ~ Lf

Owi a)Ailo 4 110

F/4LTt) REACTORCOOLANT DMIN 2TANK

ORV 1TI

C e t-Rc 8~5

TOR00CTOR COOLANT/DRAIN TANKSt~6

— DWG.SISTA, t)rf

tcftss tt'I EO>>H

r QWLEAT f>CNA At>s4'

vc«S)rFtQL> COLLPCAENTCOOLVLa SYST tilSf2 DAvNi 51)SCOC4

8

5

8

La>

4

SV-53SET AT

GRV 200 PRE5REGULATE

HIIDCOC211 ~YStt f>rrvN> SIIBRN/2

NITROMN SOPPLY5'fc Dwro Ni stso,>/3

aa>04

)~G

Risl

SV 54,SETAT 150 0'3 I

TO 4>O CROM COMPO>ltNTCOOUNG SYSTEM Sff DWG5135, F/4 > G/4.

1>s awwravw ao La>a o s

rCOOM SAMPLINGSTSTtSA 4 SPSS OIS(QH

IitcfH ROO 41

CSCLS

Stt DWC SI29.WS4'FRO>4 56STlOaarc>LStt Oot

S129. MI3 si4- sfAL TILTER

NfAI EXCHANGER-VA ~ IHS "I)

Cs 141f1110

M

TO HOLDUP TANKS. SffDWC N> 513't, )I/6

0 R>C 105

F+4 SCRD CADFOR FLUSPUU/4

1 C1411 TO VENT HEADER.SEE

CCLTD YEL tro DWC NO 5)3'7A>J/5rC $15C$ $15

OS)

301 OPC300

RSO 300p4'.C.

3 Cc)ss CslsfSPRLY NO)11K Ocaa)O)

'Q"'2 COILTA>rt

TSF5>.t10'P400 Cttff.ETK-lo)

I5'F PLANET

41

C>L>ac>A>rs SEALSIA oi ceto) t

RLCOLC

4S>

TR Aa>$>WV>C>IS AREOVTS>OR COLO>>aatRoo>4

RCCV.400X rp

C$ 11'1

TO HOLD UNStt C>>VC> Ns SU?,N/6>

1 k P. TENT

Csssl

1

4SI2

STt>A AA naLLAICOIC

c<c

CS 1>l ) ~Csstf a il

a 4Orx

Nttl 0 4

TRAUNG5~OPS Htot

2A>L 10 VOLVLLI

I <~ a a CONTROL TANK

I O

GacLIE RAL NOTES

LfG'END

4>IAI>4 PLOVV

AUX. PLOVV

/FOR VALVE, INSTRUMENT>SAMPLING, PIPE MATERIALAND OTIIER SYMBOLS NOTEXPLAINED ON THIS DWC ANDFOR MARK NUMBER CODESSEE DNCS, It 5iOSC 12.5O4

2

5 ISMIC CLAaSS IE'XCEPT AS NOTED

Q DY WESTINGHOUSE

ALLVALVES E IIOSTRVMENT~ATOM SUPPUED bY Qw

fc)IIPMDHTSVPPUE C DY Q>V

AS NOTRE>

SIOTE5:o >oc cooc. CLtr5 >aooawaav taws

vcs 111 >NAloacv Llica>OL so Aa>o>occvo>A vcc >Loss >Io>s vacrc

D Foo coos o lr'1 'vcwis rcvcva\ vcLI 'll orawoww Lss c»os vcr a>>ca>Pcssvc >>Ass vocvaaof titsco VALvc

1

SIPERTURB

CARD

0 Available Onper ture Card

EL.

60910'EOM

CHARGING> PUMP5SEE DWG Nosit9>4t6

waaarva aa oaa \

WD

SI)LF/oaa

3

C$ 11$RiACR ROO REO'O

4J

0113 I

Cl scl

Pc I51PRIMARY WITE)C SffDWC N15131,N/IL

0>CS 4S IQHIP452

lJl'DIA'A'ORIFICE,RC. 101

TO CHARGING PUMPSSKK DWG. 5521 ~ G/6

f1141C$ 141

)wCS)45

OSX C4$ 40

C$ M1C\sio

'TO NOLO-VPTANKS. SEE DWCw515 2, K/5,

5~s>

IV NtATTRLCINIISTOPS HERE

ILAKC4/P 'TO REFUE LINCaWATER SYORAC>C T>aNKSf R t>NCwSl4+O/6

f514 ~

NOSE CONN fORFILLINCL OF SP'DIET FUcl T>5T.

>K aawa >aalv OLILM>w >AALAI aawao ~ 1 ao\ a'Aaw

w Iv vwcaa I>LI >L wso

HAND Oia Riif 0 VALVIofN>>F>CA'c>ON NV>atfRS

L ONLY IP>IOVE VALVE NVVOERSAPPfAR ON Tkis ORAWWC. SCESEPARATE VALVE IDENTIC>CAT>CNLIST FOR KOVIVALKNTDES ICN(Ncill HVLLOERS.

2. TAC'Ni/WOERS LICOF>fo FDRDRAwpac vsE 45 FDLLows

TAC Nal 2 Htw/V>OS WAPPCARS A5 H5W>OSW

SR>STRIP>fNT Roof VALVE NAR>cNfs Nol sHowN ON DRAWO>cccfcvALvE IOE>IT>FIOAT>ON U$T)DER>VEO OT AOOI>>C TOPISTRV>rfNT IR>N&fRt

FOR SIHCLC MPKSCNFcR ocMAK FRRAfcv>cpsTRKA>II

slclvt st' .Rta VORCtfaf>COO Dgt t>>iw

W

I

I

I

I.'I

ll5

Otv)EL

FTO YOUlNE CONTROLTANK TNRU SEAL WATER

FXTKR,SEEDWCV 5128A,CI/5 Cscdi

DRAIFICM ttLCTOt COOLANT FVIPSEAL P/AIEt CRCIft (4 PL>A S)Sft SK. D 30H 0>VG kc SI?54)N/3

CP)t-MCs codCAOIIOR

DV

L>

8

I'YfNT

OPI Olcsfl 3M

SlftfACOFF>

I/Lcs)so

Ct)11 ~

OCLIQSO

3

c>

~IQ REACH ROO R'10'D

Vtill TO ATMOL

*4* NOT SC Ow

0 I1st

'1stf1151

oo'151

1'/ccs)5>

54'ATt

t llLlff.RC IO9

~ CSSM~ftcCR EOO EEOC

5'ssed

L ftACR EOO fto'DAC11$1 WO

5111.Nld

>RL FU

P

DIIAINTDI Lc>DR CN

S>N

(CLLSCIP 5CTI(

cfl

IVI

CS 141

CS)44

Cll I

cs $ 4 ~

4>

SltShWC

CS)TO

EL'fV.SST 0

VENT ToAT MO3.

OOI5

3'C$410

REACH OCO

RIOUIRLD

p«R.EACTOC,

, COOLANTPILTtt.(OC>IOC)

C$ $4I

wo

~PRO)4 bORIC ACID bL'END>.RSFIL DWCa 515) N/G

I'ENT I)

PIXM LjTDOWN >ISAT IICLLS>'ACR»Stt EN>CA \54 5121K N/2

C$1$1~3'ROM

C>CMVICRALIZERSIr Stt 0>VCL Nt 5150>AV>t,

C$ 111CREJX NRODREO Ci.l 05>c

SO I

C11>F

C1104ILEACR ROORfOillRCO

~THIS DVG )VCJE IJIIQUEFOtt LJ+I Kklf3EIDLGGNf,I-2 5I29A I3

v ~ aw I o aw wavaw ar aw avraaCALcirc>at rovcc No>acr coa>. aw o awva~wa awvaw awa la aa wa a> w wwvwow a>wa w ww> w aa la>i

ww wwwwv aa aw aaww vwvw aw«avaa>war>i lw Li~ >a>aac> wwl aa~aa aw awwv aaavw\aw la laav laalv>Law aa N w walwwawv w>aaw

INDIANA~ H>CHIOAH ELECTR>C to..DONALD C. CODK

NUCWLR PLANT04>ooaaco N>C>OCA>a

AMCYCS -REACTOR LETDO

8 CHARGINGONI> NV iviii >O>

2-5 I 2 9A-Aoo

KOC>a

AP 't./0 41 P(7CA>C lta A>a>O>CO

FOR REVISOR DKSCIOPTEPI SKKFKIVLRATK NEVIS>ON RECORD

FOR TIC5 DRAW>WC

8a '

C I' o I M I Ff

a ~ a a ' ' ar ~ ~ ~

HLANILcscc>A>c >owcR sccwct toaw.PAOAOWLZ cbl TO>it

- '9I)134) 9t ),8$

Page 325: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

'l

~O l

t

Page 326: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

* I II I c o I 6 I II O

~"J K I L I N

~ e ~

I u31 55

(1('l(Z)FN CF) - CPXOUTSIDE iteeACTO(5 CO)ITA.IN)SKL)T CSENERY(L NOTES(Nt4) CPX 419—'TC) ATMOS.CcwltrS~ 8 IN) t) CPk 411

(Nt 5) Ctx 456

crxCCWI)04 'WI)S 4Ccw)N.S CCH))d'1CCVI)).2 CCWI)S 2C(erl)1 ~ CCVI)t I

Iene)CPV 454iktt)CtX 4125 0 ( 5-Z Y)Nwa (N ))CPIC 1st

CPS

451t.t W)11 ICCW)12 2

LEG ENDcr>a)efvncr Iew(r ))cri.ale(vn

fkoea R(ACTORCdoaawt

CCW221 4CCW)te 1CCwttttt

I) INS(Der REACTCN2 CCS)TAINL(EL)THII (4) REACTOR

ta TD ALA(FOR COOLANT PUMPSa c(KCAHT PUKSL fKka(O

~ 3 CCV\&.ICCV))l1

CCVNI

'fw Ill

I

)

4'ld 47 CTX47

8'C ( CAVa)DU

(Cw

SKE PIIG- 5129.G/1 COUOONENT,CDOLIN(e SUPPLY

(:ONDDNENTCODLING RETURN

CFZ C WI)C IC CHILLNCcwe)CCCWI3(ra

fftc(

H 34-J

4 CCWI1) 1 )$CCWI)2 4

5 Gtla1('H t tc.)CCwtta-tCCW)tl'1Ccwttc4

~SW 1acr )))4Coif(R CUID(LISRWC COOL(R

Iten.+r('

ecbe ~)o 0(e +2))PE)74 ~ > IP(I( 4

CPX cpx~Its 461 466 Lr)++opx aca IHI4) ctx ac9 ~ fees

Cr) Cat (etr O Crt altCPDCLS Pit 1) Cta aid

I) ~ere I I re, ~~efeSKE'TCN )r)-

Z'4)

RELATOR QSIPORT CO()LERS(VYPICSL)

7 a)iCTX44

CD)

4)ICCWttd.~l CTI 451(Hei)t(-453(N!S!

C CAHLCfralwt1454UITA)(IAH))URNj( ta 4 5) (lanC(wttte $ IO co

(t I'ORUH f((rft(5 «Ito ((040OH(e(t (00(IHGQSoxcc lave ck(ia F((05(K ONO'5135A'N 2 gllsr I 4

CCW)2)-4(celt)2 )CCwtlt 2

AUXIUARY PIPING

FOR YALYK,IN5TRUMENT,SAMPLHI0, PIPE MATERIALAND OTHER SYMBOLS NOTEXPLAINED ON TN!5 tfar4)AIT1) FDR MARK HU)48KRCODES, SKE DfNV~ Il Sio)

I It SenaOW bY W EST(NGNDUSE

EOLNPNENT SUPPLIED 8Y

9 AS NOTED

r ., LETDOWN NEAT9 EXCHANGERCCW Ill

Ccwttt IIDO Ctli

Utt(R s(akkcCCWltS 1 Di(. CCD(ZRC(w211.2 e raCCw)IK I 45

H 2

R, ccwlt)t l 3 )P1 lj - )Seta()I 2I

ccwttae 'r ff(tsaaLSARRIAR 'S)560)Iccw)24 2 35 4 HtCCwtla ) +3>H

1 Ccvt)a4 3)SM~ CCWISO i

Lni

ISOLATION VALVE,TEST COHNKCtiOH CCw estAcl TH

cern))4CCwrl5'1CCM21 2CCWI)0)

ELC 33LO

II

C++2V

ug

(TX CPA (Fl(CW(60f2'~ SV.C8. ~4 D, AT)2O POT4''92

490

aeOS8)20CL()SS3(5cctn59

Cta PX

~491

rORAIN ™4-((W267

cas KatCert

~ SIP ~ c)D(Cells

Ceh'W1

Isd t)I

A(L PIFDC TO St ((ASSIS'l2ALL TOLINC To SK CLA55 P42EXCEPT AS NOTED

A(L EOOIPMKNT SKISNICCLASS I EXCEPT AS NOTED aa

5

8 fDR ccdc (1ass 6 AH0 s notreCDUV(clxks.te( IN Of)VUPARV .

~ ct)ters rd AUD )Ucefcas tstt)ksr Rddt VALVC

4'3 20 LfRD)4 R)aCTDR SUfPDRTCOCLkc.st( TWS tWC.SR H 2

CWI)SZap;

e IV4 'Vlrlrto Xnedd

4C(vtea~)3t

( DRAIN+~ I\\eel21

CCV))i'ICCWI)I+C(wl)i 1Ccwl)I4

CCWISh)2II 2

t;=,I 4I

I,t,'J

4 r

CCerlSS ~CrlFLOSA SKK DIC 813(Dk.a)N 5(22A.FI4~erne(e ~~ YIATEP, CCS

(1 Ex(HANGERCf)455(NTI)

FXFI",sv.cts.t Ai )455tH( l. 55( „II

td FLOOR DRARI CTA )

Cia l LION() 451

L~aob DN21 SiAtctaerftnl 6r r I fccw

I-, „„If

Ieeeaa arete»ere eeereeaI)Is

I)

I X )/SAFETY VALVESKT AT IZSPSIG SV 21~

Ifz'(7 terr.. Tpsc.paaki

qfc VENT TO ATMOS

(014al ~

FRONSPK)IT FUEL PITPUNPSSKE PNG.SI5( M/S~

C Cw) I5e)0''DA451 (N'.I)Coa 453(IR))Col 454(kla)

Dv

cr*4

CCR(1))150(A)ON VA(YKTKST (OHH(CTOH

(la ~ S)N'.)I tq'tA4141V24FRC)4 R(ACTOR

~coo(AN) NI4

I122 Ne 5

(d) CDR Coot CLASSR(SYONS(DRA)NS FHC 15( DOUVPARVCatlNDS )0 Aro IHC))f015 terc)R'LT HSRIAAILYclose p vaavL

CPH.TS~ ccwial )

4I ICke44 ekev rtee

g Nr.cacrac keaFC.

I(RUK a(csLYCPA

CFH.)5

CCR.act

cg SV.5'KT AT ISOPLI

Pe). (e2 55'RAUI TO F(OOR

~OCR.456 r

)0'

2'Cwl)C ~TDSP(NT FUEL Pit.SKE DIIG.SISC.JISq,l

a

CPH $ 4~~ CO

cpx0 wre TIAT

rewed cee r e) ccr eee~o04SA

~CCR.45) v I

ar " -"I(50(ATIONIVA.. CCW132

Ctl TEST CONN

460 Id NO()VIT Cfa

4ld CA 55 r Ti~ Sr

4 ccu45

5(IOGPMTI J Cw-

tavceeatc sereav to «asrccas cftvtocssoes scc paoe.sets

4

I ~

~)catac) CCrli)4

roc» teeCFI44

C Px Ctt44(

aapCT)

fel krcaer acerecta serreec\

~ 2 err race eecra~ 4 ceA sere'r e SccRr re taeearff)ae)fG

Hatt( vrc UNIT trcrer Dcleceeatcwtort)cr ceetorfvt kfH)eecaicw reil 4'HLCSS cttrcardc HU)CD

5

(e~ CRY 445FC SPFNT DUEL PIT *

O' HEAT EXCNLNGER SC P 5(ISHIC C(ASS zt Ov

0I\» rC(w)er e(r T

ÃoI f

vn RII5eo

e

L 250GPI4

t4;)trr(I Otr Cf) KL COI))K)~, 5xie)oti 4

If'TO CCrrraeer CCer CTS

SCC Prf 1 SISSA eefl

~rJi'~ re(eeM ~~ IMeeb

2I3S GPN

dc'cari(DOLING WATER PIMPS

~ 5(E ONG. 513'SA,J/G

~TTN(S G)ICE)(ADKIINL)UEFURUNIT 2 ANC) SUCeliPSKORS,OTVCI I~ 2 5)35 RCV ITccw ees

SOS ate)fl.

4'l I 475 «g5) b(SPP

s re.t. Icrvcv recce«Asec cas coeeccsacfeasce prf I sess cvr IDCN'ter)Cat)OK NUNS\PS

5(t TN(5 DWC,HI7CCv 4

'@tee)re FAil'ED rUK(.D(TKCTOR saalt(KHEAT KXCNANOKR

CCIT)ei

S)4fd.)U4 ~ Dtfb HIS

Q OotudkcSKETCH

M-r,'AILKO

FU L OCTECtoR 5Ct(SAMPLE li(AT EXCNAHOKR

425~Y4 52 c)R2'oaHS

CCW)42

KL.591 0'

DNLV ISRDUC VALVC NUUR(IISStreak DH THIS DRawkc. S(C5(tat)art VALVC IDENT)fKATKNUSF FOR CCUIVALCNTDC5ICN(HCRl NUNS(RS.

2. tt4 NLWSCRS C(kfftd fDRDRaetrc USC SS f(r.lDWS;

tac Ne -t aswvfccrwat'FLaks As; Nsvedsw

5 kSIRUae(NF RDUC VALVC IISRXNrs Ndt LHowle cw Dkavrrs(sctVALVC IDCHTIFICATN)iiUST)DCRIVCD RY ADDINC TD ~

kSTRUVLHF NU)ad(R:fft) SINGLE 0%%ASCVI

~ f(W CCC(ct SRIIXSCVIASISI)f(au)2(DDIHG)RN

I ISO

~4 t)4 ~t'cw stt.I(2'os

ace Reo eeSOGPMt10

ro 6 FAD)a t(N(YRXNCH

CF(450SV LL SCY

AT 1)0 ttlCCWlld

F.C.

3.325 GPNVH Tore ~

CPDUN4 cdeLS C Clo FAHMOTOR AIR CCOLCR 46CC.DWR..R'Sftdr Jrd ~w ~~et'Cl»)er

ccwsssfreerwre cpp) 3 I Steerro I tkcea raeccce t)fcLtcrc4tow saw4 ~ c arXtcvrnln scc slf'ae.o'FI.455 CCW KS

XCVSI ')

0ace))J

FOR HICRDSRN StATUS 3((Rlv)DOH R(N)td CDR )H5 De)R

O-tt.tt 34 P~

CRh 465

IC70 Orerew

CCWISS 4) Iccwc)s sy '/(

cave)srI

g I).I „

~Irl

t CCV)00rraetr 1

cxwers orI I II c.J

Circe I

no 0

Ccwk)ae 'CVKIS4 4TXcp )8(

45 I

I

. 456

IKl((FCSZATCR

I

I

I

I

I

I

I

dOV

FOll R(V)SOH DCSCR)FFX)H S(ES(takA)t RCVISON RCCORD

FDR T)RS DRAIRNCtCO 'DCH

II CTx

II II !'l:.- Iit

tI 5K

~ t)IIfI I

"

5OH3()

5 PUMP DISCNARCK 10RKGKN(RA)IVK NEAT cllEX(NANSEI'K'EDVIG51'ZS,LI8

45C'TX

rre aeew VMewwewel ~ reccecleeeec etre eerer crr, wo eew weeI)

BfC(XI(NS(R I

8 Cl [PX I ti)KCWSO)

ha

't6$

~eerw Me r r er ee e reeeew ae~ree r reu er r eec Te ew eee~ww» rwrrew ee VT ew» wert(„O

t.:;. t 6'fV .

gg~

CPA

~OI

«IDOO GPu 457 . 452id FORA()I4 0 CPM CCW274

tl LA~1

ceeewrcxx.rer. 4 $(CNC Trtrj

il

M eelew were w 'M act Iree cwra M aw eww werwwc w Merewa r» r eo e eewe ww Mwe,

I)4))AHA~ )UCHIUAHILXRTRIDCCL

DONAU) C. COOK -'

NUC(EAR F(ANT "

~ekceeea eooecla

I

I

[

FLUID CllDRIVE cll

~IR /c)rare, e CRTCOC

~I

e)rr

,I'ft

P~rreaaa) ar eSO tat,. CVI~di

J L—

ei cce)eoI t.II

I

I

I

I

L

LlaCC)SISS

I

CCWI)0

I

(141S

DPIC04

Ol8(ARINGDILcoo(KR(5 GPN)

o~rr .. lF( IA AM

COMPONENT COOL(NGUNIT N()2

)

COUR(ds CF90

VENTCDNOKN

SOCDMp

cctncrten AegSPODE KK,

erect

et(dr

ELSSTLO

r4r'4 SOI

(IKACe ec)O eeftea) ~ - I ~cacna ~COt Cot

I)0 (ISGPM) wast K RvAPos(ATos((ov LLcATcoPIP),SCISMC. CLJ(55 2(t (a(L P)PIHCA ISTO 86 CLASS 442) I

~ ~

e eea

A

t

O)L tt(Acra

EL 58I OI~I~e

CR(tt'C S

SAMPLE RAcg B

KOUCNI Clat)RK tPK(7 S(krwcttrkt.Sk(HPRAY I" '(Vtdkx

dt4'PUMP SUC(iON FROM OII RECIPROCATING 5Al1PLE RACK A8 z)O c~ ~~ VOLUME CONTROL TANK CHARG ING PUMPSE)S)31~II 5'KE (SFIG 5129 LIS

+ISCELLANE

SIPEW't

CARD

"'9re

Lr ''IL."-. 4

so Available On .

aperture Card'

~ A~ w reer ea ere r 6 I

0030 I83'''l9I

9 'ia*,r

Page 327: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

F

~ f.

