Pacific Gas ard Eiectric Gempaai 77 8='-": Sl'> .

Sar, Francis".".. CA 9'106

i X ":iG-372-655

J2Hi". D.S".i'-'oe,e

Ve"o Pf c ~c ~ =q~

Geq e f.i~-:".:if „4. rue.'. i... v

June 28, 1990

PGhE Letter No. DCL-90-166

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskHashington, D.C. 20555

Re: Docket No. 50-275, OL-DPR-80Docket No. 50-323, OL-DPR-82Diablo Canyon Units 1 and 2Response to Generic Letter 90-04, Status of Implementation ofGeneric Safety Issues (GSIs)

Gentlemen:

Generic Letter 90-04, "Request for Information on the Status ofLicensee Implementation of Generic Safety Issues Resolved withImposition of Requirements or Corrective Actions," datedApril 25, 1990, requested that PGfmE perform a review and report onthe status of implementation of generic safety issues (GSIs). Theenclosure provides the implementation status of each GSI for DiabloCanyon Units 1 and 2, references to documentation, and comments, asrequired, for clarification.

Kindly acknowledge receipt of this material on the enclosed c'py ofthis letter and return it in the enclosed addressed envelope.

Sincerely,

J. D. Shi f rcc: A. P. Hodgdon

J. B. HartinP. P. NarbutS. A. RichardsH. RoodCPUCDiablo Distribution

Enclosure

3197S/0084K/DY/2232

PG&E L tter No. DCL-90-166

ENCLOSURE

STATUS OF IHPLEHENTATION OF GENERIC SAFETY ISSUES (GSIs)FOR DIABLO CANYON UNITS 1 AND 2

3197S/0084K

I

~ ~

FACILITY NAHE: Oiabl n n P w r Pl n ni 1DOCKET NO.: -27 -DPR-8LICENSEE: — Pa ifi a and El ri om an

(TEAT L~FLIQE~NEE IHPLEHENTATI N F ENERI AFETY I

I NPAN .

40 (8065)

41 (8058)

43 (8107)

51 (L913)

TTTL

Safety Concerns Associated WithPipe Breaks In The SNt Scram System

SN Scram Discharge Volume Systems

Reliability Of Air Systems

Improving the Reliability ofOpenCycle Service Water Systems

APPLI ABILITY

All BNRs

All NRs

All Plants

All Plants

TAT

I12/91

WENT

PQLE letters OCL-89-041, dated Feb. 21, 1989, andDCL-89-154, dated June 6, 1989, provided PGLE'sresponse to Generic Letter 88-14. The letterprovided PG4E's actions and schedule to implementthe GL 88-14 receanendations. NRC letter datedJune 12, 1989, provided acceptance of PGCE'sactions regarding GL 88-14. GL 88-14 actions arecompleted, however, PGCE is continuing an effort toidentify air system improvements for enhancedsystem performance. (Same status for Unit 2.)

PSLE letter OCL-90-027, dated Jan. 26, 1990,provided PQLE's plans and schedules regarding theestablishment of programs to implement GL 89-13recommendations. The connitments are beingcompleted consistent with the schedule provided inDCL-90-027 with expected completion of theUnit 1-only actions during the 4th refueling outageof Unit 1 (Nay 1991) and expected completion ofcoanon Units 1 and 2 actions during the 4threfueling outage of Unit 2 (December 1991). (Samestatus for Unit 2.)

67.3.3 (A017) Improved Accident Noni toring All Plants PQE letters of Sept. 9, 1983, and OCL-84-298,dated Sept. 4, 1984 supplemented by letter,OCL-85-088, dated Harch 1, 1985 provided PGCE'sresponse to Supplement 1 of NUREG-0737 sumnarizingcompliance with Regulatory Guide 1.97, Rev. 3 forUnit l. In letter OCL-86-086. dated Narch 27,1986, PGCE provided information regarding theunavailability of acceptable radioactivityconcentration monitors and boric acid charging flowmeters. In K4E letter OCL-90-037, dated Feb. 1,1990, KAE informed the NRC of installation of aqualified flowmeter in Unit l. (Same status forUnit 2.)

75 (8076) Item 1.1 - Post-Trip Review(Program Description andProcedure)

All Plants NC PME letters DCL-84-034, dated Feb. 1, 1984, andDCL-85-025, dated Jan. 24, 1985, provided PSLE'sresponse to this item. NRC letter datedNay 15, 1985, provided acceptance of PQE's actionsregarding this item. (Same status for Unit 2.)