I~

~, I

Page 328: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

~ ~

~ ~

I ~

I

~ ~

Zk !BLM~

~ ~A

'i~ ~

gb @kg 'e ~

~ ~ i~

~ '

q'y

e

~ IIRRtl~ ~

~'

I ~ ~

A A A

m ~ ~

~ ~ I ~ ~

~ ~

A gP

Page 329: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

l

* <~

Page 330: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

0 '~

'

4 ' l

rZh dh%F %F

~~ gms~aoii:WtttWg

l

e ca~KS IV

~

'ox+si

WGII~~KRKKEHKKGKHI~KXREERKR~~KK~KEKKKR~R~~KKEEKKBKKERK%~~KIHEKKKEKKEKKR~KKRKKIHiREKKEKR~R~EKiKKBIKKKKKKKKKR~~KEXKiRERREBRKR~~KBIEBEERKKEKRK~~KKEERKERERKKR~EMIKGIEBKEBKKEKKE~~KEIKiRKEKKERKK~~KEEIBRKBRKKKKR~~KBIESKEKKKEKK%K~~REHKKRKEKKK%KRKKKHKZHfKHIEXRKX%%EKKR~KIKEKEEIKRKKRKKRKX~EKiXQKIRKiREBKKEK

~ ~

~ I

~ \

tss ~

o E ~

~ ~ j

Less

MXitK siss~ I'

I ' 1'

t~T

%F l ~

~ ~ ~'

~ '

~ ~ ~ s ~ ~

~ I~ '

Page 331: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

P

l

OO (I

I 4

Page 332: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

r A I C I D IE t F i G ~ J i K ( L ' N

FROM PRESSURIZERUOIND 5PACE~G 5)ZSA/7/CO

N51

104

)IRV )PZ

HSX

102

NRY )53

H5x

RV.Ioc

"Of LEGLOOP 3DCVG,S)ZB N/

KS As)

PECAY CINL

F M NOT LEG tO

LOOP 1, SEE12B,E/5 )SEL)0

N5 )jIOI

ACCUMVLATO'R SAMPLESSEE PWG. 514'3, P/4

ISX

1

15X 15X

2 3ISX

4

r.c.

)RY.3EL 642'4)

HS 3)t+

FROM PRESSURIZER STEAMSPACE .SEE DWG SIZSAsrsl7.

1151 ISIcc s

FROM LETTOCIN ONEIf SEIVIL INLET SEE

2 5129s )Ut

Il — -s

1

CPN BI

~1

5

~ VOIAAAC Sassr~s

SCS VKSS+Sats 4

anots Df GAYCASSC\Vttlt StrLTASC KCADCSLSCC OwosdfoRCC 309 I O)OEOI)

ctort Llsttt 143 051FKSSC COSLAsrt ONDAA 4 TANICSCNtSct Dstc COCO)A COO 44505jiFAWFRM Irtttr IPRCSCVRSXCRCrt LAC0 TA44 W41St 4 Dssts ACCSA 31

C4org 4'O04VACKi CVAtsVCittSCC ovtfsCDOCSSAACFO CCOSCS)OCF

Fttosl'7/CVC6'-SAOLD\psTAStsc SlVCNV SCC DKCIS 5 I32. su4csHrgs~wcssu, „gp/crDCAGC r441 5451VfvtSCC Ossa,12 513ds a/3

44/ ~

(YR ALLLCKC isxc5)CACIPCO~

yaco dot

CL ratlases 3 'os

'1411

CCOZOI 501

051

CKOALFAt CV ~~ 55$CCSNISLOL TANg VC

OWS.2. CSCSAC Klc~

Ott Xttt

So 303305

sv r1 RRACC00 CtaWR0IAS LFSSVDRAKC 'cAwVCNIC. Ct St 4 ~ FFO

TRCASIPIITV2FCCSS

LCLtcr 'VA4is Vfi4t Stc DKC

Ci 1 4 A~*rI

' "Oh.dt)SFI 4ACiD 7 VA

vt I'I SCCC DNO I ~

MSO5 101

'stil

52

.aIRgssfstsc

CLM520

'LAAC )4 53 FLCVCote

rtos452011243PI.SI'OHS.TOO

SOS

~CVCS SFSLDVWCAICL

+ SEX OKCA CZ-5132tH/5

4 +441sostSs3txDKG

CL vsuc toD aasggr «1

)LSCSVtt'SCC siKS

t<gO.VCO 1OT

)rfttrtf Icdssff tSKSCKCLIII Sv tssA vtKCASS) 'A cca/'

LcogSCALSs SVSSASVSS~ Atc SSASir 144A/4

VCS HDLOVW

1 I44VCHtSCC DWG123tr1 F/5

ICCIDttd~

tP

L1

sf

CA005DWl SVSN'Vite 1'Cc VKSSOWCI 4th

3rd SPALr) GAS Ccr&LCTON|t4 PLA)jTAIRSEEDWG.I231205.f/

I'NIT906tKtZERO645)51E orle.SIldtce/3~

PL. EL587L CF

ALLSDL VALVCS SCALLSGL VLLVCC OSOW

CICSCCO~ sit 4 11 Vt

srs.cc1 + t

1ftYF)

AUTOSAS Al

(

TIOYZEIL

NCOCSfsf N

IACC SKISOsst Ct)]

Ktst5

vr '74s.ssd

~C. 45311

lFRGLI LttoowNLINE AT DEMIN,OVTLET.SEE OICRI 2 6129A Ud)I-KS St 1 g

sist rwavKIN rs sscuvsc*L voSACTCK 4 4 44 crsc I'Sscsvrcscs Aac 04 trat I vALscL'Sl

11-sorst AJ

AC-5152 J/8

AAKAS

AUTO~LSA~ iv 5%5 AEtt)ELf2'EO.TOR, VIIST5 N'4 1 4 2

14OTE TR15 'tox. ~ ICFI Of LAVG )SIDICATE5SOAR'ED COVIN trrV4TED ItlUNIT ~ 5

Al.l SOLENOID VALVES bY(ti'k

.s43 F ' v44

CAPPAD

CAS DC CAY VASICS SAISWLCR 5C C Osvcs tx 5CSS,SVS

SAI'ID YCNTHCA„csc

Crt stat SSA ority Cdctst44541

307 3oo

4)

i2CE

1

4

Liri 0

Cs

si 41

e A

ts2~ V'

0 3-0 0 I'I n D

tr Z ti v AsvrEceuRK

MOOD

rrvcut vo Vvgsvs ICCA CLKcl.tAHISOS

nss77

SICgTP! MENCLO'SED SAMPLE 51535C

12 CIC M)(ALLVALvcw DY'IC MANUFACTUefe)

t4OTEL TNI5 PORTIONOF DWG INDICATESSHARED EQUIP. LOCATED IN UNIT-I

rtR44,515DAIAI.OAALCKAC

rc sNo w'104

~

)

Z ~

p

3OV

~I a9 Z 24t 1 2 0

GENERAL Hat tS

LEGENDa MAV4PEDW

P)JX FLOW

FOR VALVEs 1NSTRV MEN'TiSAMPLING~

PIP'L IIATERIAL,AND OTHER 534tboc5 14DT

EXPLAINED ON TNISDWG.IAND FOR MANICNVCAtssER

CODES, SSE DWG5.12 SOS 412. SK)4

SYMBOLS= E3 OVICK DISCONNECT

COVPLINtr

ALL EOUIPMENT 5C. Et

SIAPERTURE

CARD

THE LC)ITFH ACFI)CEEBrANATIONFOR EACH COrrsscsIEL)TIDSrftlFICATIOI)r7~5ERIS,25 IPILcoo otstctc vrtso ACOTtio

A ZiDRAii4 SSEDWG.I SI41 ~ LIS

FI SLEV SOAK

s

O BY sWE5TINGNOUSArs $

c

7ALt. PIPING TO BLEXCEPT AS NOTE~

4~ ACFCCS

0VLL» SSSAVS 0A ~ w.caseW Crtso/ACCVA

Lrog cotocccvwss &Nwnwvvcs -r~~ ~

ICit VA-V=4 SNCRACCAmc Frith. Ftcscrf vncvc.tNvwrsv cct c. cent'o csscgrs%I 'osgnsrsss vgr CN Istsstunkav Kocrcgsos 4

OW 4 SACAAAOCNVsAC

Iso Available OnAperture Card

/ TO 54MPLIS)G SINICSCE TNIS DAIG„SX'MAt

5

sass dFC

s 4541 411 4

AA~L A AKK~ s ~ ~ As Arts

c5x Xol

~ISC 102

PISX 304304)NSX IIN,IC3

705X 300

4'SIIC

4

fxost Yt)tVNE CONTXOLTINK G15 SFRC'E SCEttSIG. 5119 A, I(/3

501

I

,.Iit ~IC H01

110

ORV 104ccf cs crtso

P)CR'I OS

HFZ

103'103

ct

FLUKE ZtÃ)DUAL .R,

'EA~KZKlL,af'sf srs Agric sL clice

KSSKSSIA I-151 ~iVS433

)IFV.SO3 'I SS

F.C

IRV 304

FF(OP('W'.P;" SIDDZI4H=„ATR(TiDV/sLHEATE) C3)ANGEFZ. SEE lDWiJ Cs. 5)ASSJ, Pt/5

4 l

Are,~ CAVA(KSILSlKt 04 AKN

I 4'.~~st ssw I

ss ~CAL 4 sw,vl

III

'ItttIIIIII

CA II

~4 SA

scilZLr l LA

~I0I

su

.-lCS l g

) l~sd Ecc

KEst

vs

2|

)5'od

tt TO FAILED Ft)EL~DGECTOCt SfE txtQ,

BIIB, ft/2

35'0 5 TDSIC 6CDSCFCLLS/f 0XUS)6WA)ttFW!)5tt

ONCA$135, 23

5CX10~HSI50 ~HSSIt

NCISc'O.D. TVSOCCWIPCREMT COCL944

ICATER,SLE 01CC 5115.03PP>-

NTATEtCHANCFR

(COIL TYPE)CTTPICAL)CLC 501 lt

NCS

SL45PLING. RACK

'SRB'C

SOIIe

TD BLDG EXHAUSTVENT SYSTEMME vvOWG.SIC 8.C/I)~

10 XIO

I

N I

I

f tI

III

N 1 II

A

Nottoy

CANAL C acssst

Dt SAVSLC 41

Ksis5

CA

~I

7

I 1

3 3

as

CL

0

vs~r

)C 10 VOLUME CONTROLTIRE 3EE DWG,Z.SIERM/4 ISX.)

ISC 215X.3ISXA

'CANS 00 ttAVCO VAIDCNttrscA'tscN Nussacwc

I. ONLY IFCOVC VALVE Nts'HCTRSAFFCAR ON TH15 DRAWCCI'A SCCSCFARATC VALVE IOCNtIFSCACSCN VLIST FCSI COVIVAIXNfDC5ICN

I (HCst) NVHdfRS.2. TAC'NVHdcrtc IAGOCFICO rett

ORAWCSG Vsc AS FOLLOWS:TAC Ns'9 N5WYs05 W

AFFCAR5 AS: NSWSOSW

SWC5tttVSACNT ROOf CALYX IAARKrsv5 Not SHowsc ctc oatwfsctccxVALYC IOCN'tsFICAtSON USt)DCRIYCD d'f *DOVCC TO~IStRLACCNT NVHdtR:

FCR SINGLE ACIIASCVIfOR DCMXXSNKASC:VCLCICIRCANG

7

p)c«'TO VCNC HDKALCC

Dssd drdsAsst'5

rtoss Visits ogcScsts,LI&

CAlf

Oo?KHSI SISO

rc'SSSS~

N 1

IUD

Ms IC3

141st

I ft Oft105 3 0

45ltdksttcI/2

Kttss

Iot sssctctltll 511105 511,SP Rtvt)KNRtowo IGR TMC Iwr

')t

4 I 35)6SffATMO III

i4

CAVILED

55.'TU51U&

tttEVFJZERLIGND

51)IILE Y135tt(a)et-2)

l 9 9 7 /rJXv vrrvcgtc a 4 rsissco

SR

FDR RCVlSON DCSCtcff CFC 5CESCRVIATE RXYISX)N RCCOIO

fDR TICS DRAWIHCI1

t

It

t1

I

I It tI II Sf

I

SCCSTALLCD WHKM TASSI HCcssigwccs Ctvfs 4 FLAccc3 v s sAAN A s4 vsvs ir ~ Artsass

tsccswc tares Hssgt erst w K sngsVSS SWLSS SVS K 4 4 SS 4 K SVS ~~ssKKs A 'vgs ss Ann svs sv ssAAVNVVVASASS SV I~ MASS AK~Assis vwv sr AK ~ I~ Hssvc crw s~SS SV VKK~ SS SASS KKKS

tLcr

r SV ICOCtff AD lfFSIO

INDIANA~ SAACHCCAN CXONCSC Ccs

DONALD C. COOKNVCIEAR PLIVCT

VOLUII2Eostfe)LTAICCSCSIPLE4/f 55EL

(OP t3F LOW )AGRAM

NUCLEAR SAMPUNGUNIT No2 0

T 1 FB

)T'503'OSIASV LSCVCSLODsso Stet.t/Scu4cffl)

I/cg rssx 2 524) 27~I t~cEt 587'A OsKSS SC IsI

'7

AV 4I~

)CC)TIE-Ttclb DflG. MADE Vttt'OOE,FOR, UN1 T F 2 AND SVrc.RBEDESOWtt. 1Z. 5141, REV.tb.

~Cs

SAIIPLING RAGE'SRCtENCLOSEP CABINET) r

l/ J ~ CF„FNts s

it //rrs

~ s

~ ~

~ '\

S AS%ssssrvS

I .B I ..C. J ., ~ D .2 E GLs ' r v ~

~ ~~

~ —~ -- ~ -.-- —- ~ . —........I NI J V

414scsc ctccttsc rowct tcwsscc c)str4

1 440404tf 1CW ~w v irvrrnsvvv4s r svnrN~

I„.t.

ct j030jOE'Tt'9:"~j'"

Page 333: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

II)!i'~

o<Jt

I~

I

~ ~fP

Page 334: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

t

t'f

dEh

tf

dh,

tfd2'a

tf8Zh,

C

rXh~r

T

:F~'

t r g

Lfh

'

V .'

t ~

LQ l

Hr~ ~ rrrr

dcL dh%P

d4 dhQP

t~f RRPzK~dh

%57 %W

db dh

t f

I-t ~

t ~

CRT'~

~ ~

~ ~

~ ~

T.

~ '

~

Page 335: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

)

w/~ e I

tL

H

c

1

~ff,

Page 336: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ 9 e IS''A. '

0 I)' S-Z

c D I EN

~ s

0N RAL NOT S

~ ~ L I

CPrsttSC$ tIC'IS

IIIP.C.

~II.I'I1st2 CC

Lta ellaacf n<

lat

BLtrps 'I)

P LCI'N

SLIQ

Nar a» MCasaarc IIpcac')

fC.

~ct u.

FC

Ilt f2

AC

ILL fs

CP jsl

Ctafa'345NINar'va

2141

POST~raCF H

I sr corot I

g Tl

es ) I'I a~ Sill C

CLO=HT 'OT(TALHMFATGSWSI MOH)TOZIH6

INFF PASSEL 1 Sf)A

SFS rf'ttIla

aao 4C AOSO

ICV'e~aec-SFO S

Ott 41 AOte Tf C raao SC

Cae OC ~

'F2 CALIOCATNNDAO To OaeaelcFANCL ~ SF 4Stctpss Dwres VT

NOW IO

ate(sat Nlrtf)

R) 453

~ Cewa( Cll eora 1 3 Caeaaafwe

~ a ~ crs etl. ~

. loca ~ PISf tsetseCC 4'SS 1XTlc CIS

CALsatattatf+CllwOCC'2

CCSS W2ccass Sf

TIL 214

Vt CEASE)2T (LCS TOsetapct ppftCL' SO t)'siCC'TWS OWFP KJT

s aaotov tp el» ttsr acoocetcoerlseetvf pe)call ~ werNWlrsT ~ ssl al tcc taNIONIN vsotIC OL lail

2 acl csastpNNT Ic cts)NIC cllllJttctpf Ar Notcfa

SIPERTU

CARD

Available Onerture Card

Cess sel 1)tat Oee

t0V

ea

S

~ SC

4f FC

ter ssl as~tlag'"Ntel

FC,

~ etI~ILIn~

CC

~ PI

~LalgCC

Cta

~ I

ILICSLO

'I ~ C ~

ILIIOS)L

~It ~ 2 Pilot+-w tl

111St'talll

Isa

. ~tasse C

Mesa lettres esI tee IW

ra@ale

Lla ) cL'ILPO'L1

~ PC

(Stt NOTE I)

SAIIFLCt)ss I

LOCATIONoepsa vl eosstsst t

t)a

t ~

I O.SC)ar

CONf. DOsl2 2CON f, T rv

covcasa eaoaa a couosrDw ACDNI VDLVNS C

DWCN CONC VO VN If

Iel

CS'C

~ INaartt

3TLSFLLC C(ASS I

CSO v'M

2 Nof2 s) 'rSLVFVNS FLMSL

2 SP.S

Ite SFF

I

OC'93OC. SSC

~ r lel

tII Cf

'O'f

Aar

tat asYF

I'W~

ctl sita~speerrlC orSPPSPI Oeerie Nstr'raa'el

Ctf Ol'O~Of 'ST aa

ala�'C

~111)N

Ctl lla~saws cc octopesesow\s ~

uc sss ICLC SSC I

1rrotOCLN (tarotaealfl tcI

)s=) ea'O'

SOS)

ep alo'a'est'

Ifsp 4).a I

~ pa I

I2

far)1 ~tttr

CN aw so afttw'atc4

wf1R

10 '59 eaeo-os'o

IfODNCC yOO tt)AQRO Lilt

~ el

IFf 12'F

~Ot~ospeoar

'I

Sr.lite 4 \V ICTIL~Ilt al tao

~pl)I™. )fa)SC'O

~sp ~

NS ~ IS

ALISkcftO N GASoat esca oro tlfINS sOC N neater Oaa

~ll Ost Pa~f crete tec

(cct Noft OCT

~ tSO Do

SCINO 3aa cooslo ~ tsa IPW

Ptat CNeavlfcNt IpeA tolT alcesevt ceelapsttcssTNt~o Nrleeacss saesetc ~p(~loft(ptattta) ( TE-h )

(ate

Meet�)

'ttACCNT4 aa Crlesoa Ae(ol rap)Ctsssascclass OL

nc tsssf

tt*DtNTOao crs. ~ ssoaa t

(Of eat)'ISSStSSCcia' ') fft

TIL 215 2

~ (Sll Not IN)Tt ptas

s . s

~T Ate

N)414 arewSa(aao sert 1 )

3 3

'OCSC

1 covrta'seprlv Lotrttp ov tts 3~ tcesrc tees» coettea recce

'I acasaatM relet sptp vp aw asser~ eraapettsaett cvacls aeo~apttl rasll ~

5 ALLPSFINO IS OsO tlctffasrsorta

'TNS UNITPREFIX DESICNAYLOI2FOR CA(IICoeaFONENT LDENT1 4FICATDN ILUOLGER LS t (fNLCMsOT)LERWLSC NOTED

~ a

NI

NAFC) OPERA'TED VALVEIDENTLFICATION NUMBERS

L ONLY IPOQVE VALYO LLVMSIRS GAFFCAR ON THIS DRAWWS. SEC5CPARATE VALVE LD(f22 IF ICATH)IList FOR CQVSVALCNT OCSICHVPCR) NVMStRS.

2 TAG fcfvlDERs fsooLFLCD Foe,DRASCINLL VSC AS

FOLLOV:S'AGNt: C.NSWYIOS',

AFFEPRS AS: NSIOOST( ~

V'4 5"5",'ALVE.

LOENTLFICAYROS ()ST3DCRLVED BY AOOIHG TOolsfRUN(NT LIL)VSELL

FC)t SLNCLE OCCLCEYLFTLT (tttfLS IHPLASESTLFSSLTLEIFO

R.D-FS

4I ~

I'~

F

I

C;

~ e'

~avttCCTOC COHfcllMtNT'TDCOCCH CLMFLOLS

LOCS Tl0 N 4

tsa II)a'S

vpptacoslf volvet wNt atter ala sl ev N W

DOllC

SSLSISIC CLASS 1'

'

Bf((NsiP INC

(Te:6')

(S( 4EP.

fOR REVISOR DESCRFTON SEESEPARATE REVLSLON RECOLO

FDR l)95 DRAOLNO

Lt oaveat Itre laTa caereessl stSl ~ ow t' lose

Ctr VISSI

I Vt

lC

aca sowPPCI.. (TC lf)IO 111

~ct ca (Tt:s)

Steel OC TllfCaw I Crew

Osa Nc

Plit

~CC

Nota)> 'e'ee

stews e 'M Mweet w 'Maeltcaaafcnec toet ~ Natscc Coat. Iw N ae NeMa aeeeee ~ ~ e e ser ee sr epwMsese area w ews w N INS se eve eee eeeepw see ew se ew ester «peer M~etsfr ewwe \ M4 Ip lleeet StepNa ew eeww wte t\\N w eee eeprel,~wr IIN serswe ew pwwe

OtOIANA ~ MICNIOANCLCOTIIICCCA

DONALD C. COOKNUC(EAR F(ANT ~

tsVDCNAII IISCIOCLA

FLOW OIAGEAM

POST hCCIDEHT SLMPLLH6

COHTAD()LENT LSYDEOGEII yUHII'foeOIL NO t SLALD O

~saevaAPC

~ J P

»s I ~ INr S

«sD I E I I M

I wacs e)etawa . C«ese w

800 3 0 9.0183 - I,I

~ ef

Page 337: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

.lg"l.

4

C

1

IJ

l

Page 338: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~ er

* I e C I' F G I N

2O 15 2 Terr 'pro

!

I-COLO LE GLOOP

I/2) / Q 0/5 (YVR)

st ii1la 514 ILII'/zjI

SEE OWG Stz(FF/4, F/2, G/B,N/4

!

COLD LEG SII~ ttlLOOP I I'lty

!

LCOLO LE G lar2J stiiNLLOOP Z ~ . r strits

I'/zy /t COLO

LOOPLEG l„„,„QX535

I.In[inz

0

IFI3/4

ng n

)LID52 „1I

V

}3/4

I'Iz (5'5 r/I'

II2

Ei

/ ZMO 5(

5/4'1

I-2UI

2Ci20V

/.IMO-54 u

I2

2CI20I/

0i0C

v/ lc

ln5/

~ IF I CO

in2

)'/2

n

0

41

IPX

I'

HEAT ~4CINGr r TOPS MCRR

51ISO~ rT(SIGN»

Sft T~HISQWL(//4I ~

litCi t

5/4'ISINC VKNT

SHits$ 1 liSM~

5 Eri Sliicsst riCM

~4 NO1112 DRiiH~ NE

rritl51HVQRIIN~/SIIASSSIIES

F6R dtsYRUSI KNTATI04SCK TAISLFTSrt/5

~%4'SUCTION BAYVCNTmSIMIM

Miii'S

I) SI5K PLA'IK DIIIIH

2'KAI AND DRIPPOCKET DRAIN

FRSCTNN ILDW

'TAPS�

(TYPCAL)IE

IRSsgd

I~

It)2 .Ih-/

cpN 44

CL

Oit'O'rcAT

YR Acr 46BTDP5 MCRC

3 IP231

\Irscw

St I SS

SKK THIS QSTC.K/6

rlttrCbrr4SIISY

SIC TNrd

MISC. INSTRUMENTATIQMAT 5AFETY DIJECTCDN PIAU'5

NORTH SOUTH

ITA 2 5 I ITA-253

FUNCTION

00420 5(AL NQUSIN/I HICN TEMP il.iRM AT I'10 F

BiT RCCIRC.Stt THI5DWG.@

SSI CC t

VE~

tTA 252 ITA-254LTI-2(i0 LTI-Zf2LTT-261 LTZ-26'3LPI- 250 LPK 262

IePRIHIRV WATERfLU5HOILIIIL't''N 5(LDW6. Defi,

SI ISII J40 Qfl A QRIFI(K, A 103

( s»ssTO IVLS HOLD UPTArIKSSCK DWG.SIstr+/r,LI IN I'' ~i

250

Ii5V 51Sttlt 1155

~EEI

DIBODRD S(AL NOUS'INC HIGH TEMP>LARMAT120'F

QN tÃLC(KCZR PISCHAR6E LIANIFOLQ 30.240 F RANCE

QN THRUST SKARPI6 HOUSING, 30.240 F IEANGE

AT THRUST SEARlhIG HOUSING DL INLET.O 30 PSI

~SIDYISX

LSICIS

M209

511M «Fe'

SIISO

1RV 251 ~ FC +F.LIRV25''st MTQ BORIC ACID TANKS

Eea SEE DWG 513(, D/55

EL'EC'TRICSTRIPIIIEl E EE

ICHLNWAV~BQRQN INJKCTKN TANK

4ÃDIAIII'rrNICH(QVKRALL)CAPACITY 900CALS

(TK'II )

FROM BQRC ACIDTRANSFER PUMPSSKK DYYC 5131, K/5

3'IMY

N5141 s ~SI S

5131 5. 5123A.F/5D,K,I/B. i 5

CAD'VED C OEurrrn 'S (CCSP. C FK~~ 2

ARRICT. QE Nisi."PI PIN(r ATsitKTY INJKKTIQN PUMPS

r ~

I '0IGENERAL NOTES

L E a E IIE

tfAIIJ FLOW

AUXILIIRYFLOW

Q BY WESTINGHOUSE

FQR VALVK~INSTRUMKNTEr

SAMPLIVQ. PIPE MAT(RIALAND QINKR SVMSQ'LS

'NQT'XOLAINKQ

ON THIS QV/0ANQ FOR MARK NUMB'KRCQQKS. SKK QV/0 5104

MOTE:AA'L KDLSOrrENT.VLLVKSI-NstverrRNTs svoPVCO IPF-

AS NOTE.D

NSPVESLVCS IN FICLD TDLrrsiy IEUEISO EIUNO'JT TISLNLocrc IN POSITION.

IOYC. CippsRNY StsspNG

CLASS Z CY"SOT AS NOTCD.

NOTE~ CLASS t SNSYILV ~

IEIKNT CDMNSATCNSITVC.XCZBIEPEDARY DxtcND5 'YD gIICLYD(5TMS FIRST R/DTMACVC

IVITC CITCCC CCOSra 2 lCNTS IDcatrcs Tvc,xsz sraovbacYCFYXVQS'TO! INCLUDES 1vtPiCST NCSCOHALL'Y CKIVVCDVALVC.

~rsT'EFER To DWG.2-5123CFOR

PORTION5 OF PIPING CONTAINEDWITHIN L'EAK Df .TCCTION SNCLOSUSLES

NOTE Glllrrccsrar paert Dtscvatarr Foatacacailrowal IDIETvscatrrv iat rd 2llitt$5 Cirtaailt inrtK

I~ ~

SI-PII'.RTURE. CARD

so Available Onperture Card

KTriis ONCE/5

IT25

Stste

DRAIN

IYC

ZSI 4AOPI CHARGINGFFJPIP CK065-7) E

5KEDVI(t IZ9,G/4

ICI CL 2ldrtvssaNa uNR

$1IIS15 X

sKK THls DYYFAK/5

'LOD

I51I11awe

5(tn

F.C

51 tol

)RV.255

KMD 256+ I ~H~rNGDYOrrbi NCRir

~ 1151 ConSti'

SII

Isso 25'I

5141 BTIOISDJIRICIL2

.EL Gfg- Cr

~FROM REFUELIMG 'WATERSTORAGE TANK. OR RESIDUAL

5IIIt /. HEAT EXCHANGERS, THRU4 "r CHARGING PUMPS OISCES

HEADER. SEE OWG 5129, FIS4'

cut~MR PT2RACSN 4:~5 fOR VCRONtN SIAIVS Fft

FIF RtsssroN Rtcblcr IDR 145 tsoc

Nirio ~ liaY va vIDCNYiriCAYION NVMOIII5

L ONLY IPCOVC VALVC NVMDCRSAPPCAR CII THIS DRAWiNC. 5CCSCPARAYC VALVC IDCNYEFrCatrONLidr FOR CDVIVALCNYDCSICNINCRI NVMSCRS.

8 YAC'Ia/MSCRS SECD(FICO FCSIDRAworc I/sc Ad Fou.owt:

YAC Ni' NSW.VOS WAPPCAIIS AS; NSWOSW

S,INFYRVMCNY RCDY VALVC lrAKCsr T5 NDT 5NowN oN trtaworotscXVALVE IDLNYiFIC*YIONu511 ~

DCRIVCD SY ADDirIC YOSESYRVMCNY NVMSCR;

IDR SIICLE ~ PIASCVIFLOI IKLILCSSisASE:VI OPSY RCASD

7

EL612'-0''o ccsivaitca RISRF TAIGASCL SII'Cnr CM CEEG, Sitdaea/C SII15

/I 125 28

8

CPII 4'3

g 50 LOOPS Nt 2 E3 (COLDLEGS) TNRU PIPING I'ROMRKSIISUXL NKAT KXCHAIIGKR V/SKE JSV/ta 5143S E77 r e

25lCLZ fSt ttIS

IRT.IO~

i'KE

THIS IINFSD/5 5E I

I ACCUMLRIOR

10 PRKSSURIZ\RRKUKF TANK SKK

SSE DY/C 5(28A Sg.'IT3'V.QC. I

SKF AT 220PSNT)6.

D

SItra YKNT Cal

ICM 263/SII205 tNG I 8'r (g (Lr

Si 20ir

)~~a ~O

SV-933 SCr3rff50 PS OS KTVW)

NDT BV O55/4 VKHT

51iI\5

PN

81

c~ giI'Qtitt st rot

4 DO 215TO iiiliiarlttltYLIU YANC INC

Iaea OCOAli,140 262

FEC „ IF I

Set.sautaa

O'A'Stir

Fp3422$ 1 Ills

54555YLOIC

Pg251 ialI

ROIDC 4

th

51aiI

Cc 5~OC Der Cn V

g4srrvc r3sc

I I

FROM RESIDUALHEAT EXKNANrfR'N'SIK DNC

SIstirs Dtroas Ercoia rico

g'CO.KI45ISOD SCI SOS CL.O+2MS:362 g r - / ~tr

4STK 36

L4 5145.(/5- 'SX201

PDc

4 TO LOOPS I)4/COLD LKCS)T HRU PIPING FROM RLSIQUALHEAT EXCHANGER.E. SKK.tssvG 5143. o/8 4INI CC L~

51'IDN ~ CPNCC

(CMkfg54vevr~-I 205

St~4 Krg NNIRVIJ

YFcrr~' is fs DRAI/ICVSBIIO

EED LSDSf KSCN IIOS CI'1046

I)'%'IS( CE

I2

POg, .TCEEVOAARTNYNAM~lnscTeeecaE)

f4 lair'4 IIIV

reit nsccuareicac, ccai. ucaT eacaraNDUCSaero CEM cooecccs sac diosaITwpicaafIl™ MlnV (2 SAFETY INEIECTIQ

4DOQPNK=(btdiCN) teobFTNT I U'650CPM (MAX) 1353PRI (QH (D'

MAK QISCHAIICK pRLNUT

( NQTEI FQ'IL MISC PIPR2 SVAKE

tPO-261P 3510 RPM

VIDONPF) 51015P K SEVR )5KE 5

.M t.

OUTSIDE RKACTQR CONTAINMENTINSLDE RKDCTQR CONTAINMENT ~

.A i e I~c I / D ~ - I E ...,.. F ~ . I .. ~ ~ ~ =- G.

DVM

. ~ E ~..EE u ~ L . ~n ~ ~ N

tdt CC 't

I lor

XMn.zr I"

.+ FROM REFUELING

WATEfL 510 RAGfIrt ~St'ANK. SEE OV/G ~ ~

5144 r E/CS

TO REFUELING WA'(ERSTORAGE TANK.SEEOv/G. 5144. E/7

ELSSV'W

'/'T H(5 DV/G. II3ADE Lsre'IOsJE FOR(J(EIIT42 ERND SUPERSEDES DVECV NO II Z.-5142 ICEV 16.

FDR RCVISON DCSCICPTCYI 5CKSC/YVIAYC RCVI SON RCCDRD

FDR TIRS DRARSNO

e» E e ~ Ee aewnr Er ee EernrreTIETrprc reeii Mnrra Iree «e e ~nn uweu,rev a e «r Ee rr e~~ Ee ~ ne rnewu ~Eee re nr f n EeaM ev~wire Sneer v aa ~ I~ Mrriiiorer~Ee nt wne ~~n a iin niner nn ennp ~

iraslAMA a svorlcarr 222CYNic cDE

DONA(J) C. COOKNUCLEAR FIJI(I

oarocnaa SIIOOCAO

F LOW D!AGRAMER(ACORE COOKINGtslS 0UNIT No

«JP.

CENTI

Iaaf

2-5 14 2-ZB.IY/E;rs.

~ W

~' I IS

WEEECEEI CICCIAIC OOITIA OCOTKY CD

oaoaovlY ~Iw Yoat .. /Frr~.. a.- = —...:(y'A»ir+ Nadir S'eeCE'»r4 '5

I

Page 339: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I

t'

Page 340: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

N H4 IA 1

%>(S-K 2 DISCHARCETo ATMOS,

54CXI. I (N' )54X)0.2 (N 'I)54XO 3 (N 3)SV'XD'4 (AA4)5$ 1 AY YOO Pst

~ OLA$$ ~ 4 4 ' pt$vrapttitvEcvacevs vrc ELI scavttoAAv crecteA 'vo

caae44$ vt\c VCAST tcoatv vra,vcloc OGAOP t vcve$ Atto ErattpS vite'l$'I ENAaoeare crvctto$ vat rees ptcLatoc$

4 c Sccaetto erereraAv cLEDScse vrlvc oAENT(ato$ vo Alto avcaato4$ vpc svateaeVLALAccA cAA ApvcA A IoeiverarvCLOLGP vra.vc

~tataSC EAAAL~ 5 4 vCite$ Avo NAAA4$'4 c E ~ E sceaeaoAAv crvcvc$ w» Atra

caaestc$ vpc rtAST ttoraaaAAV cao$ coVALVC

liat. SV lotDKTAt TOO PQf

IIIA.(2(DFZ)IOA (31(NO3)fDA 141 (NE4)

II I

5 r FC rIRV-NZ

vl4 UIITIALPORC( Y(NT r rtoM IMTROCIN

( P SUPPLY MANIFOLDSKE DYI(Ldlldde Pgtegl

!RV.122(NO2)IRv-132(HES)IRV M'2044)

He~~t

'ji~-iI — ACCUMULATDR

I (He I) TANK

()atf C 3 fkF3i 0- ODEK 6 4(N44)

TO RfACTOR COOLANTDRAW TANEC SKDDWFL5 1'37 A, LASS CC.CVI

4STILL 5

SMSI Ilfa ee ~

taSEreNLL

IPA-(20(N42)IDA 130(IFQ IIDA 140(N(41

I

Cav 313 (2) R 6 S I D U A L N K ATK X C I( A IJ G K $(5

DA

IIC)LCRQM CQMPQH'(NTCEVP.eet SYSTEM SEE E4't

DwO 5135ACCVSL Ers Oarow

(4CLS

ILA.I'21 (NOK)ILA-131(NO31ILA.141 (IF4)

I(A IZV (N'It)t(JQ ISO ( N 4 'Sl(IA tto (NFCI

L

IIQNt I

3'70 PRESSUR)IERREUEF. TANK.SE'K/ OWV 51'KBA, br»

Nc ()W17Kpd'tveOA(reset Ee(l

Etv eeo (vltt4$ (Li'el

5 TQ patssvatttaRELIEF TANK.SIEQwo 5$

2(VLDC'OD

R(O)t

IIIILVSIILCDSTIL(M

483'SV-OL

VrlSV-N4W SET loll.fAT 600PSlSTNio 4

SXICL!5SttoxatSLISC I

IRV'ltoIRV tto(NYZ)IRV 130(IF 3)

STNseSLECNPrsoSIICN

siresKFiSM

fRY lllIRV 121(N42)IRV 13$ (NO3)IRV'41(N(ll

v ISX-2(HSZ)~ Mt~ISX.3 (IF3)psst(NOISX.4 (H$4'1

311

r LC

IQ

IRVULO(MYC)TIO

SIIU.4SIIL) 5Sfltl ISt( C)'e

fav-Ilo IRY-320~at

14 e

RNCLW

SeetalI)'fo REACTOR COOLANT

SYSTEM Cotot(CS SEK I'tt ~t taeaaetacrStlo CLI

SIITOU7LOQP HOI

FJ:sv

Y(D C)yeeCRNO 879

FY(NKRNETSK,~Lao 454 F

3

ACCVEAISLAYONS

ket HDS

( .I

HOT Qt vVC La(E It

dt

sre.eO acato Ncetv (c Iprt aacAvte E

IF33

IflPX

REACH RODREQUIRED

RNI IS W

RNIISW

) falls

~ NIN(taretsw<Stt IOl

fSIN4ar ete ~

slNot QYQW

NN Sesod'

NO AOL Nalts

Nt (Les IL()E)(Q

RN ttf('10DICT(

,SIK

eev4$ $~ rte Saarat~Et'teerrteeev cre(eet

f(M41(

C4

tart Vse

7 Gee vi NIT(~Idx +.

30

53FIO(O'I XV ) g~$ < Ve'IRAI

5tt I 4'a aNEZ. (

I'YEHT~SIIQSLS

tNO 3

ILGE IIN(34IQ FROI V CLt ML y

st(CFCt vtt ACC~REI Q TAaIKIL

SIICI'LS LLC)V

F DRAQ(Stt(eOW

LQO('O4

RNltttgd

NIAQER3(thNf5 RN(ts

REACH RQDREQUIRED

LQOP Nlt

L(OP Nt3

ala

(To patssvRIIKR IMO 31'IU'Q

Vttfa (QNTAINMIIITSPRA'Y NEADER. VIACPN.OO S(C OPE. OSOO fts

hco TO CNIMICALY(XUME(QNTROL SYSTEMNQL(NUD TANKS. SEKOWC 5132aasfd

IRY.III

5

IMQ-3ZZ

Rcots»

~. „„f»8 TO UIPIt ((E(TAINVENTSPRA'( Jt(AQIIL VIA

Rst(Sta(UEF TANK 'SEKOWC5128 E(6

ro C FROM OTHE(IACCUMULATOR TANKS

d TO QJTTY INJECTION

RHR LOOPS NttK 3 CQR COO(DOWN

O'RAIN CSN SI Stt Oa( Sate Cats

t(5'tst fa)N Slrot K

IAZCIKNFLSEE QEA$I 51 ()PCS~

eLE I

511)l ttt g.

q NV)I (

'(g"4)3,Sf. 113

2

5'NR

IVlP MINCLQYI LINE

PUMP SUCJION. 'I'EK

PWO SI424K(D2'10 CREEL C VOLVMECQNTRQL SYSTEM FORPUNIC ICATIQN. SKEOWC 51'29, F(2

SIIOILIrrr

~Ae aleCLC CL)

ACCUMULATOR FRL LoaSEE DWC 5142.5!Q

f~ teaStlOILC

6Ve

di RNV7Iav r)7

IMO.326

St ISCOW t(40 3'24 A,4as

F DRAINSIICOE

6'OW

MEAD SAFETYDMECTKH Kl N(tf LECS(REAC'toa COOLANTSYSTEM). SEK DWO.