See Attachment for Coding Definition31975/0084K-1

IP

1 I

FACILITY NAHE: Oiabl n on P Ev r PlanDOCKET NO.: $ -27 L-DPR-LICENSEE: P ifi a and E1 ri

g~IMPA~N.

ni 1

ya~n

IMSJLMM '"'" ' ll

RE LVEO NITH IH ITI ~NF RE IJIREHENT R ORRE TIVE A Tl N

TAT

75 (8085)

75 (8077)

75 (8086)

75 (L003)

75 (8078)

75 (8079)

75 (8087)

Item 1.2 - Post-Trip Reviev-Oata and Information Capability

Item 2.1 - Equipment Classifi-cation and Vendor InterfaceData and Information Capability(Reactor Trip System Components)

Item 2.2.1 - Equipment Classifi-cation for Safety-Related Components

Item 2.2.2 - Vendor InterfaceFor Safety-Related Components

Items 3.1.1 I 3.1.2 —Post-Haintenance Testing (ReactorTrip System Components)

Item 3.1.3 - Post-HaintenanceTesting-Changes to Test Require-ments (Reactor Trip SystemComponents)

Items 3.2.1 C 3.2.2 —Post-Haintenance Testing (All OtherSafety-Related Components)

All Plants

All Plants

All Plants

All Plants

All Plants

All Plants

All Plants

NC

E

9/90

NC

NC

PGEE letter DCL-84-242, dated June 27, 1984,provided PQE' response to this item. NRC letterdated June 25, 1984, provided acceptance of PQE'sactions regarding this item. (Same status forUnit 2.)

PQE letters DCL-85-151, dated April 18, 1985, andDCL-87-057, dated Har. 24, 1987, provided PQE'sresponse to this item. NRC letters datedOct. 27, 1986 and July 24, 1987, providedacceptance of PME' actions regarding this item.(Same status for Unit 2.)

PETE letter OCL-87-156, dated June 30, 1987,provided PGCE's response to this item. NRC letterdated Oct. 30, 1987, provided acceptance of PQERsactions regarding this item. (Same status forUnit 2.)

PGCE letter DCL-87-156, dated June 30, 1987,provided PGSE's response to this item. GenericLetter 90-03 provided a relaxation of the NRCStaff' position on this item. PQE's response isdue to the NRC by Sept. 25, 1990. (Same status forUnit 2.)

PQE letters OCL-85-002, dated Jan. 2, 1985, andDCL-85-151, dated April 18, 1985, provided PQLEEsresponse to these items. NRC letter datedApril 10, 1986, provided acceptance of PQE'sactions regarding these items. (Same status forUnit 2.)

PGEE letters OCL-85-002, dated Jan. 2, 1985, andOC-88-115, dated April 18, 1985. provided PGCE'sresponse to this item. NRC letter datedJune 26, 1986, provided acceptance of PQE'sactions regarding this item. (Same status forUnit 2.)

K4E letter OCL-86-074, dated Harch 20, 1986,provided PGEE's response to these items. NRC letterdated Oct. 21, 1986, provided acceptance of PGCE'sactions regarding these items. (Same status forUnit 2.)

75 (8088) Item 3.2.3 - Post-HaintenanceTesting-Changes to Test Require-ments (All Other Safety-RelatedComponents)

*See Attachment for Coding Definition

3197S/0084K-2

All Plants PQE letter OCL-86-074, dated Harch 20, 1986,provided PGAE's response.to this item. NRC letterdated June 26, 1986, provided acceptance of PGLtE'sactions regarding this item. (Same status forUnit 2.)

\

FACILITY NAHE: Oi bl n n P w r Pl n ni 1

DOCKET NO.: -27 -DPR-LICENSEE: Pa ifi nd El ri an

Q~IHPA~N.

TAT F LI EN EE IHPLEHENTATI N F ENERI SAFETY I E

RE LVEO WITH IH ITI N F RE IREHENT R DRRECTIVE A TI N

TAT WENT

75 (8080)

75 (8081)

75 (8082)

75 (8090)

75 (8091)

75 (8092)

Item 1.1 - Reactor Trip SystemReliability (Vendor-RelatedHodifications)

Items 1.2.1 & 4.2.2 - ReactorTrip System Reliability-Haintenance and Testing(Preventive Haintenance andSurveillance Program forReactor Trip Breakers)

Item 4.3 - Reactor Trip SystemReliability - Design Hodifications(Automatic Actuation of Shunt TripAttachment for Westinghouse and B&WPlants)

Item 4.3 - Reactor Trip SystemReliability - Tech Spec Changes(Automatic Actuation of ShuntTrip Attachment for Westinghouseand 8&W Plants)

Item 4.4 —Reactor Trip SystemReliability (Improvements inHaintenance and Test Proceduresfor B&W Plants)

Item 4.5.1 - Reactor Trip SystemReliability-Diverse Trip Features(System Functional Testing)

All Plants

All PWRs

All W and B&W

Plants

All 'W & B&WPlants

All B&W Plants

All Plants NC

PG&E letter dated Hov. 7, 1983, provided PG&E'sresponse to this item. NRC letter datedJuly 8, 1985, provided acceptance of PG&E's actionsregarding this item. (Same status for Unit 2.)