CPN 581 VENT

4 FROM SAFETYI(ODNQ IN)ECTION PUMP'5'

S(E OVSQ 5142DSIS

ite)51155

rst Qw~4

I ILDOODO

IMO tts

8OE~

51157 L'I5(2da fldaN(6 ~ SI(STLS

Stlsdt'ILDW N'EAO SAFETYR(IICTIQN TO NQT LICS (D

(RKACTO$( COOLANT SII5QLSSY St E M3 SEE QWCSIZQ, F(5, Nls lOOP IFS

SI a57($IMO I'20 St(tot

IM043$4RNISV

RNNLt

Va'bx

301

QL

RNIISWRNRLW L

IIsx

'c,30 2

d'NR

PVMD MOLFLOW UHK

ELCQSV'L.

4V&1st - «™~I(M.321stlsZS s(TAT lro tllSY IO) t(M )N

lo PRKSSURIIKRIJLIEF TANK.SEEOSC SIZSA:I/6

~ CV

4e

ELSOW CLOWELKMEHT lfYPICAL)

«(r REFUKUHOWATER RETVI(NSIE QWC 5'IS

~D 4 as

'S'EE NCIK'A (Vt14'CROM LOOPNtt NQT tt(t IORCOQLtOWN SEEQwo 512a K(6

FIHC SCMCCN

, ~

LOOP N$4 f< tttr tssE

LOOP HtlVVIIV

ISEMIMQ-3$5 SNSN ~~ tStlldl

4$ 'ttNT~te IIS 5 NO 9

CON49ra

~ aAREA()$ $(OPEII(JRIO

IOI(13W~(2) ats(QUAL HEATREMOVAL PUMPS30(N) CIM 35(JF t TDN (KSIKN

%Oft TC((ECOLll80 RP)t 4(O N.P.t(Ar.C(SC)L Fttssuti 7$5 Pslrt

/~ WFROM5ACETYI( C(30 5 g DUECTIQNIUM'O'N'.NCOOISSURK(QUA(IIINQ SttstN~~ ttt ~ SN 8$ 9LINK SEE (NCC Sttsafls

($ 'H 47j SIVAM.CIM

N $8QM REFUELS'Ntlta S)QIAQE.)INKSIE QNQ 5144 65

JSQOCPAI 5((t

ICM lt9~Stt HOTK 'A'4

~CAIL+tart EDCNAHH

gaCN RQO REOD)

)t'44(AL RAlta TQ C FAQM toM(CN. StAL MEAT I(MA+No(R(SQIILIID SY I(WP I(ANUIAC)SIE QYKL5135A,CIQ (IYP)

OtalYNNIOSC

To'E VALYREHCLOSURK

2'X3'SV IQSW, SV IQSKttt AT 35PSIC

RNGGSN 4-FROM E VALVEMNelct INCLDSVRK

ICM 305 ttICM 3Ãr Pvststt

(RIACH.atoo(XJD)

~lt

I.C,Pltttte((RIACNROO t(FS)

6'KNTE St&'4 LC

8SlttJIC

4 N COS

4512)CJ/6

M NESS W

(CARS L(CI((NFINKscattN

R NNCeeqSVE'4l

PINICK AtARMELCCS(ls

YEN'f 77OO CPMCts(.46Xt A(4 I MNEME

RNIO IN (REA(H RQQ

AEO D)

to(.'I

Vtvs

5 I

~PSSC

I'NEOtwCaSSO(t

Stoo CPM

ISOLAtION

I PIPlt'2OQCPMS(QPE

MQ'IQR LOCITED4(slot INcLQSUAE~I

IPX.)05 'I

(at NRNOI too 'LO yt

h'ILAILSSI' Is(Q)-

IP)IOat

< CA'IPKDDRAINS

h'TESTCONN.

NO 28'I'ALVE'mn 'sttId

4 '0

SN'4'ECIRCULATIONSUMPVNoat LAP4C

Egttta Ctiv Pepecc 'c sacr Ctt

6'UMP SEAL

IXV(SC((IIP)litt IO(IITVV

TO (QNTAINMINT)rt'I

~NEWS Eoow(R(ACN ROO

5$ 'RAY 5YSTEM SEEDWC 5144,F(9

ENCLOSURt DWC 5123A,Q(tfACN Roo Rtlroat

ENCLOSURE TK B7ENCLOSURE TK do

Etcvccvvec caeANOParavL Cttrt(COCOTo LavcN Ae Y(tRVNC

sl44CNcc s(N+tcf VLe(S EEEAClte eeeeeteo(IEN CEDY4NO GCESU

two(8 (RKAca R(o atob

LTCceccaAAva(44 Naettp

Lcvca NcrcN eae arvvst(e NLE ot E 'W YALVIE VALVE

o 51254 3/9 ~

C 0 K I F I

ACTOR4(SIDE REACT0$( QUIS QE R

ca c Etc ~cc C

GIN('.RAL NOTES

LEGEND~ MAIN CLDWI

AVÃILIAR'Y FLOW

fOR VALVE INSTRUMENTSAM)EL(NB /PE MATERIAL

g)V(PD(ENT SEISMICCLA55 j EXCEPT Jove DKZYK(2

(P BY WESTINCI(OUSE

ALLIOMFHINTtAL$SSSUPPLISD er 9 EXCEPTAS NQTK(r

VA(vd INTKRIDCKED WITH$$EACT()R (IQOLANF SY5)%ldPl)ESKVRK SISNAL (4 A/0

5 SIERYURECARD

Al Available Onerture Card

Pat(tat O(54CHSIYIOat

CSCN CoaAPONCNT IOCNYIISCA~N«VDAQRR IO'4: VNLCSOOYNC+wesa HO'Yto

ele Parve ~ tcc ervetf p $4 tracetaeere etta Nese Eepa Ar4 atw Neeeerr Se 4 4 et te e eweae e ~we ~ pet 44. r evc «w te~tepee eervee te tp Aee arete$4 eeae mme e ee 4( ~ eeae Etv

ee ee seve eaeveeA et~carel ae 4 seve Peeve ptt~

Nso(ANA 4 EececCAN (ttctloc caDONAU) C. COOK

NUCLEAR P(ANTNCSNNO ~o(NOAE

FLOW DIAGRAMQAERGLCORE COO UNGI()S(

UNIT bto 2

DaNa 3 5143 354 te

P DVAPV pCAW(s Fpa e

vt

EN(NNJN IICCYCEC tov(S I(CIS(t COSEC

t OSblovly ICC VOCE

Yeiao ceres ttADc atvacv e(atlVer r 4 AeeO $VtCE(5COCC (eteLE.t SDOS, Ntv. Ct

N t SCT VlIotcetetscAYECN NLENS

t CNLY '(OC(KC VALVE NVVsfNsAFPCAN ON YNIS CEISNSSR 5ffsftARAYX VSLVC (O(NYEFICATKNIJSY FON COESVS(XNT OC5ICN(VCIII NVVSCMS.

teYAC NEN(otMS VO(SF(CO FCNONLNOSC t(st AS FO(AON5:

Ysc Ne CNEscpv(XPNAPFCANS As:,NSNCON

XPESYNISEfNT Moor vltvf VSNKNe 5 Noy ssaoaEN CN.OE(SNvsc(sffVALVE IO(NYIFICSYEON LISTICCNIVCO CY AOOENC TOPEYYCJVCNF

ICSES(N'(tt

5INCLt SSEASCVIFON C(XSLC SCEAtt'VOIPFIIECAEC

7TQR HKtoraH stltos 5t

4F tfvNKHtf((NDrccTNS

~ 3 /t tr 35

toit RCVISOH C(OFTXSWI sfdsftSLSIAIK RIVI5NN MfCCOO

toa TIC5 CNlvvso

'

4

'I ~

,900 3090183- l.Q '.'

Page 341: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

/

1

yP-P

I

4

Page 342: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

C I 8 I F I . M 'N'r

GENERAL:NOTES231'Eo

PIOINCPX

I~ s

CTSIII 2 CNICTSIII-r TEIIPDILRRV PIPING

foc Steat.vs oa>LV

INSIDE REACTOR CONTAINMENT OUTSIDE REACTOR CONTAINMENTLta>GD~ MAIN FLOW

AUXILIARY FLOW

9PP IS-Z,

24 MANHOLE / VENT ISPAACO TYPE I)ISASPRAY NOZZLES ~ ~

IIIISLroluoZZIES- IFDR REF.SEE DNG542TA)

PER O'EADER) /~1Frb'ISt4''rssltv s.CCRC r

gxoGFM ctstssrIF

$

I)L~~+M

Lro.«t Ctprotat

10

~ 4r l)RYP>sas

Os«I rs

! I t>a tt'ttt taps~ 4 ~te a st 4 ta>S Oael

CI~

'agcrtstsvg ELEV.C40'l'wS

FOR VALVE,INSTRVMCNTISAMPIIIC> Plot LIATIICALAKOOTHER SYNSotb NOT EEPIAVCDOSI THIS DWU.1 AND FOR MARK~IVVDER CobtS >SEE DISC«rtsSIOSC IZP OIODL.

ALL EaVIFIIEN1 ./orb PIPDK4SQSMIC CLASS Ig,XCEPT A5 NOTED

OW SY WfSTINGHOUSE

REFUEuus VATES STORACETANK FRIEZE PROTECTID

DRAINS FROM SFIIAYA00ITIVETAHKs To sPRAY AUCITIYETAHE ROOM SISSP SIST H/I

sI FISULAIKIN

Cltsltr~ NS.

*Io OYERFLOW /10 1st

DETAIL'M-I'PECIAL

PIPING FOR TESTING

l>t1st

~tt s)s

t rs'tts pa>FDR BOTH

CCocerw tasvasoas'tspot a

osssst«4 tesvaasp~ ats

~ aa a2«we saewattlaa at SSCv stat«it

SV ttota fLOSCrsstlC 245 E CTS PX IPX I~SWLIS

244 W CTS SLW tJ

214WCTSSSI E IIINR

COT'~SO'Il E'lsHA

~

~

2'ENT )Pgi.l SISCC

OTHER TIIT

a ~ PIPING AFTEIS TEST

I/R'TE>ottarsY CSsNN ToCttet 4 COIITASSIBCT FKOII SISSP

SEE Orts. 5427 A

DETAIL M 5SPECIAL PPFIIG FOR TESTING

6'

rt/4

3r<nf) Raatt~

OP '25 IT(t) TYPICALSPRAY NOZZLES FOR

BOTHYISPAAEO TYPE lti)A= 3

TOTAL 150 NOZZLESPER 6'fADER)

8'>N4

UPPER COMPARTMENT

ICTSVSE

Sssast

CPN.SO

CtsstlCCCSISOC

'earoftING IFIIIEO'Iooact IAHK

~tat t>Casa«DECSCC Saass cts45'-0 Dlt't Sar 3 HICK

CCP. 410,000 ttlt5.ITK 2)tt t

.5C s

II)CODITAJ:LDINT SFEAY Vclr

Crtl.stsf

~

ass

zTO 440 fRON CSCCSt RVS CO la'lt5 SC SO>PLVLSLOER, SSS 0>ICISSIS

«ease «Gt~ Fto«'4'OPC

bacsr CR«spotssec aes.tts

Ctslttv

ts5

erst tsv N~ 6/S,F/9,G/OFLOWS SHOWN ARE REIXXED

BY 2+SGFM WHEN NCOHEDUGTORS ARK IN SERVICE

C

LF f3cpu 54 IC Oslutt

~goto RtrIID RING HEADERS CtSstlSEKSK'A-9'E ISW

p IlrocpM TOE FROM KD55ENTIAL SERVICEWATER 5VPPLY HEAPKR5EE PWG. 5H3, SJ4, Cj4

6 Lc.

lI Cat att

)pCPN.55 zto

0Ctssttt

0 ~ NOTEIOR TEST REMOVE VALVE

O P E, IIISERT TEST PIECEILCI/O st ~~ SEK DETAIL'M-IP

6'DIDIG asaaal>s-s >a''s

0 CFSIIIELOWER COMPARTMENT I CtsstiX

tt4Cra0 cL.I 40'o'ssr

ILC@o (gal

IC MAKHot't TSDC Wtt RtfftSIIICSSO>Sot Spat44CN coaa>IODPENt socNTDFK4tgwsaseocR td t wLcosorNCRasvsss slorco,

17 HfCFSDI>t

Cttstac II'O

PQ'tsstsC CrsstsvREACH ROO REaUIREDISX «e C>DL ts>LL Lp 1 ptaaveaap cowL

1 st gawp aaaaasss ass a>ossa« s>4~seat a>et waLo st« t>OL cLLLLs DL«taro>as>Lett tlt

~pep« tsstaea ttls esaaotas tp pea«>pear taesao aaLVL OILLataarl leIaesaeeta t>L >Less «Ls 444>t NtLotto pa>CStoa tte«ca«La Its apt>start>a>ILt>L111 S>ca>est Ltttaost 1st aaaata4 Pa«Pa aae«stat carato spats>%

CONNECTION

2'To UurfNt'I TANK

fat SV '.UT To ATMosSIT AT 10 PSI

REACNI'AOO

Los BEDUIAED

FILLING

90

tEELCI/I

S.'Ps

Crust t4

200 GPM/3200 GPM IPX

'It otrritf LISP't Note'6 G2) 113Ro IMI f Pvaaot

CrSsttv~ fII I)'I21l

CFS stir

tcf111

220Crtstsr

ITtlo ~ 6 LE.D/..

~COD)''L cls 0 Iotbr >+s EL CSE~C II IUN ~

Ost EL rs)3-0 LOLOSat Cstaafo

Cttsts qtt Its'II

Ctuso ~EI

20'LCSCLCVIFI

R.EST~ ovI'C4DN N0181>0$ OPC SISUC VNPOVC

FOR IPlltat 4N0 SVSCRlfotsowC PI Sstt CCV. Ib

CtSSLLPCO>Dr,

OCSOCS.

t.

r cttto

rst R' ~

~ 1

I

I

I

I

I Lc"'.tspegt 12 Nstaoccu

SCE DPFC OSN4 >/4

1st V1Io Ntstscstsost Nasa>st>DS

IRCV-I'Maxcwp FROM

SCRIC ACID SLENDER.SEE DNFL 5129A.M/6

I. CNLVRstsox vALYE NVNSERSAFFEAR CN ttcs Ostarssr«cccCtfstttatc vacvc ICELTrscatsotCssr FOR EOLKVALCNTOESICNINCRI IILINCERS,

g.'rac'MAIOERS Sscctflco Feltotttrtto VSC 45 fottorsl

rac NlI E.ttttsc2prappcaRS 45: Nsroor

totttttoksfrr Hoor VNVE IISRCstrs Nor Sstottr ON cstarstcltctvaLvE Iocstrlft atlON NsrlOERIVCO Ct 400DNC to~TILstcstr MJLLCER;fttt SINCLE~ftttCOLELE Srsast"~

2'ROII REACTORCOOLANT DRAIN PUIIPsSEE ONCLSII)a,r Z'to ~~s«

>apt SVC ta>VIL

SI IDISPCCtsoas0 CL.'I

0 g Cttur

I// 2)2'FRUM SPtufe - FUEL PIT PVYSTCM

F VACUUMLLdtcas41~IF,OOO C FN

SSLX,

IVIIKI ~4NDO4

P I100

\

44-(TFRMINATIONI

Ctsa>5

~FVIHTIMO.202

SEE DWG 51) fscrlI

-L~PIPE TVNNEL

IO~ ~492'rss s4

ICK04

crslol/teats

2 ZCVIRCVLATKHI LSIEfAOM CAFKIY INJECTKVIPUMPS 5'tf, DWG 5I42,M/5

VALVES To 0'JCIILRCCUP ttlgose„rcrst IIR.CRG.

"«iLCIE&3; NtlIMU204 ~h'a

Osteal

Fau RUUMTYPICAL FOC(ll)SPEAT NOZZLE w

MISS ID ~ BARRIER

IMLC

FNQSIIECTSNSZ'ZST LINE

2)2'at~4'ta

s. FF 29 AsvIKO RIGOR t 0ltustt

~I

tfCts l2OC

I'RAINCtssss

To SS,FETY INSECTIONPUMPs. 5EE Dwo, .Sr42PLI/b(Isoo CePM MAX.)~ 08 REFUELING, WATERRKTURN. SEE OWG SISS Cttf~14. TOEMECGENCV GOCECOULNIG SFSIEM (RNR)SCE DWG 5143 H/6TO CistaRGHIG PUMPS(1,100 GPM MAX)SEE DWG SIZSP MI5~ IF)

5 TO REFUELING WATERPURIFICATION PUMP ISEE OWG.St36.C>/9 ~

epAAY ADIXTIVETANKI04'ba x rosclsTEUGNT

IFI 4FPOO GALS.f[KA)

Fot HSCROIRN 514105 tt\'IVCCSI ctcocss fco )sat vr

REACH 200 RCG'0

CraorCrsttfsr«L '1

l[L45 S ~

LC~CIDN

3

c ftsu ECKtawslIKTsfzav HEATIECPSIAKCEC EDSEE TAIS olo.bsr4

tat

FOR HEVISIOH OCSOCPrtf ISEFAXIIE CEYI5KHI IIECOO

FOI TNC ORACVIC

BL 5rsl 0"

(hYP

KL. IscsTIO'I02

/3'sfoaY pvsspTEST Lltlt.

FRICTIONFLOFI TAPS

r~ W PPr ~ GPr

I~ APICAL FORtlo) $PAAY KORE K

Irs) NUIItf5Pttt CUR

4

Y

ILIOIl0pSfsl5100CPM 3200 CPM

IVLVtlI

m >«wt e «a >pep« ep p'. 'pats«tr'atst or stets sat«tc tsep. >p e steppp ta\aae apa e e pt p p pla wp

ta tap% p ppo p p ptL ee wa p~pee wawaev aa pe pep >war~«sap steep p «4 a lt trtast tsar wp>VR pww >pep«14 at sac> esp«aw4 p vppsww pae aww

paO 212

Pl IIOPILI'.II/ItoLKTot

C4tnctID+OR Soot

2~ 192'6,000

0 PM

ItfSEALI'sallattc

'pe ae «p staaa>a

IP

tCIOIOOW INOLSNA ~ stsoocAN ctvotsoc

DONALD C. COOKNVOLEAR PLAHf~I14CP2205CP

4s 1L. a DRR>lplpp R a

a~Pa«Perp)RWST. FREKTC PROTCCTIVISIe'EEtso'3 Dwc.sc.s-sl Ltc~ 6 0

GPMIIPCLDS

~

FROM RECIRCULATION SUMP.SEE DW4 5243DF/D I,~Q 12 f/ CINICI~

~a DILC O>epv

PCLCCNOP~'LCttsttt4

LSLNLP- Sr

M Zttomtsl~r

FLOVJ . DIAGRAM .CONTAINMENT 5PRAY

ON) Y ND2

0 FROMwCase>e 4rl«LN ROO 0

R«OLSRSO sa>52SDW3

IZCACst ROOsccatavIRCO ~fTTP.. CUNTAINIIENT

x SPRAY HEAT)EXCHANGER Yf

sec Tule Dwep/5

l0'o>PCO CLst PVL«ea NDL\ IPI

4 IO Itt>asa«lCCSDOIV

REAcH ~)2 IDE FROM couus ATCoo REQVIRED Mg K SEAL HEAT EICNANCER

SEE os 5135A,K/5 (TYPICAL)Q., 573'

4'>»toCoaw. I s

PP SW~0 IMOr>MIF

BEACH ROD 0 ssasse~ Lo0 Pv«4 Lo

CISO'1s'EICH Roo RFOO~ A„t

OOC>ll 'foec TONssoo Frll Coo ss ~Naz Fvsastascrasst ttcssvtac ssfslo.rtol Ssttsts sat to.

geo '- 2 5[A-29 ~

5123,IVV(2 lll114 PILG

et.acu fooRIG'ofFAN POOMTYPICAL FORfit)SPRAY NOZZLES

SKETCHA.9'CNGMATICAARC f OF LOWER

COMPARTMENT SPRAY ufAOERS

raf 40, 's)t'LDSN

Cowe Il

IIZIN

4CDPPO~ F ost

~ I4>P ~st>. V>4~~H sate 4 ~4«lt ~ 1>. rW

IRC>ssocsatstr Or LDCSTCRS ws~fssaoP Irulo)tsssEIDIMQVIEISQCtpcaot TLNSa IICII CC I

SIAPERTURE.

CARD

iso Available OnAperture Card

:2.41.,

I'.

s',90.03090 18 3. QQ..r > ra

~ oCt

~ %.

Page 343: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Ooj'Cr

. "eI ~

Page 344: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

' I I t ~ ~ ~

~ ~

~ I%P

~ %4 rA

l i 1 l l 1

~ ~

I ~

0 ' ~

1 1 I 1 1 I I

~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~

, ~

~ re

~ r

~ ~ b ~I I

Il ~eIIIII! ) l I PppA

KKECXM~Wr k

~ r ~ ~ ~ ~j ~ k iI I l

~ ~ ~ ri

~un aa~ ~ ~ ~ ~

~ 1

~ r

Page 345: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

1

I

a

Page 346: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ p

89P(9-E YIN 2IO

IVDIIT(fYR)f R Zset

C I

(SO) FAII CCCLEA IPCTS IN PL'ENUtf(OCATCD AROUND COIITAIIILIENT

~ke

ot

Ce

0

CPS116~g

IQ

~~IOYARRCAV 1 qeh

TOFltl CCCILCRCetktt READER~

ca ce E DIVASOIIAJT

~hC'A2

I

GLYCOL EXP~

~efteltVtkIO

RDV

NI

he h

J I K I

Craft(RAL ND15$

'EGEtlo

ssxamm ETNYLEtC 01YCOL

AIR

ALPIUARYPIPING

SE(t(TIE'I',1

II

IOR VALVE,CISTRUMCI1TSALIPLING 4PC MllLRIALAND CITMCA SYLISOLS IeojEXPLAIIIEDOtt YMTS OVCAkND FOR IAARR teULAEeCR.CODCS, SCC OWCe GK54

I'l.tetr f,RZtr'I

'ISO- LLVS(pzoraOPIIR'lko

cpsllz+I

CPSII6~1KRl41 SIONCACI IteCl I'leetuze'1

2

4

et co '-CPSU 'I'LP.241. I'OYPcAL) CAITKR

4 i I

(BYPICII,)5 IIR

B I

III

I I le kvRI63.1 TNRU RI63.3O

TTP) SEK NOTE Z~I(1551 TMRU Rl(e5 30

RIFVC Iltfto RIFVC SOOVFDeot Ct Q~C Chvfarre

Lett IIC COVOL

~ gr'IIlllrlI

I

t

0

VSD'301 360 t YSO 3OI 360~I

RINVtCPLI

LI~ tttLAetaee ~ ee ~ e tfteivo 4 ~ e

I /I

I

I

1 I I C

~.ROIS j I tg Tgr(gj I I ELE(TEK(EeCOHDCHSLTC

(TYPCAO i I ( (TYPI Ao

I

I

I

I

,I

I

I

VDS

le

4 el

I I

leITEZIJAL I

RVrl4TMRURYAN 30(v\voek tteeavtDP

I( +

voce Ce,oav 4vpet c tehvelLPA DD Olw lt

Ih'DRLttMDZ.St 56131k. Jll,etft.LIIe IT

'VTI'ZOITMCUZGORI664IILRU RISC SO

ITI Icavoaa ceeeavea)fAVtoettee ieeLAtFaore ett tOCVvetpe

VPAIet(

AR aSTRIMTION Ic%AOER 20 DLKTSI(KAIED ARONIDta COtIOENSER

AL Pest Res 'Tehe Lethe(R, Ye DeFTS \'YJTto AIDLeeO

ett ttPIDINttf

~7 IVytetat)

fAII (POLER ttfkfetFROM ICL DDHOCHSKRPL'E NUM

AFT PAL(PcfR

OME- \(2) FL(NR OE fCO

(teceCAL) O'Eklblt SC.IK

e'es vTR

31 SI ll PH'E

(It'(IMSV-I~ CPS'ZSIeeSEE MOlt gDIS

RtllP2'Z-RICA1 RTLO 2-,

~I V

)~I TVEUTRt36

zg VPK Rl4

'LRZISCOLSDFMSER Slts=LCOOLILNE

If2'(TYP.)CIZI 1'THCU~(25) ftooz sLLB

COO(RIG UNllS(TYIf czzsITNEUzk I1lOPERATIICV FLOOR

EL.o's'2 7Yz

I"ZLIIRRUaef

tfl flvPSTR

I VPR155

Ct c«'W'FASf WESTINCNOUSK

DC TCLAD SCNSORSQR.ICA~VT~CNO

]TR Sth.vt~tI," VIA 111 Vek 115

IL STRAPPED ID tt'DohI I ''fAIOS VIA 2N.I 4, ~ 4 ~ STILL PEDTDVALL

VRV.IS

rzRrtt Nt 4 UDCATICtt6'EE LVA TCIGIIOUSCOVICLIIS5452

IV(ST61Toit LK Cot(DENSER DRAINSSt 6 DWO. ~ St24,afZ [e'4. ~ ~ 4 ~ ~ e SCE DN(LIISE45'LI. f...l

RSOD

TO Tvvo 40 PT DRCDetstttssk'RSfi-ft) TLOOR 55kbCtl PAteEI, sV COOL IL1(S IJ IJTT

g'fPl CAL)

CCIIOINLCNTEND0RCRAIR WAILPICC

VFeL

IlSl

Z

20'0

0

5

Sf0

ALLEQLIPA(ENT YALYES ANPCISTRIMr(ENTATIDV OYWasllNSNOUSE ICILESSOTUERVefSE NOTED

2Ct

z

20LJ

tf0Uoe

~ 159 7NOT SVQw

ALL PIPIILS C 21 EXCEPT.

As NoeEP

ALL E(e(Irs(ENT SEISMIC' .CLASS)I EXCEPT AS tloTEP

HZ' KIZ.EnGLYCOL PIPING

END WALL ONLY.

LIIYF"-LD/S,CIS,OtfGLYCOL CONIIECTIONS FDFL

ICK BASKET WATER AOO(TIONKCVIPNENT SE'E PNY .SFOTAeeeee ~ A,k A,O:r 5'5

4Pro root CLASPER(D «Stteo

~A(crt coeeeetcteoees Tlecl'Llstceetoceet tktteeDs To Aefo~ KLLPJ(5 lct fektt te(DT eeetvc

Fell C. Lc (AADLI VtefffeAOOttkevj feet 1 st soeeeeoccv trtta1D rheo eetDLVDCS tee( s((kate Ace vhaett CLDLCD VALVCot FtltoesYDAeto eaeteM PCS tee ceeeto ftveltDt CAPeef Ilkee IAPeetettt LOLCDVALVEP"LL UAet CLA55 1 C 3 vLvt5 eeao

Dtaevs Trt 1st DOVLIOARYtkttetof To eave evtauott Teetfeeat LNteeeeie Dkhto vALvt

0

Rl'5 ~ ee l (A GLYCOLSUPPLY lCDUGLYCCLCHILMRS55+ ON(h slk(reUIsek)9

ttoettleDA ~R201 VPX

11

LIOT EeYOW

VfI

I VENT

VTIIO

VCR.IO

I:C

em..El Cefr4 9

A.J VCRVI (4'113\

uf uAT(51CDCR 5 Vf

s

P R 294r DR*tet

(TEST COOLR

MOTE. THIS DYJ

FOR uNrT'2 MD ~PCR~D(Sore I ~aceICFI CIY OW

D

NIN(e DP ttkt(D vkIDCNflfltkteoN Noeeotets

L ONLY Ikttotec'ALVE Note k ERSAPPEAR Det AIHIS DRIWLNC. SCCSEPARATE VILVC IOCNTIFICATICNLIST FOR (DLNVALCNfDES ICNINCR) NUIACERs. D

Z Tk» IIINSCRS NODtft(D fORDRAWPeo VSC AS fOLLOwS:

TAP Nl ' Nsw veos wAPPCkttS AS; Nsweosw

SPISTRUN(NT Rot/f VktVC NARKNf5 NDT SHOWN DN DRIWPeCISCCvkLYE ID(etflflckttDN,USTIDCRIVED DY ADDDIC TDINsTRteee(NT NIINs(R:

FCR SINCLC IAPIASCVIfttt CIIILCOAPLRSCVIILPSIIICAlD

vlcoaecIRII

21RSS

NOT ISYow

ATELYCONN, vf1R.ISSFREON

VCR 2Oft

V IRII9

CLCCLV4'~i

VT5SURE 31 P DRAeN~

at 295LJ

L TEST CONN.,R152.v f~mST CONN RIS3IG TNctpcf peek ret DES cvkteov Foz >

crol ccfapovcvT eoteettpeckfeoefekpeoc R es t tpettss cnccevs( Ntc,C TO Mklet QIYCOL P(RAPS

SEE Oui�'5146aM/Sek/IS.

I DRkeel

fRZO(I f I?-Ff 25

R SOS

rRill '

tact cl AeeaoetoCL

I~ Er ~ RtleOVC steeseNCr

Deco ( VeeLVF eentRVALSfDR RCVISCN DCSCRIPMN SCE

SO%RITE REVISOR RECORD'ORTICS DRkteUICClol

)'/ILr

/ VrI)ttva m~ c M eveace er ac Arpvea

teeeeec eave eeeeec eea. Ava eDva pea~pvcca eac c c eae el N erhaevca aa

~eet ae aaa eee~evcva atwwee ea ere eeeca aaheeepc eveeea eeveee er Da Ael eeehg tar

~ee hase~reeeet cv c llea ~ pea «erect«RZDB

Q azr»RZI0~

vPI.. 158If

VPII D

INDeAHA ~ looeoCAN CLCCltetC CAR

DONAUI C. COOKNUCLGUIftktff

FLOW DIAGRAMICE CONDENSERREFRIGERATION

4 5 SCQV(D CAPVPI156

RZCLO

vPI151

Netfvtof 5PLA'TK81 ~ 64ZPO2-3146B-etb

(Z)FLOOR COOLIIJ6 PtflAPSloo GUN( z04PT'ToxZOICW 845(S ROIARIAXDISCI(ff(e'IGPRESS I'15pszttPP Esb (SC.ID)

Q.KF Ipc eCCai K ~S.WAY YtiertRAYUelgStcseVALVC

fe 'eN ~

eeh eK

Qkclttt Ioeetk ltetYKC toetf.AY got YDAK ~ r

AN(RKAA1 DAOAOV

SIPERVURE

CARD

re'

so Available Onperture Card

hh ~ ~pre

D ~ I P D I N

gpo) 090].85-.I,r L ~ eea ek vA h r, ~ 0 *re ~ ~

Il I~ V

Page 347: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

)'I ~ok-

4

1

I

0'

Page 348: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

~ ~ ~

~ ~

~ ~

~ ~ ~kKL

: %PA

4D

N

~ ~

~ 4 ~

~ '

0\

~ ~

~ i '

~ ~

~ ~~ i '

~ ~

~ ~

~ ge) ~

v I~ ~ < t

%F~KQLX~~~

~ ~

~ ~

~ '

- l)T

0 0k J k

a&ter ~ CP

~i

i Rhh+

4bCRL

JKh%P

</noir i

~a

~ ~ ~ ~ ~

~ ) ~E5%88~ ~ ~

Page 349: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

tS

P'

Page 350: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Ar

A I B I

6DIQ.Z

I D

I VCNT TO ATMOS. ~'ifrwv«A Aa 4aovt J aacaaaa aalV 5 lava av\

5IGiNT GIASSVGG 3IO

Overt

Sv 34.Sci Ar 30PSIC

KIDANSICN TANKITI( )C)(3 CALlS.c, I( C CAP

cwaic» 15taa ccxFFDobtoat ttrcLsotbt

I VCNTT L1405

aii DHI)

IVC~» aaait

I OctaxcRAUKEO WarcccS& Ovia al atia AAfr ovialai

St. EIcvnrtxa»cv ~C

0» ILCV

a54~i/~ go raw y r~ ~a taSV

)c Dtwtcaaaccco Wa vta TclIarvacaf itk tx

3 TO RETVIH NKADUL 3 FIDM KSSKNTtALSIKOaaossli L SCVc.c F/1 SKIVI(K Warilt.btt

OaSSSn)a 3\Yt 2>j)

t SDO,AJ ~

0

h

TO ATMCS.

I

ICONDENSER

I

FILTERDRY KR~ vciDtv 051i

KTPANsltrtVALVEitVCli

LKVAPORATOR TI'5 I2

YDI vvc

317 lll

FL. CL.C 50& ~bl I D»ia)H

r vcvriiIC taaaavta 50vaaaa tata I+

vao .1 f vM

)0

I E v'

DHICSH

PI'5l')

FoxccNr.sct5iltrCH'I5 rc acta4 Harl

'ltt TJS wor\

I

IFAN

IIIa» xtlca

w»c

I

/2) HVNZEKKPACEEECS'WC-CC~

DHILW> r~\ij

9 TO(33CNTIAL, I KK..SCRVICCWATCR3(C OMG.2StO,sf aC Ift/LV

~H1R CDHT. SKESKETCH E S"

» )0CSSCNTIALI«VKCWSTCR .s(I ovc5KN),sc-s.),a/2

Vol

vr13is rt

31C

VTX

315

DtiiLAH Yare'a vMO i«Y»Daa t aarSSaat/I

lli' tc» 55acvrtk5CCJCO Mite5llDANSOCSCK Aoi "/I

VRVt32Iw/

tvc't ODAI Iccorvaalaact »,ltact Dva

I Lr I P' G

I

2

K

m ntKS~ ~4 0

DHICS

I'NAIICKbOTTLEtTK 53)

S.C )I

Vrcart

VPI3

L I M I H0'ENECAL NOTES

LEGENDAitvat tat

a» atatraattaarr

~SSDLCOCOCAA555tattattJV COAJLCDOVSlK.ISIDca»oacf Iarcvaa VD AJD DANccoca raa tiacr iotrtaliC

cfotc00accaaa SvttariaDCOAIVL rite ISItcaaoaav tctatta 10 Ait0 I»cavort rica fattfVOLVALVCaoaao VAVt

vENT To ATMospHcREFOE VALVEINSTRUMENT,

SANPUNG PIPjMATERIALMID OTHER SYMSOLS, NOTEXPLAINED OH TNI5 OV(G„AND IDE NACC Nt CODES,s'EE DNG. R.Slobs't(acQ-MANIIILYcttrtc otNPEK

g-NORMALLY OPEN

g-NORMALLY CLCSEO

MOTOR OPKRATPOVOLUME DAMPER

KACC CCAFT DAMPERCLASSAAHIE Oarv3PEIL

- CHIORIOIC OCTCGTORE

L

SENSOR

EDUCOItrrG FILTER,

MCOiVM EFFICIENTF ILTCO 5

ABSOLUTE FILTER

EZE)a)LSLGH GCHK (TK 74)SV 54. Ls ItAL.)SKT AT 30 PSlC 3.C

SKANT G'LASSVGG 52O

DESI')2 PRESSURE SQ PSIGKSIGB TKM? GR) F"

Vc'Dw»taavtto wtta~v»av Mt ~ cava an

T-vaaa» nt fccot

G CAP

I VCVTTO tDVO

32D

DWILCta ta»TI'RAOI

K-cworsCars)ntr

rtaactswta

Ow)35 4q'Tlaaota

»ca VJD Data ccrc

FILTER VRYORiiVSIDt

V5054t

XPONSICH VALVE~

vav 533

3 TC RKTVINHKADLI5'KK DWVEbsxatttcra'2 >F

3'ROM ESSENTIALSERVICE WATER. SKKOW(absttSASKTI'I f/2

@TO ATHOS.

II

DH ~l~ Ir i

CHARCOAL FILTERr ~ COHOKNSER

CHILEED WATER COIL

Ittvtaaaataa awa»a vtal~t ——-r+—----~ ~

,II

rra..I L- 5 VC Carr WvrI

4EICCTRICJhUSX COILHLLTCR 2 SCICCIS)(YV KAE)t STACt4CONTROL OPP

gg RtFE)GKEANT L)ta»TKMPORAYVRR

CC.TR ESTUIS) Asc EK(i&VISTvt LEAT tttfta DLSvavartcv~no tat» aacacacsvr otvrifaClitoo AHHSCI t5'2 ttfLOSScrrvtttttsc vorto.

0I I

VAPORATORI322

m.ECCER S.CZ EXCEPTAS NOTED.

r vaID H'rcsicAriolc HUH5505

Tt VT1

FL KLCS04)

NORTH Ll()JJID CHILLER PACKAGE S.C.IG(HV ACR I)

30 ILP. RPtt3.C. GI

NORTH CONTROL R(XH4 AC. WATER PVMP(pp rr)

35 GPM SOFT TONIFc H.P. 3500RPM

S.C. ZI(7ET)t)L D G

NORTH A)H COND(GGHING SYSTEM

NORTH AIR HALT)IC)LP)CEAGC(HV ACRA I)

IKOOO CFMIO H.P. Il)0 RPP)

SOOTH Aca «(JV

V'Si

col

tR PactckctEta tiCrra

SOVTH CONTROL ROQL) AC. P)AIEIPWMPCPP 427

75(aPL( 'SOFT TCHI)1 HP 3300RPM

*C.1G'EGGL IC- C,

SQI)THF~MDITIO~ STEKK

SOUTH CTOGG) CNILLC)L PAC)t(AGE()lKF ACR 2)

30 N.P.E C. )l1

~ tc ~ aa M C~ ~ Jwavtia»» tia 5 occtr5

~ aa»t Jta aa ~ ~wacac ~

mace ic tiacat C. ~Ltta C Ci.

L)OTE: rtca c tats)at TestCAAOOCleft .'IFCEtcarxtc

FCD DHC SCS 5(ccctAAT A.7SECrcv AE 0HV AcllDDSA

VV.AIRSViA

rcftctHICCAALO'ILTKR WIRE'ROTKCTIOOI SKS OVIG12-5152K J/Ii FILTCR UHII

HV ACRF

VDI VDI

tal24'v

Accoaaa

w farIiv Acarw

CAST w Actcvi~«v»aai l

oo-,tc

1 C

OCTAlt. C 4coatvk too» totslvolttaicitAtivtfaavlat tEt\'5 (i StaiiD at)

coo0 ctM ~ lfati irsoatM(i 0 Vaaav atar Otlaarlti4)

cact4il tl L50.0

2 satan StcOwf il5iVia

~aii

~o$ (~

2%iV]8

t

I4 ~

SL

Wavvacaaa4 ann toI

il vv'AtacYavt ACOot« I

~Cl. LID 0I

IiltltCX TDECTCcaviST SAH

410COCfai vwrat00 ILa)550

SKETCH CNCoaratc 000» Vtktrcioctv vt»rkarov

(Siiatll EOvltallv'I)

taveJ Jat"SS

I

0

tw'col atvttv C»tata itE ~ ia'aaat

! lpga~

-1 'Ha0

g< Sggtt)

SF

ila0 NISSILC SARRIKRLOOTER

(OLGX)ODIPAlIEIQGKK)lWltL'AIACRGVI

ta ca tata taa w'MAItttc,ata cvctc4 Jia cavil!a'aE J at

Dis»J at» tRAVR COOLS DCCHDCHSaab

UxirEHV.ACACV I

aaa Eat» ta»t DJ ial »'tia' Ha tHETJ AVC t»volta~Acaaota 5ta ate~~

~ACEVOal U ~N

I)

0 Oat IS V I1I Vvii!DlfKa Oacaaccvif SC.ZI lltria50AC. CtraC

0't

Wkttlrlto'c fa„BI

'

AX)

i

ata Ca at i 5totrt ~5 f4~ aa aio

4 co Xtatttt5

2000 tfv fax cck vairIO lit)acovo atatf 04 HLtxc )acO

ttrvtx,

iftLAI coatv iva ~ Aacaat 4(FARtaaaafaa all Dlr'44

:AIILORROIT)oxtxbsrsrU5 stc cccttc

QSTAfv)SV)arl

sN ACCJtDCS Vtl

0 toavstacit illItatrvitV OEOAI VtLC

(rpoo CSH)

ca»a Ctaatxta 'aEietl Ctcoat»

4atta'ONTROLROOM

XaCSSIIIEATION/CLCANeIHV'ACES)

OCCMT Crt)«1505

4iic tttavcrovLwt

r,ilail

7I

HV

SYSTEII vfc valan OOC DCD0»5ID ft000 taaa IHLOIEASARRIKR

LomfCR(CKGGQDIPÃ!KJMTA)IE)l24 t248 aria

rotk Dt vtvwCfv

Vfl vtct rtxttSSOS

HVACR(rt2:KMAC: f / Jt CLGSKDtl 550 C

f Jtcttatf DJ

vvackactaf f vvacttsD i4 2 Jvat ttat ttxaFRCPI coxTRCL Roon RCTtsvi AIR .

STSIDI tbpoo CfIII FROIS CON)RQLRAO)I". E12.43O T.FM)

SKETCH K-3

CXNf~D~NOITIONIMOAcICHCFDCTIC OIACRA)l ra45 0»004AOE ctvtovo r04 vntr ~ 2 tStb Cxartc aNA)'eft COVTROI ROOM atsrnttttKNTS 5vtttsoots ow4 cN Si45 Itv.ll,

natl

foa vilaorn» tralxt StlArttltcn ttcato lot lit5CAVC,

fVt- 5) 23

SIAPERTURE

'ARD

'v»»»» o aJ t»»» v AJ vvacaaacct»c iowa Havtct co». aaa J.aw»v» ca»a» v» tra a»»» «»a»»» aa»a» «»a aa 'a «» a ava taa OJ

Ja a»» a» ~ a»»a ov~Oilia a»v» it t» Aittcttvt ccavc»t» a»»a»v v»»»J» t»a»»vi.~» J H v aat»»a v» aa»av

Also Available OnAperture Card

ctoxAHA 4 liicxiOAHtatcrrtcc Cca

DONALD C. COOI(NVCtCAR PLANT

OAOCXAX CDCxrtat

F,LOW DIAGRAMCONTROL ROOM

VENTILATIONUNIT NQ 2

vJcactx~a. S.O

~ tltt~a a»V ~

2-S 12 9-23

avcatcat tartrate tovcx clatter ccvct.

5 tttDADVAV cow rott

L Cfx.Y tlOCVE VALVENVXOERS'SSCOR

Ctl THI5 DitaWWO. 5CCSctaxarc VALVE rotxrrtcAVNHUST SDR ECIAVALENTCCSICNICCCR) CCVVOERS, 4rkc'raxcscrts vcctrtco FCR

Cctawro vsE A5 Foatowt:TAC Nt I 2 NSW Vios W

Atpr NS 451 rcawtcow

cshtttccxr rtcor vklvf vatx ~

NvS Hor sHowN cH cttawrc015(cVALVEcotxrtrtcartox Utf)CCXIPE0 OY AoottCO TO~ SIACCNT IOAIOERIrtrt Scxctc awtASevrSCN IlltccOVEASOVVLFSrxCAH)

A I B I C GI

M. I

9003 090183,: —. QQ,'4 J»tvaa Ao

Page 351: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Il'

l,~

f;

t

0

Page 352: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ 4

MI

g

1 1 ~

VA'I'I

gl.

t le1

~ vCGA%P

1

t

~ ~

~ )+ t '~ ~

I ~ ~

~ '~ ~

~ ~ ~ ~

~ ~

~ '

~ I ~ ~

~ I I ~ ~

LP3 I'

I I

II~1BH

~ I

- rC4

~ ~ 'dh

G)

1~ ~

~ \

o:p4

(4g~

'CF~gP~jg%HE;%M

KP.BD

bled

Ml

IChRKDH5f~~RZP%

~ ~ iam de%P

~ ~ ~ OI ~

~ ~

II

~ ~

1l~p~g

~ 34FEeR4~

Page 353: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ o 'I

4

Page 354: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ I

~ ~ 'I

~ I

. L

~ ~

Q ~SKI

199

m1RR

RBR

84%P

dh

~%K

8 5

N

o~isg. gf

I ~

W

. ~

0

I ~ ~ '~ ~ ~

0 ~

r ~

.(REIQI

jul~r'r

r

r

r

r

~ ~

~ ~

~ ~

~ ~

c > )

.i . ~

~ g I

1

Page 355: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

IOo l

"P

I

'

5„

Page 356: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I ~ 8 '

C 8~ ~ ~

e ~

~ ~'

0 H

e

%KP

~ ~

~ c

I I ~ cfhc

cChemmet:-mm~~KX~~

~ ~

~ ~

~ ~ ~ 0 ~ ~

r%P %P ~ ~

~ '

~ ~

Page 357: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Oo P

r'I

J

t

Page 358: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~

IJJ

~ oW~I

~ JJ

~ g F

i~

PNg~ 4

I,t3

LIkL

IV 7

- HSI~1pit~

I

af~M 8'

~

~ ~

t'i

~ ~

~ ~ I~ ~ . +y> . ~ ~ ~

~ ~

~ ~

~ ~

MIQi9 bi I

JI«

~ I L'

RZK%RlwaaSiR~:~KX~~~Vi ~

SB:7

~lh5

SI

i 854

KDi .. le~ljg

RTi]

5QiLa

~ ~

tSI Q75

4d~ ~

5~ ~

I ~

~ I~ ~ I

.IKH!5)~

~ ~

~ I '

Q J ~ ~

t)

IS

s~

~I)Il

~ ~ ~ ~

~ I

41

Page 359: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

a L>''Vl

Page 360: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

M

I

D .E

KSICdl

Sr

V5) l 5.- E lCENERKL NOTR5

LECEND~ UAKK~ VUTERI

PRIMARY WA'TKR

RECEN. PIPISIC4

4 ~ CONC. ACID

CONC. CAUSTIC

AVXIUARYPIP INCs

IFL OILUIE CAUSTIC TO ANIONEXCNANCKR AHD MIXED BCODKMINERALIKKIL'EKEowO

~O

I"VENT RECENEKATIOH CUBICLEBY QP

OME 116 (

2)c'oi(I/IK Acto ToCATION K.'XCHANCKR.SKE OWC SI(5, Ll/4

IFL o(LUTE Aclo IoMIXED BED DKMN-KRAUKER. SEE51 13, HIS.

[KSX

Krl I /s~ 7 ID DWSrs

)oi I owl)o TO

I PATMOS

2)3 FILTERED1(ATKR. KT

5EE Pt(C crt tsr J/3 759

lAltELF Critic Sr

NOT WATER

~YANK

SLD'P(A. X7m STR..

tofCooDr

J(KCKILCABINET(3)IDCQP) ~ O~C.OW 9 2 (tvtr(JL)W™

FLASAIXIM DIVAN(R (TYPICAL) 0 SS'

~ M ~ T

~ ~as

XPII NP KPI I

V%5

XTS70i

IOt2C MANHOLE

SKETCH J SrACEI AND CAVSTIC KOVIPMRNTAMDPIPING FOR DRA(INRRAL(RATIONSYSTEM (CLASS III)

Marttgassf 7R()

2)L ytult5TKE

~r

CUBICLE NEATER

bf Qt()C 111, IKW

ra SL'COSr 4

R rvsoor SPRING LOADEDAkMlAKRC(lcoro VALVECIYP ) CDfOLILLIIIOM

R( cxtrcLL) OKK

t Oa(L 511&a WD

(Nnss ~ RDDN r(NIslbSKE OW

~ YoovrocDKFILLDWISCg COMM SKK DfKL

12 55(ST2)irFNXBIKDtx(vrtcocsNLRR(ALIIRMLIT S KK

702 0

I)F

Lf(V757

SYMSDLS

OP. I ERMVTir

)I C NV)K CONNECTIONS

FOR VALVE,INSTRVMKS(TSAlltLING PIPE MATKRIALsAND OTHER S'(MSDLS )XITKIPLAINIISCN THIS DN(L rAND FOR MARK NVMRE(C

CODESs SKK DWS 610*

K, Ntt FVMY.I'r

Frfoot Fsasotg)» 5

FOR ccvrf scoross oasdsca4

5 SRKTCN A.5RÃEIFsccrrsc, troat. Hosrrsta(rcrrlsosatssasc tl Fo Ssrc I

Sfsrvsf Ctll sit tsvr2 ™

SRIKt(VL)23

iso rfo~iV

Dg>: ear-750

AJII

KSX

0( 415NLIITRLC(O

21D adCLC VKNTSYS,%(octo(IAIEIL) ro(z/ISEEFLL(Dfc

NIPLFLZFS)07

LI'701 Jmr

KFI113

d/CRFLqsr/

IATIRLCID

qLS 950V I KSIt YRV.

So Sff

U7~ r~

Q

LsI 24 NlMMOLK.

~ ~~ 4

I CARR(N SIK+C

2 RISK)LD((fft10 (HIT'o

cvcs srs(FN 3(K DNK so((1/L

2'RESELL CHINLIO CYCS SKEK'ffaSI3(,L/t.

~ s

Ma I'ar tr ~

f~tres

4 / PW tot iMINH(LE IGRADE

lcstrsvwvtI

L(. KLC001(r WIIMII

~ 4'NITHcl DYERFLDY( rpRIMARY WATER STORlCE TANK TO FLOOR

STLVrDll 1 'IG DRAIN:

'Kau IPMRNISK Isic Ic CLASSAS NOTEDMANHOLE I

Prlt 0ILD(R DFAIHELSCSH)'s~cotw

rfa CCOLC tarsr its

(I) HLKK VtSYSTCS(ACro PUMPS

(PP-ce) Ri/Q HP. )IltrtH

4

OR DLIAIL1 NO'LO(AIION ofH(RC(NLY SMOWKRS( KYC

Mfs(rltos rtr SLLFVDC ACIDCAUSTIC S(oftACK ARCAS 5(t

DVfli.trSIIC~ SIA.K 1

SA)c N,CAPACITY '250 000 GALS.

SEISMIC CL)LSS 2I (TN.-Bi)

(Vrnr No.'t 5rtcILAR)TALIKAREA ttttYvyrlt.

RAIN To FLOORdr TUNNEL

~CS ~UST,C PUMP (I) L(dot SISYEFL

NOT OY (PP-<7)52 HP SSC K Rot ~cto„t Lc) 9( (Pt

fssrcfrt ra sorsarvf vc Vsse.ossa,svrla Ccfsc, Caorst Srssrrst vo ooLSVLO

~ PIFL'CAP~Y

SULFURIC ACIDSTORAGE TANK

LTK 44 )ClPACITY 10 000 GALS

CLVSTIC STORAGETANK

(TK-45 )CAPACITY lo OCO GALS

I ro sssssf rsr assoccr4ovd caaae ~

))4 Yo UNIT NK I COMPONENTCCOLIMC 5(IRCK 'TANKSKE PHC.5135A,J/2

Dms iDWI92~

srssssr ssa ass~I!'keg ( s,sj~L)C( 1T MIIN

UbtÃt EX(LSR LLG2(sba) ATVIS)ISLILX

2. Vnsfooca ccUHII Nf I

JRLsrc fca cdcr T NS2sc fvsrrotsfcs

(4rcsalrsaaaf aassfr~aar7 caaf

trtco

OWS42DWIOtg

f Lc,

D/XC

I 1 Toity(TMlt COMPONKHTCOVLOIC SURC'E TANKSKE DWC 5136A J/2

Q TO ICC MAOIOCKSboRAK LlrXIMC Toro(.SKK PNC.5146A,K/3

rssd wsr tcltrl ccv4aarsoa roccsea cvsrvr rf asccrrs/srarwvr rc Iss) sssafra rsaccrrf Lasso

s

1'FWtS4

I TD bORON MUKCTI(dlTANK SAFETY'ALVGSKK DtlC.5142,K/4

FVIS IFW(52 g KC

DWI 1DWI Hcccyot(IULM(s«ANKto 5

ftlauDOCLMI RFEDNO((L. I~DWti)

u;.=m „p<r

EL.C'SO 0FWISC

I'TO DO RON trUKCTIONTANK SAFETY vlLYC,SKK PrC.SI+2srV+ I

~ Rl ~ VlI frtrtlcarror Nsrvocos

L ONLY LJrro(C VALVENutfozrcE'FFEAN

CH Yyr5 DrtleoNL 55ESEPARATE VALVE IfrNfTltrrAFKffU5Y fOR EDLRVALD(rDCSI0N(tf(R) fcyutrtt,

5 rfcrMNIOERS MO(Ãffxo FORDncwtfs usd Rs fvtl Dot ".

Ylo Nr. DysrorzrtwAtttles A5

NSWIOOO'rysrnucftzffRoof VALVE lclNNvs NOT srcrorc 0N'lacyocs(s(2VALVE IDXrfrtfrcltrONUsriDERIVED SY lootyd,roOrsrntoc(yt IRRfOERftftSIN(KS OarAccvtftftDCLOLE OasLM"~

vrnbc

(ORsC lcD~~. AIY(51(SULK .5(t Dsrcyasfr VN(ryrt

tsn)Spwlri

Y(0sttNT Rlsol srasraltTLNsc ocarsr veloce,su

ELCSY4'are

DCY ~'w

res2'NI)bC KctDV(srtouLE.

ARIA (IOR f(ttisttHCtotNrori LKT0 or/N H(AT(X(MANC

prt210

ceo oatt

DWltt ~ DWI0)2'TO SPENT FUEL Pl'IOuuy.SCK DWC.SISCsAIC ~ Oa 5

2 TO 0(SORATOIC CATIOsz

SLD /MR Nfltpbtt PKMOL, trro pd 05KK PWC St)O,A/0

N

st(SD LLfsrrtttlCg'

NKOWASSCHO'gOLVLPORAf(((vota sut

t)c ILCOrag39

I C»A, Ozt DC 0&Ill.4 rr

I 2 I), Dwreo

DW194

:." '='~!:,'Wi,.T,::,"

Tr Lsftn VLLOKrlc

r roftcrsfr rosre pf I 5 Stdtlvfstts ~ LO

Dotccctu clo Kc,DLILRsltstJVSOao rrLCII Pw(24 KL(OY.(f

tss ro CLL(osr tWSCOlvrtNLOrfa

SYIO~GL 1 'rrf 0+\rrszr,crs g

srcIFNCRMS

FL (LLIIMFDWto)

DW205

r

3 ~ )T~ 2

0 I

DW101

5 a)t Otl 210

I AY OIVJCT FtÃl DC CLSscCtlt~)C

CASK AT Susttry(S ttd ssOsctrt t)FI ar cs4

5(XIDRZ29

Frfm i ~

IlrRC'/g Rc Y Ta cDNLKMTRAYKs

ILMKTRANSFER tuausLSKK, Dtld.b(53 C/3

«™vassar ~~ aa4 C lorrCFSCaas asar asar vr «aaara Vlsrl Lrtt~a~~ L ~ - ~ Mtodtrfc

ra Va 0r'assrYD bofuc ADOBLENDK)(S SKS r ~ ~

PfrdDLR+,fP~ R 2 ~ c ~ ~ ~

ECIrt

STATION SKKPWS St)S,NJG

SI'PERTURE

CA.RDI

Also Available On

, Aperture Card

2'0 ULOIIRYRooyf/f Ccsorrr FfdfsfrYS(5 tarCIP54/t

cracL rsso IFCRaaL casa soasrorso car 404

tto rcorrccsocsa ossarar~rcrcsst ocr (assi sooscrcaus(Arrl0

l2 5 $541~4

fOR REV(sczy~ SEESQWtcrt IKVI5cry IIK(DRD

foa TN5 DRAOVro

DC OtoOrrtt

DC(02»ClosL 4SN SV4

cstoi I' DWFFC

PWRib/YDYFRDM cHKLLCHN(CINS TANKSKK TIOS SWG lottts

I TILLrllt

IO RO(VC ADO.KYAPVI(LIVIASKK.

OWC 313),L/7

IKXKINKYSP,Frf40

EL652'w'

vr~ OTI

015

uobassa eye or\ wNrvc craaVlsroo raa\ crore coos vao svsv aoa~wsaa vr r 4 ar ra ww+Ae raea r vrs aa ~ w ar» aa~ saaassss ~ ra rr~ carrvc assssV csrvr r va Lrr rosaa csavaa sv ar ssssssV sssvwo % saso~ va rv ra rsasw raa vrw

LVto)cease ssoaacsstzatslfLocrarcsctsv~error vcs ~

3 IRON MONITOR

CSIOS

~~

TANK PUMPS SKEDWG. $13 JsM/9.

Itafrs

tbFas'I90 I ~ RKCII(CLIMF

Osx 902 4 VNnttt(UNITNit)/ QY(HT plIOU(

I ~rfttt

~ tons~ Ltttoocty Narra I MCroa LrrtLscrt trios

Szo TO~rOct drat%AN'tuw srtr ttrd cooLLarcrtaroAItfrNrlSLCVNCr D

tVac Ig

3'rfttt

It'ra aasrLCwroraa arL vac 444coo coraocc. casaavsvra oassaa(rOV4 LfONJC )4LC

atrLO carl AToosr rNLc 555

~sC. Cfc sscvr cf svDW224

f DNL&uyfr'WKI 3'

FWIISFWllb FROM UNIT Na 2

PRIMARYWATER

frcNANL~ rocyrcaN c1$crtoc cclDONAU) C. COOK

NUCLELR FLA'.lr

L YV AMAKE.UPM/AlER 8

PRIMARY WAIER 5YSTEHLSasrrvor Ll

KlcltvrdrcS ARL lrdlKzfL)4(A )2-Sl)SA rLI

~vsc ~ taI

ra FTA

J'r'Tsryfyzarrcd cltcfNsc fottR MRrset cele5 Oacyrolr uN Yttft

3'c % crbcscrcH u/'twlosN " tvzto/rtttrtoltl S )I ~ twac

fst)j

r-Ityf.

tetotsCISINO DCLAIN rz

LKIPRtyltY WATER PUMPS DLSEPLAIR(50 Gttl '22S FT TPM DRAN20 HP 3,COO Ray

VHIIN'I I (UNIT Nf 2.SIMILAR)(tt 4)) SEISLIIC CUSS)X

isWIOSS

P

6

3

PUMPS ANP TAMIL(SIM(LARTo UI4(I NID

) kc.scEtrclstcs,rvcvt/5 5OWC. )Mls f/')s H/F

PWIOd

DWltlDWI to

4 trrllcot tfffttb~DW219

~vra FW114

Ills

800) 0 r) 0.183= gQ

g'PLucvosfr 100tcA.SOO ZRuol ye( 4(KPwc L~IAI(VO, (NN ILMAVSSI4-'6s

Drfs si(5N/ss

Corot AT CONN ATVMIY NI) IINITNit UN(Tag OIIL

vtrf(5 FILL

PWt IION NKL

r Hnlo.i Nc2 ~YI)r AYVNIT

AUG. PVR>G ATRo.tl CHEMICAL (5(ARCING XLNK SLSIS 0

IL.IIW ~.u rsrf s r a~<——

CHKMCAL CNARCING TANKucrcc sce Wr

CAPACIII 5 GALS /CLAICE((TK.692

PWtll4 t 0 H J K

s a ~ ~

Page 361: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

o

~i'e

"1

Page 362: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~~ t

C ~

$ . ~ ~

dhqp tI

~ 4

&m~

%Rehrmmam~m.mAIi ~ ~

~ ~

~ 4 ~ 4

~ c ~ O ~ 4 ~ ~

~ 0 ~ 4

' ~Q.s ~ )

4 gg~ $34~W~a~hm ~ ~

~ ~

~ ~

~ ~

~ 4

~ 0

~ t

~ <

~ t

P ~

~ t CKKHEHf~tRZRU)M~I%

~ ~ ~t ~

~ tt ~

~ '

~ 4 ~ ~ ~ 4 ~ t

~ ~

Page 363: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

S ~

tI l,

'll

Page 364: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

f ae 4 I B I

~ a ~ ~

1 ~ D I E I F I G

~a

I L' M 'a I c)

4 I

I clcr Z) 2 DIMINtxatizto WITKINSCC oeltl). IZ SNSA IF/7

SIANWA'Y FILLLEGEND

t)ORATED RIIT .RPRIMARfMITLR

AUXILIARYPIPINII

= SYMETOL'5DIL'PNRACsl Stll

,cia /GfHERAL Itot'ts

CONHSi PLUG COTNL

~SEE WOIE t:OI+

/3

(-I)]I SttIM Pxt15

5 C)t/ tb SLITTNS aaeetLSV( 04 (

4)J

0 ~ IZ.AaTNSCN

f.C at.bw t54

OIV taeDR IC ACIDBATKHIW(c TA WK

0 DIA t '1' HIGIScap. Sot) GAL5

S C.)tt(12- TK-Ib )

SANWal

~as

4 0~4CI

SPAIC'I

I STRAIN(4eefg .I Aeeitavb

t"104 ae 1Foz PMYSTCILates T TSSRDahs. 5454

FOR VAIVECENSTRUI KNTSAMPLING, Pl'PE 'MLTKRIALANO OTNcR SYMDOLS NOTLXPLAIHED CN Tsals DYYG 1AND Foil IeIARIC NUMZTERCtgstta

~SC'K DWG'3 IZS103 4

SIO4

4C al Steel 44y TVCCOS 4 ha

I

4 ceca» I Jt teaa-4 I O'

ea ttrachh I.taactS Qe raetdCIaatas Peat 41 aeaebs

25045445 Ocsaoa

I'CONOEKCATL TD IJISCDRAIN TANK.SEEDwolt Sltetetle

IIIL

rciprat wshtcbenstts apepeaaetaweea paaassoal taea (ttp)

C)

0tsaat4 ect

el csaos

Q BY SY fSTINKNOUSE9'aP

404 ELLV. C09 04

A'

ALLVALVE SANO INSTDa)LMEHTATION5UPPLIED 8'f+EXCEPT AS NOTED.

Et)UIP)CENT SUPPUED BYeJ )NOTED.

CP)

4ze "".Pr zt) ATMOS.

Sre VENT

r2 fCIW

PCSIISV

sn

0$$ 414M

122O'IRSO, D/9

I.RO.OZK

IZ.ROIOZM L

FC

FC 0'15ORV-410

2

~~YE ~4 AIG.CIC. 0/C. LII

OVERP LOW LOOP SEA'5 TO SEFILLED TIITN D 14HERALIZEDWATER. wNENEVER TANKS AREOIERFLONZD. LOOP SEALS ARE TO

bf fLUSHED TO PRKVEN)'ORCACID CRYSTALLIZATION

~12 Ott 470 >C VTIITYO411405.

~epcsatac

C.CS ~ 24$f~LO

ICSIISVAr-

<tcscaas

/Z.RO.IOZS C~ NLAY

TTIACODeboRIC ACID

F I LTER(UNITN0.2)

S.C.ZZ

2I 0.V.CSIISM<

eaee eaaeeesSeeps acct

SIDSMacle» t CSITIS

Icsatas4 CSIesaa2- t csalt5L.O

1 Isa l\),

~ itCSSS

QSX

I-401

~aae eaaNesSTCPS alee

Z.aC-IZ(IRXF TRACED)

SEICV~ CLASSIFICATION OFEovepeataar As Mottow BORIC ACID

fILTER-(UNITNO. I)

5 C.)f

asx401

SCSSSSN

FROM UNIT Nt tbORON INJECTKPITANK SEEOWG 1.514zca J/4

pcsssc

r )

tcseac.s+

'@=+Icsatos

FAT tttAP>NCSStnlaS saCttra

2TAC54IIV

e

~l1stcl

~SLSettal Z4 I+

metsaat 1

)( QZ 'tcs4at.

(I OC It)CR(eaT TRICtb)1CSSSS5

0 5'x

FDR CLASS 3 ITIRRIJVEMT COCINECIIOHS TNE 1st SIs)VOAICYEXTENDS To A5IO 14(IIIOe&TIICFIRST ROOT. VALVE

fROM UNIT NttBORON PUKCTIOVTINK SKKPetti t Slit 0J/4teCSSSS

~ aa4GDXSS 4 catt F ITRAY

ttaaaaCEDt.cs» ss

NOTE. MUST bE INSTALIEDTKRTCALRVN OF PIPE (SOTN VNITS)FROM CONCENTRATES

$4OLD IN6 TANKTRAHSFfR PUMPSSEE Daefrt.itsss.+g)

405ae Taa,eei

Seaes acct

51St 2

zaosto 4'2 OyLI CS4tb4

ZOS

) 'Lanattte4tf~ ~ Seats a cat

14)IO 410tsxZDS

4 eaKSSTOPI eec 4$

t.caascas

PCS4 teSKIIKZGEUCY

c CAlaclat

TO CNIZQNGPUIIPS 5'ffDRGI5129,G/7

AftfCVITEbozaTN)41

417ecsaas I

27~ F fsrctCETICY

F.z / botATIJN

FAS 4 Z12

$4215~ 4'41 TRACCr To CHARreINfaSTCOS NtCEM PUMPS Sff

DICKS)29.G/0~eelst~

~C5 ~ ea Iac5 ~ 14 el410

tTC Itaf NtftiCCDCNIJTCN fbt facaa

COCTPONtNT IDCNTIFTcarTON actaicx15'It IPACS5 JINttWTSL NbttofALI

I'RAINTO wscentt

-V.C44$ 4

PCSASS

.a TCS ~Iaa/aeal ~

4 twlSS4' NISI

e

~I

TD UNIT Ntt.DDROIC INJTCTICNTANK.SthDWG.Z Seat N/G-O'CS41044~

Res~Is-/fI'CSIIOV

4.1 TO UNIT Nt IBORONINJECTION TANKSEK INC I 3142)it

POTC

411

QFC

421

aeaab OP Teat VILVC

dt«ISSn

1$ a Ia I~.

C'Iatis1I

IOCNTTFTCATab'4 NCCMICRS

I ONIT IPROVC VALVE AVMICRSAPPCIR Cre TAIS ORIWPCC. SCCSCPDRITC YALYC ltatntarltatWILT5T fcn COIRVALCNT DCSICN114 Rl NVMICRS

g 1ALPNJMICRS Mbblfato FORDRawvas vsc 45 Foclows:

AG Na Z.h5w veto'wAPPCARS AS. NswaOS

Q BORC ACIDBLKKOKR2.OO 21

SCh BiilltN415(4'fAT 7Ra(f0)r g

NtastALTERNATfERATION

acpaaIPat PSUCS~tC104(tYP)

LA

430I IaOLA

(410SI

'PERTURECARI}

IA

410

IS CS454 QNMRCPCOSIEKOE RI 00.21

5th EINITIP8(HEAT TRAI(t)

2'H)tt.iel {Z

eCSICS4 t~aes 5ltaT

dltfDqP)

iz

5e l~

I CSIUStCS ~ as 4

IF3 PISTRVaatN ROOT VILYC MARK

tits IOT saebwN CN CaawsNISCCVALVC IOCNtarICATIVI U5f I

K,O.

IIcslls4

II

N(AT1RAClDLr

IN.potrerwzt ht

+0+TCO'LCTZLccNN.(w)T

410OCRTVCO RT AJOTNG 1044STRVMD'T NVMIClilf01 5 ITFKC ITCPILSC.YI

70 'I QCIItx 44PIAe E:VAPSTRC AFIIVSIRV

I

SEENOTE'r

at t.IL

SEENOTE'('

tNNII

~ 10

StdIibtf''PA

iz

DP(

421

Or)42

Mlt TIVZ M

t tntCS( fr )9 IF

~3

2-TtQ. 5

41

I tTVZ N

ore g,rI

~

~

I eaeceaJ

.IC

Otc'21

Pwtsstrctct~ 4-

RV41~@'.C

il10 CHEMICAL g I.PPIIO~MIXING TANTCSEE (NCCISIZSANlt~44 4 1 ~ ~

I'2

stveraaG dbc 0444110 SUsFLATE (TTF)~

2'To cNIAGiaicPUMPS(NOIIIAL ~

CRT.GING)ALEDWG)512SAall

HEAT TRICGK)STOPS NERK

Ot411

Iso Available QnAperture Cardfot MICROFILM Sratelsstc

lesTSTSTI It~ fot 1145 taa e

ttN417Z Za taacrtt I I

444

foR REVISOR DCSCRP™MCSCFIVIAtK RCVI5104 RCCOIC

IDR TN5 DRasvio[

cae)aaa

)~y'nt

t4.Stt

trat 141*

HEA'fTRIOPIG

'

'lcJ

8I

I a':'

' I

I.teltsSI ~

PFP44 Ir~ STOPS NLRE

ZCJICVA27

l)tat tRICPCG

~NLR

rLfIT IRTCNS

TKRI TAIta.stt

~athtxR('1YFC )

A

5 illel

2

ee

RCSMHM foae43IGAJT/5

I

LSTOCS 41st 245'Sst

WC'L~ e4.$

~~ p aN meat w eae aeaaecacaectaa Coact Neeeca cpa. » ~ ~~Ne eNpee ~ ~ p a~e~e woUeeeeMI ee~ee eee~ ~eea N ~~wwtpeee % 'M ala NeerAcsee ee~aa eN ~ wwwwlw 0 ea E wltwo$%t eNW

Qw 4 SORC ACIDTRAVsfETI PU44PS

S.C-).Tscfsa 23SFT.TCN,(SHARED df IArTS 4 iz

(pp-45)(IGAT.TRactb)

BPcs sis

~451$1 I

STOPS stat IeCM44

ea

~TO CNE MICAL MIXNGTANK SKK 444 Z.SI29A,R/1

tcs $ 14SIJi. IrtttSFPLTGOAISV ttTPI

Se

Lg Z etntSI> ttctsa- 2'ca

INOIANA4 MacNCOAN ~ I Ztteac Cch

~ 4ONALD C COOK ~ = ~ ee

NUCLEAR PLANT~aaabcNIa Naoacap

51 SKOFLATE DR(TYP)

alcsan'I II'CS405 2

sc5 ~ I~ '4ICSIOf

2I 2- .I.C'I440$ ~t 154thI.Csael 1 FLOW D)AGRJIA

CVCS-BORON " iMAKE-UP, }';

UNITS No I 8 2

tC'I~ ea D

24

bg4Q cb) tscaccic Acao Yaaacs 1 CsaahI CS4sa .INLML 12-5) 3 I-)9J

1

I 154IO3' FNPE CAP mac~a

ea Nr.~e C'TPt CIP

R) +a.3 tzlo rcd.x It'c)'setolt

EAPAGITYIILccK)IGIJ-CtaC 12)

~ )I ,+~I Ae ~ C... P.' ~ rt IICF/'

CL SGTSG' 4 ee

~4 eaae3 hr

(its LBs/NIL'2 STEAM SUPPlY FROM E)PS l SATURATED)AUD STEAM SYSTEM SEE KITCa za

IZ.SI26

0 44

179A SVCS 9123k; JIG

A I B ' C

So4

91 31 JFG

D, B I FI I G

4se ~ 'ee eaAaa'eG 44'eeNAer I ~tAI'se 4 r N > 4I' Ah~ is64cr A» F.CAaseaeH

n1111 Jade JAeI.. J ..I K

I

e

4NCCKIP atttaaeC POWIR etaeteta'Oht 'Icoaopar + r 4 tea (Lefat I

I . I

~ ~ ~

BOI)-~-0-olI i 8 >--?)4~ ec e

ea

4-+cope

Page 365: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

l

r

Page 366: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

NOTES SPOOL PilCFS VSLDfctrL DRAJTLLEC OttitlNSFlt'Aii r) 8)

0 I

2'S

Slb)ID tLODELOeliu

Wreecneceet

wl,-:

c I

M))SY W w/TD Dcmk)FLEL "L- -"L I/~RTApit KLC)00'i g 500SRIOS $ 2 5FOL

2 F I c

VALUUI4 CLEAN!RHo)E COMMS.

SFIO3 L ~

RT NOTBT9 .2 AN)l SIPHON VENT

(. KLe5052'

IC I

~T~CCECF ClS LNSTPUT'CTEYLiras Tva 1'll DEELEVDAt.t XCELLXA

vt 'To Aiip vecrepeaec x»L ~ LTLSI

TLCOT VACvt.'fOIL COOC CSS VXELTSLALLLtDTLALNC tie XSX DDEACEATATCATFNDS vt 'To AEED LEELLeareecittic frais teaeeAL T citscDMAL»C

Ct

GENERAI. NOTES

LEGEND~ SFEtITfUKLPITCCOLLNG WATER~r~ SKISLLITR CLCANVP

AUX.PIP INt'r

WATERPVRIRICATIOH

stccic riel ' 5

Av 3 FFLOM teOLDLP taNFSRttttKIALLDNPUT/ NtOaf» Ho 5132,IVY

2 etc» TTAvltiece»EA SLLALT

CL

C3)'0'RAMSFER

CANAL

3 Rt)LMFILLctt OWG. 51)O, IL/t~

~I HO5t CONN.

ELCZL:I

-QE'43 C

Slee SOT

,t t (

ts ~

C) rl ~ALIF).SWLRL TANKS

gl Ii)S)DE PIPEIO

Llt

10'

EL CSOO

Stite

~SF t52

FOR VALVE.IN'STRVMENTSAMPLINCL, PIPE IAATERIALAND OTHER STMSOLS NOTEXPLAINED ON THIS DWCL.ATID FOR HARK NVMSERCODES SCE DLAY )2 5103 (.12 5IO4.tOUIPMKHT SKI'SMIC CLASSAS HOT KCL

OW BY WESTINGHOUSE

ALLvatvc5 E IMSIIMT)aatioHBYOw ExCEPT hS NO'TED

tOVIPLIENTSUPPLIED BYOWASNOTED

tT

e

f

I i

/i Rsf.$ 01

~1 IJcEK IIOTK 2LC/4

~NOT

FoR ate SUFFLT Fot SPCNTtvIL PLT Gatit SEAL.SEED»C. Sr)DDPIZ.

~ELAIT

~lTLOCATE Vt HOLE IN PIPE 4BELoei Teat'' LINC

LOG ATE KT HOLE IN PIPE 4BtlOW VTATERLINK

IERMLNATEPIP'K CFTABO~FUEL ASSKMBUESND'IE4 Vg'SAT ATPJUDTABLK SUPDORT DNSLsIMMERS To 'LIMITDOWNTRAVELTOv BELOW NORL/LN.WATER LEVEL

5 ee/C

TEE TYPE STCATHARTIITN TEUPDRARY vcREELTFOR VSE OLIRINFTPREDPERATIDTIAL FLUSHING.1 LOCATE As cLDSE To piatpAS POSSIDLK )

trore e 'nec Uvtt tetteLL OcbicvVLOit tow Jete cctreceeecvt~pcvrrceirov vutvacc t»NSELAATSS DrrrWIEPSA ECTTCD

ee i'i.'tt

AR Cei THIS Dea»LNC. SCCsttAeatt valvt totkttttcatwiVst FOR tOVtva'kf Dtsivklvcel Nvttotes

g FAC'wLLEOTRS teNfttto foeDRALVFLC Vst AS folio»s;

FAG Ne„ 2 tesw.vios wAPPEARS AS AS»EOSW

5 pcstttveetkt Root vtavt HaticNTS NCT CLLOLATt Dti DEIA»VCitsttvalvt totktincatcv Ltsr)DCREVFD DT ADDLNC to ~

pestALTJpet Nvuote:'toe SIACLC petiLL.XVItoe Cauxc Fttcastivtapfletacc

VXCXtATISINXI

FIFO'TStt J V.sttl<~ „.I

MKNOICSI)5,04-Stttts

CSZSO~ A

~ TI~ Ceo 4

3Z

ZL

Ot'titEie

3 taoel 5 Piece ~ R ISOO

Ow

TO CVCS HOLDUP TANK. 'St.t.Pvio. Sisters!5

Ist ias I

Sttetu

SPENT FUt PitOtutu teauZERtsb'DIA.ICT' STR.

105 PUAIP51 . Mess

3) ISF IGS FLTLIL XXFAFN

IO'OLtLX44 tLGHwttC. 5)KAG)t)/

Stiss

'4

=,;i"ta FULL Fl)

I it+a

RESI'H VOI.VUK30 CU. PT.

1 OG2) (S.CIO3'TD)PIIITRtsi'NSTORACt TANK

8',Sr IOS+stileit

TL LIN

RPI 5)S'5'm eet RPI)OI

~ 5TIIGetx Stl'53;''J TtttIRPA 4PF)D

) I I

'teoet CF

Sitiisv —SCELSU ECCHANGER

lt)Sttiit FVTL PiTNEAT KXCHAVCCRS It B~

cacNT FUEL AT

~ I I etacuERALTLR

I ufoaxe'4NKJL

OW(DOC)

tetlb

K (ut'I/Ett,NE Irt5)S.C.'& IO

J .ttifttY)ieti /

'cs gStele-c )

StiiOVSe»OS

REACH ROD REC/taL.3

XXLSeisp 'I

s EFIUI

ts(Ut)

CASETIC4 yt DRI.DI)L.~XJvtut, ~

2

P. D I502Stt DLVG.)I)sa, Z rStnt

Dtt. B.e

EL. LI)L0 lireVCL5~r gr

H

DJFTICTAC J IO cccttNOOC 21ALV

%5cWO23

RSX

~iStttb+

5

is2

I 5till~L UEH

ego

SCLOIF l5C

8152tttt 2 J

OLXSS

I

SIAPERTURE

CARD

/ ELCCY4f~5'/LA

~TD tl

SITSO,M/9

Leo)1

b)i M SIXAATR ttu4?v SDiU/Fe 5133'IY SLAIDVS txKT: SO ~ GTN 4LN Stt)l

!VJ'N TO Sa)ctsatt D I3 )J sit »pelffST/)C. l49SFKHT FXICL Ptt

SHIMMER PUMP =

IOOGFLI Soft TDHSNP I)SORDM

(Pr O)t)ist)m

tet)F,M/4 51)T.M/I ELCCG.Z aEttoutovcoutHT

CXLIET3SYSTEM.SttP//G.S I)5,M/5OV4

Stt)SN IStttss

SteGSStelu SISRL/0

Rt1521'5'/4'ast

PLAT2 DtaluA—SDEHt CUIL

CASK CLLCE55

3 ~

12)Srrut tua ATPUMPS 9RDOOGPM 115 FC TDN

100 HP 18CO R PM(/PO)VIPeen) (S.CR)~L

III-.

1'tuetteALIZFDwlttR,stePriv. 5 I ISA, Lt/C

)so Availab1e Oa-Aperture Card

y to Rt FUELUIG FITILSTORAGE)AN¹'MotrCittx)ttCCA

32 sft42

~ .t7 ~

LII ~

~ ~e

I

I

IVD PUFLeeg CCAIU.O)e I==.5-e~~t ITN)E) SIFEATGER Spt Off

NDT be Q«) 5144~

4i//e )

OVT5IDK ttaCIOR COLRAUIMEMT INSIDE REACTOR COMTAINMENT UNIT Nr Ir-———~~NDtbr~»

I

5 t) 'sLtc/«.SG CL 445 -8

2'2

) tt ttOLN»S ervncP '

FOR RCVIAA Dttceittett ~etSCPLCRatt Rtvlsek RtcoeO:

foe tees Dpaaxettt '~ '.I.1,

MrM»M Mwrwr I CACK»

UNIT Nil23 To CONTAVI LENTREFUTQ'JIG CAVITYSEK SX L5 IIOS DWG

jt Vka Met~

-1 Stut /Lh NOT Ov Q»/

Sties ITL'teo eervctnsTEIL TNTAIL ess len

Dercccte

estis

Ntt OTQ» EO'SPMAj h9CC TX)))cp NOT OrOw

8~

El. C45 l)g

REF UEUNG .CAVITY

I ~ LRIE 15 CIT SY OUIL'ti

eltcTK terre ecrrcc ctir, Mee eeEwM Mr p v rr re r 'v wvrr

p EMArTMe iv w r TMMwMM~Arie Lc er Jv»~eilr\ Ee»M r M et ~ lie»ET cert r~ee M »M» rrrtwv \eM»ww er»Mere M\w ~

psctts2 p 2)'x

SO)

I211 lii

Oi5

»DC OT et Sl EFS

Itst IDIZg

SFISISSiiil

MF)SYON)/t')ST+~a

C SASEDLATE

502

RPI

2)L'05

14IPX tNDEANA ~ EACHLCAHCLXCTRC Cr~.sr tss

e)-ept

I. DONAU) C. CGOK

OAECCNAUA TC . CATQ)3I

3'FROM RDRAIN I

STE (7EV(»5137f/3.,

EL5DTLD

Fh",t I

LIKALFU)L)R SUMP. IIM PURIFICATION

PUMP AREA

~rto OFF

I

J

LPIEF NO I

L4 '10 REACTOR

NOT OTQ»

Vtbt k02

FLOW D)AGLAALSPENT FUEL PIT

COOLING 2L CLEAN UPU

2'ent)FFI KfOw

Yi'5LN DCSINt/RC,ROOLSREO ~ CDDLANTcieavtTANKiitDWGNr S)3)A.C/G ~

REEL»TORTESSELtsttxt Q~

LCest ESA

Ot OT irRS <St JS

SIST,IL/F c/Jf

0w REFUELING watER pURIFKatiou R IUELVIG WATER gFtLTER IOOGPM I

TO FLOOR DRAIN PVRiflCATIOHPUMP ~

Io'IA.Ka''HIGH IOOGPM I)OFF tiiH

(L)C 33) (S.C.I)t) I. 10 HP SGDD RPta slSY I/O(P.P 30) (S.CI)t)

L

r Stree VNTMOt

To UNIT Nt2 REFUELING CAVITY I(VIA ZCPN.SL) KL SPILO-

LE) e lL )' I~

/ »Ocit

~ i'

1 STLO4J Npt OrQ»f/G

~ t4

i, .'P'r, - V. ~'-

1 'I(It

'ttt

))IP

~ ~ t

3'terat REFLLKLJNC

WATER STORAGE

~)2-5) 36-,tt5'

e\CT i

TANK Stt Drrtr)ILC t/82'DRAIN

Q

t SKFTCJI L8 Title DRAWL)AC.

PIPING AT REFVCLLNC CAVITY ILCLEALue uiiiauLulili IL 'I u LAAI

~ rqJEDEICAN llIC.REC tpexe Iraelct Cpi1 eeOLG»ltt 5 C lt e NIV FOD, ~ i

) . cv

I 4 I/ K IE

~ C) I> e tv» i~

A-.?jr)e

'L LA Li .Li- 'l KL J4»LLJ e' 'Jvse ega, gq e r T sr Ty M Zecrye

9(jo >'0 9 OT,8'

I, 8 I- c o I 2 .I F

Page 367: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

t

I

": ~

~ 4

gl

Page 368: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

I '~ '

~ ~

~ ~ ~ ~ ~ ~ ~

~ i ~ ~ ~

~ ~

\ ~

~ ~

~ ~

I ~ ~

I ~

I 'I ~

, ~ ~

I '

~ ii

~ I

~ '

8$ >~

'

~ I ~I ~ ~ ~I ~

%P %F~

~ ~ I 0 ~ ~

~ ~

~ ~~ ~

Page 369: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

V

h

Page 370: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~ ~ ~ '4

Ol I) IQ-Zl I IIm~IT stt

4 I 4 I~«n «4 ~ ~ )44114

I

A I $ I C I D I L I F I J I K I L MI

I I O

GEIAIERAL NOTES

LHiEH9~ ~ Ctvrhhat)C TeeW

01$ teHN

rb «4

VSINH IN PSVVOLM So'8 IC ~ ' LA Parnf ETCafrwate IEW CC V OeeeeLY

~4

LTYP 2 tao)~wufwnah»rearvaseevseae w1441aael HION

4

~1 IIt---o-----l.-----

F~ tt ops)rouaeeCNsf

IvlH coeeLoe«HT~il 'Ti cov ~

'Tfs ccw sc cTV'ENLLC Ceaeo I,DDS.LI

I'oostecoNT.

ASCDORICC Saoorlt

.,CI ECIJIel \Mhw ~ eeoc»L

~ » ~ veow ~ sosarrwc TLI)~~SI

rn4«1 ro

CONTEe» IfecT 'llfesl SAOSPLC 1 uv Il

TV1 1 6 tsl Hs«44 n )salt,af)

fea

ta.ttofN'» IV n' ts oa~r Oaervrr VSWXes» PVEOC Settw NT tH'oe LL \Isa»4 Lvr,

~ L

'Dace sl ~O

~Stet $ $

~ ETIO 'r« I

/'I«4»

~ II'l«WS

C'tres»st CHattf TO SATLHNsocsaaoc.v«OAN TDV+LCL CNPO It'SIIDA

~0 PPAILITI

»»» we to.«LWTL44 144eH Csv 111 'IeeoHh at rsl

N~OT S0 Tr s aov oeaotsv ac IEC cta Dc'

leal NeD evtcootst 8ts cte ctsalls or Eoenaccenaesesn

Surer LCC ROW Ceaoth» I'Seta

D Tel sass voeED avo oal~ 4 ~ el l»EH 0«ooev wtl

4) lsl cares«sen 44) a»v eaNews Lsaa CI IccltlAL NEIIL

I)halts Neo ter»a Lear« 4 a««es»«e«wr arson son OON tsvl,~ wAIN

41 CI rvsseev asacvc eroseta esne

I)EI re«VNNA 44441 0 OH~)g greslsv» eeroa

~ »vew a«eeE 0»aan4w t 4114»« 1 caw»

Cut

0NUS DOST ECCIDIVT

l AV 4 ALLI P

core«4 4 HrC»FA l aee

sn

> vs'

se

Slg youosla

~140 41 44

coot 'NH ADO'c' ~ I1

ARSONCILVUDk Vg

Lscrcu lWI ~

<ealt«os vattL 11 ~

ICCC.DIO/'e I e)

~ 4aT OL

Eo ESS

-'ho )w~ AW rtt lose Ela «4$

I HVg~ I

CIAO

I

4«eat rollOa ret I;

I-.

I

I

~ca»s-I

l==

I; .l.:I:I

I

( I

~Pw«vest tbt

WCDTRNR

4«b)SI

0 I) ~ .»+es

~ ~

jYfae 1»L

0

as a .t -a~wwS4«aroE cw 'EATT ~esca e» Aors

I—~ OITHET 9ol

VV«I 4$ )Hanw

~ e« 1.~~ ~ INI Iso«4 2 Cs

40 —r'aJ H'> ~t«evP

4 Ew ~~h vs» AANL

~0

~ 1.)1 S

LIto«I I ~H»es» t««assr~vaa eaNE oc'44 ~44

~4 Sa taws0 «alTI ~4,

tasf eue~S Ira

nc

LI

C 'I

4

I..'='.: .

~acr I. ~

~as 1 4114 ~s»r olllsv cscvh~4 eel COvle~4~ 1~ 1l'I~ I~0lsWl 4WsSlsITICACA~AIA

A

I avets ~ I1141)$41rivet.lve~ INI1JNII IIIIt )Ill~sellt OtaI )41t )VsI sellt )IN«144~ svs~ avesve

I ev»eoobre~L ~ lr«os«os

«saverH setab)e»t'f1\ II)114»11st )OE

Ill�'WE

tlt 4Hfat 4IO4 t 'S~PI 'O

coEet 40M eu»«ceoW eo

«\ les

s as

~I'IN~ «bise «bass

EI«44

~L»u

~ ~ Ihvo~ 0 ~ ~

IO)Ooba» SCMNO

ISO f~ ~

'IC eoa~ . r

l 101

~tssbercfe

One»el~L

Obit 4& 0 ~ D)llOOPissue ~4

4$

EH4 ~ I~4

~ Ts

~es 4~4~WAY

«4 4 4 4EIser)

I

I~esllafeov

lf

IN Vn>'JI~ ) «I Il

1TteLEUH424 ~ ~ 4 ~ )1 r ~ 10ft I

e bwe

~ 41 CC ltot

11 Iee ~

~ ~

W«& ~ICM 44

4 AIIU(

I«stoats

~ ~

~ « I «e)~ 4 ~

'PT »SAICya serve

--;.45I»cevseCN

~ 441 444 ree

I~141 O»ao)s

IC.H I II

uu

r

I

r«IE 41 Qeoa

0 I

~'ul

I

N 4

»st«roIc,

'

II

1»r'WsI ~~ICCII Sevva

I'4)"llIarl wh'D~ «e aea

I 4

I4 Il ~ la Ol ~

e ..-e~ Le

S ~ ' I

<itevee

~44

0 4

I ~ ~

I rrMI~

~evaa 44 4 tCva so ~ 01I».Os

~L ablef~SF)2 DECEEOIATItaf

POR 6ACN CIEPCPIENT C)EIIO~TIOIIIS IZ'PCLC$$ Ofletefe\C

I.I-N

vase"4 oea o)s I

II'lse44

W Iulbl~ 4

lM~1 g Ivies«SQ~1WS sn

SsLDNLTIINIOUKVALVKNVuSERS

APPEAR Osc III IS DRAWINC.Sf1Sf PA»IE VALTC IDEN'IlfICATION

IS'I IISR LOUIVALENT Gf8) QlNCR) NUNDERS.

"IACe fetfu8KRS LIOD)fIEDCO)IDRAN)NG USE *S fOLLOwSI

TAG Net NSW VIOSWAPPKARSAS NSWIOSW

1INSIRUuKNI ROOT VALVEIIARCNTS NOT SNDPN ON DRAWINGMf.VALVE IDKNIIfCCAIION LISTSDERIVED DT ADDING TOINS'IRUNENT NVNDfsflTOR SINGLE IICPVLSEIVI 7IDR COU8LECNPULSKIVIIVOSVENO

TZEeefNSIRKAIC

»wss

91»es I~ 4 ~ 1

1 1

I

I Cre«ctf~ ~ '~I Ifffa

~ vr 4H»aI 14t «444II are» aefo»EI+yea aw osge

I ITDE CCOST att Icwa ~ se14.»erC 44 IAeu» C NT

I LsropDwrLC

NITROOCef PVRCCOIC co«f) eDeoer,rrctoe'cocM I SC

LS 'le ewlC IH.a»

~ ~

~4 VC«4« ~ fI

Sb Seaee«tc ~

~ vw 04»4~ \ ~'144

fg Dv«enasteFLLrr Isset vws e.9«sp Iss~g~ii

~ 4»nIIIe«4»

rvwr «else«4«AereE s«L

I'

C L40 ECleaeH 1

p ~ ores ~ ~I

I="'iI

~ ra bv VVI»4aa«Le»an ~

CC rsIree»et M»

eo fres

t'j»4ecIe'IAPERTURE

CARD

I

I

I

I

I

L

~ tso'4H

\«04lr eec 01Haec

I~ V~~I.JL~CECTA'Plfecg

~ rOET ll'4' ~I-TT SlEc c I»0 I2 1»P

Ceoats a 4 rrsoTco\ ee (bib le

I'k$ 4$4I~'4 )0 Nb $ $ 4

fOR REVISION 0~TIN SEESEISCRATE REVI$ION RECORD

fDR TICS DRAWING~ 14 I

~ )

IAsvshvo sup« «eve O ~ »1) ICHN>v otvr ess ~ rpv Le

rr vLIITIcs AVCOLCS Ytest OYD

HSgj~gRNS 4tOr

he cAIeDIEATICNMt Dea«D ItDealt Crt ~ we 4 hs w»ees er ev I«facet

fs Ice rc roeta 4 trcc coao. 4» 4 aev»PA seve«» e»s et 4 op 4 4 oev»ee»AVML» vis»NML»rvoW»4

Also Available OnAperture CardVW 4 ~ ~Llhs»14ee tooq y

I

el'tst

Ne I <L

LNE4»D,

NW Mwwr»ep e\» Awe 04~ Mo cwree v I» II~ Naecc cw~» rv Avvn er»»44» \»t ew«PLw0» 4 Nerwe v»»Mre

O«ouaY

l~ Iles a«»4 eatn

I- lse 44 wH 44 ~ «AlasIa ~ \'Ne I\vcos»os~tao

~ISea

IN

LAIeaCIIIN tEAT

4) )V

I Ihteef«IHtsEPL 41 te«E4 4444 VD

~41sttaeoaeaSh ~ SlVe

~I ~

~ Ie~4l

~ \4

as

f4WV14Lltt4 ««IIA41 f«vow. Ns

'e t Noon

Osl 0»

INCNEIIA0 NICNICANCLCCTRIG CCL

OOIIALO C. COOICkUCLEAR PLLIIT

~ EIDCIIER tSV4CLD

FLOW DIR62PJAPOST-ALC!DE)IT LIOIIID

ASID 6SS SLMDLISI6 D

Uft:T Vt I Et

~$ «lSI C»ee»hv et fv«1 IY\

leo)4$ IS )44

to\1st'vw f «4»0hhNC AII)toctscfoft IDLWISTE CDLLKCIID)ITAIffeSERVING SDDC LrsslpIIITAIION CtfehOCCTAIetat VT LOCATV0 IIIUepf V'I CCEhGTOIC~LETW)1'EL

I Urc))hh LI

~ $ 1IttFl 'I

I c D E E ..I. o

he» oar\WE» rveca41 PVWS ~Ilt

f«44 I~ VL)Ie Se ~

)en toa sale Es»

~ ea S owe LCEs»v «ave sea

I K „' I I

IL ' r '4

cC ICSC CC.I2 RAGS>

NVP hP()LarNvoe

L AC

14 HEI Or

12-5 I 4 I C-8

M IC1 h~

4 '«4«» e«rLree I wr Lve, Cr e la or 1 ~ rv»hofere«1' lr''I ~

9003090187"1

~ .L'

Page 371: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

~,

Cb 0

Page 372: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

A I 8 I 5 I F I G I

GBNKQLL NOT B>g)P)C-2) PNI>G

Ca L>IC

cowes+)

)ssI

~4

ava a cau

leI

Natl~S

C

~ ~ \Icaal

1«41Clar4Ncaa >Da~eeet e>v

14evl >AMwlewe

rcweu ta-

~e ~ 4

CROLle

rIIIIIC r SfsIC

IIC

IL

CALO Sat>PLCPALLCT

aal

L»»* e»e

ACC>DC/ty RA>/OtKfrLVKNTLCDNITDR

sfa

~Csct CL'I,PALLCT

I'

Is

IIIIIIIII

ctou VRA ta>D sco. r es DWC I S>oat,a ~rNDTC 'C

wt r -A"---1~ Stol)5I

$>wss a>LST ft) RtTVR>t CRDNlvTCR>u p.ASLL>ILC Stat to>l, ERP2500,

~, rtov vtvs)c) SlcDwo.t l>oer, ago

r SIL))ERS ES00,

SealsV.$>a 1sttacavaao NOTT 2

Alar>at>O

4 1stasacv RDD

aaov>alo)

~as ~

TI TD )usga>ll RALAatlt svclfu~~24~'UNIT E)

La ~ 4 elwtwvvevtaawae va eveewla

NDTCSIL1$ telIaccvc vs aa>reawe lrl.St Wet. IDR ccwc

aea paces 144>c w/Lt.>av> aw>$ c seRf Aas aat>c>cate I'tsa c

aao>salsctra ar aaeaLLN seeraalcccg) saaDr tree> vv tsa e>ea>a sara>LL

Lsaev o Late>ov cas Q'qWN DWLall swv'1'WK Vt

BY AEP— BY HUS

caaesaat>tw cas~ct Ca>t 1st Del,~I OK>ca/4

raAtcou Cata%1 ca'l r)P~ t> aaa lll~SsveC> 'ltl,

I I ~ ~

~el 1/et>11

le ~ )

Secl

o ~4)ee>545 a(C>AA>DA

I~I le w>e'0

(Lgg NOTC A)>TVP)

I ltSW)

CLsat>ell'alcac

LLlCt>e 1st

Ills'>1 uus cl)

Oeaaeev vl w p>')

BY S)US — BY AEP.

~~aIrpp

>I 4~ tcwu watt t

1OLISC

~urrOa>L s»pvt»t ea sa>ovc c>4$ $'4lrwa as vaeaDD>vs «selevoe> avNL as elc

Dc >t 1 ~ 11)t La>ae>ese

~)eaaeae wa >Wars «nvvaaeaawseeaa ra>elva ~ 14weeae 2saetl I DLL'1~

IIIII r s/sII SLNILC

PALLCT

~>44 S/ ~~4>e ~~ eee

t.»*.>ACCIDCNT RANCEKrrtvcuf ac)N)TDR

IIIII))

LCRLC CLStLILCT

II

J

~reaast ~ P>RDLeet catt ~I~ DWL~1 14>C C/I,

~ real>alllevc oul t)s

fest(CA>IT Oaut)N gfyt 5 paaccs)

~P>W, csCLwe>

CP

ee>aa ~ )COS cog/

la>el>14~ Vae earaw >ta)assr\4

Tceeaoceat vcaf Ttac>ND'octl >too sRDN VRA tcp LKK

~ ~

I'lwf>I'stoat,agoI NOTt 2

Seat I suoa 1>ass)CO

~SSOTO~ elit

(QQ1$

CP>oafIAR.)l S'I Rgt)RN t»CVA

N>ttea t>ettOC>tctSa>eats STAf>DN

ERS 0I. WSLRKKu)'

RDN VRA'll>OLCCT Dwf> I.s>DAT llo

1 svslERS BOO

$>ass ' tt-Iwatl4 uoTC2

~a. IS ~RcacN aoalor>ato)

Le Lee ~

L'l

PCCO)I

e.c. 1 ~ av >esCCASL ( ev" Wa

~ aaaw~

~etrts'to

selt acc>oc>tt 54>aea>vo 515 cfIA/5 IDRcavT lcC Dao >L 5>AC,O>l

teravtavLC >eDDLc oal tvtt>cvaatt Avo>DD>vapuasotactreapecotv>eec stvea 1

CSCCD)1C \ Dr>sc I Feoa 1 slrDTDOt P>aW 0 Dfls

gs'4 PD>>ON C>COOCN

Nc cc/c Lal wc4'SKI C >

e/1

CALO'1lttu Ss)tftu

ADDI)�>CN

lOIR)

let g N>CACICNTWCQC PO I tX

acre>

VOOI) KaaeeOL NL111

Cteau. Wastk PI/ROStpa CD>ty Dao Dr>Dst S>4>ael/C ~

vs&

LL I/t ID tuo'tae tacllsvcl)Kewta S>e OL stal eusl(FTCIC C 6 (U)5)T P 2)

~>Veeae 4 treatrt'

aa c» tea ovaN lv C>VL~

NITRDCTW PI/tog tt'C

Dwt 1st Oaala ' '4> C

lcLsp et$

lepuo

1 ~ I.Sl C

/C ~

'T)

~ C,It>PSI>

1 ~

~ So

A

tcctocsa )'Iafccs

le~ ~

ta

>Ict5)O

a casts

ISI Vs W u>)

HS '1 SA

PS 'SO>

SL Sayscrc>L ltatcw 4>1

Ce 1stgls awc Natl 4)

v>tcoolv llc Pass>us c/a

DlwwltaL>TLS trLtcc sll or>Os>ate.t/s

TVCLOOT PRK ST g DLSICNATIONFDRKICNCDISPO>ttuytogufta)CAt>ON~t>P4OKR )selt VNLESS OTNRR'Vl)SC ROTC D"

-L = I

~ r..'$5

r=p ."o

WW

I tc I) 6 r/

srAPERTURE

CARD

HA>>D DP l)AT Vile~ > 4 >C>v wvwot

L CRRT LPADVK yALVK )ONSKRSAPPEAR CN THIS Dtaw)NC. SKCSEPARATE VALVE trKNT>c)CA)puLIST TDR EqulyALENT pKSICN 6<NCR) I.uudCRS

TAC sc/ltdgtS upptr)CD TDRpgawotC u/>K AS IDLLP/tSI

TAC Nt: 2 Nst/V)C5 WAPPEARS AS: NSPIDSN

ROISTRVNKNT Rppr VaLVE uattcttlt NOT SHOWN ON DRAS/>>IC)SCEVALVE IDEN)tr)CAT>DN UST)DK Ctytp Ol APDINC TDs>sf tt/NKHT ss/udKR)

TCR St)CREOCPVLSCVIgpd )XLRLCDIIL/LSL~TKKAW

VKCXIW)IS)TEAN

2

~pw e we'>ea taesv~ 11 CWC Sll Pea,N aa>C ~ Ln.Daw>v wart a

4'aswat srL4't~el Cart. 1st DWCN SWC ~

1/1pW

Weo> aavrea caawaesa)

'lscop 'lca owaN Ia>C>L/1

a

V1111

stw>N waetR Dc>/t>ov ) ~>NIC Seac L/t

NS Sst sc.>pl

NO vera>LLSR>LA"

a>sew c/»saatev csee> ca/vpl~p'p~

1'S a)C LlS

osvootCLLI~ CLyatCDC-t)N)

( SK)S>AICCLASSIC)

taaeat>rt Sls O

WW eWW P We >Mew> a ae ar>etMDtcrpc tress Net>4 cset. ee> 4 ewewpve eewaa >wt p w at w w «Wee>w~ wa>a w we > a w > Ka aw ew waraw «e we w ae eewe ware> pa

pee eav» \> we a\ ~ eccl>ct ca» eawe we eawv eewww ~ w ww wr e>,aw p N N e>eave eae wwp>

Iso Available OnAperture Card

t>P>A/>4 O l4>CH>OW CLRCTNIC CO

DONALD C. COOKNVCKEAR FKA)fg

~ It>DCNlt >DDRCLR

D>L NO )2 5)a)C 6

FLOW D))LG'RAM

POST ACCIDE))T L)QV)DSAM)SL)SKG )NST>TVLCBNT 0

PA)56L

Weetatira Mera>a

0 T LCCI O))T LMPL)))G )4 UMPL)T T)KN(QC OSS ) CFC OC ~ l?.taC

ala~ ve Llt "r.-

)Sh

+-"> A

I, ~

K) . ~ I K. G I 0 I J I = K I~ I

I ~ O

" -- -c)0 0 3 0'90 ) 8 3. —.g5-'-—

Page 373: Rev 3 to 'DC Cook Nuclear Plant Unit 2 Inservice …Testing Method: (SLT-2) Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except

Ff

lo

g