PG&E letters dated Nov. 7, 1983, OCL-85-070,dated Feb. 21, 1985, and OCL-85-151, datedApril 18, 1985, provided PG&E's response to theseitems. OCL-88-132, dated Hay 17, 1988, providedadditional information for Item 4.2.1. NRC letterdated June 24, 1985, provided acceptance of PG&E'sactions regarding these items. (Same status forUnit 2.)

PG&E letters dated Dec. 20, 1983, KL-84-194,dated Hay 24, 1984, OCL-84-211, dated June 6, 1984,DCL-84-241, dated June 27, 1984, DCL-84-347, datedNov. 7, 1984, KL-86-336, dated Hov. 20, 1986, andDCL-88-298, dated Oec. 9, 1988, provided PG&E'sresponse to this item. NRC letters datedHay 16, 1984 and Jan. 6, 1989, provided acceptanceof PG&E's actions regarding these items. (Samestatus for Unit 2.)

PG&E letters DCL-84-194, dated Hay 21, 1984,DCL-84-210, dated June 6, 1984, OCL-85-360,dated Dec. 6, 1985, KL-88-307, dated Dec. 19, 1988,and KL-89-074, dated Har. 23, 1989, providedPG&E's response to this item. NRC letters datedHay 16, 1984 and Jan. 6, 1989, provided acceptanceof PG&E's actions regarding this iten. (Samestatus for Unit 2.)

PG&E letters OCL-84-241, dated June 27, 1984,OCL-84-347, dated Hov. 7, 1984, DCL-85-025,dated Jan. 24, 1985, and OCL-85-151, datedApr. 18, 1985, provided PG&E's response to thisitem. NRC letter dated July 8, 1985, providedacceptance of PG&E' actions regarding this item.(Same status for Unit 2.)

See Attachment for Coding Definition3197S/0084K-3

~'

FACILITY NAME: Oi bl n n P w r Pl n ni 1

DOCKET NO.: -27 -OPR-LICENSEE: P ifi nd El ri an

TAT F I EN EE IHPLEMENTATI N F ENERI FETY I E

RE LVED MITM IM ITI N F RE IREHENT R RRE TIVE A Tl N

ggQHP~AN

75 (8093)

86 (8084)

93 (8098)

Items 4.5.2 C 4.5.3 - Reactor TripSystem Reliability - Test Alterna-tives and Intervals (System FunctionalTesting)

Long Range Plan for Dealingwith Stress CorrosionCracking in BVR Piping

Steam Binding of AuxiliaryFeedwater Pumps

APPLI ABILITY

All Plants

All Bus

All RlRs

TAT

NC

NT

PQLE letters dated Nov. 7, 1983 and OCL-84-241,dated June 27, 1984, provided PGSE's response toItem 4.5.2. PQE letter DCL-84-364, datedNov. 30, 1984, provided PGCE's response toItem 4.5.3. NRC letter dated Har. 18, 1987,provided acceptance of PGSE's actions regardingItem 4.5.2. NRC letter dated Hay 30, 1989,provided acceptance of PQLE's actions regardingItem 4.5.3. (Same status for Unit 2.)

PGEE letters DCL-86-047, dated Feb. 25, 1986 andOCL-88-135, dated Hay 23, 1988, responded toGL 85-01 and GL 88-03 respectively. NRC letterdated Feb. 23, 1989, indicated that PME's responseto GL 88-03 was satisfactory and that procedureimplementation had been verified by NRC Region V.(Same status for Unit 2.)

99 (L817) RCS/RMR Suction Line ValveInterlock on ROs

All Pcs I5/91

PGLE letter DCL 87-187, dated Aug. 4, 1987,submitted KAP-11117 which provided justificationfor removal of the RMR System Autoclosure Interlock(ACI) Function. NRC letter dated February 17,1988, provide the NRC Staff's safety evaluation andacceptance for removal of the ACI. Removal of theACI and procedural enhancements have been completedfor Unit l.PQLE letter OCL-87-233, dated Sept. 18, 1987,responded to GL 87-12 regarding loss of RMR Wilethe RCS is partially filled. PG4E lettersDCL-89-005, dated Jan. 6, 1989, and DCL-89-030,dated Feb. 6, 1989, responded to GL 88-17 regardingloss of decay heat removal and expeditious actionsand prograxined enhancements. NRC letter datedApril 26, 1989, provided acceptance of PQLE'sexpeditious actions and provided coeaents on PGLE'sactions. Provision for Unit 1 RHR pump motorcurrent trending is scheduled for installationduring the fourth refueling outage (Hay 1991).

See Attachment for Coding Definition31975/0084K-4

FACILITY NAHE: Di bl n n P BB r Pl n ni 1

DOCKET NO.: -27 -DPR-

~IHPA N .

TAT F LI EN E IHPLEHENTATI N F ENERI AFETY IRE LVED WITH IH ITI N F RE~IREHENT R RRE TIVE~ATI~N

APPIPPABI TY TAT

124 Auxiliary Feedwater SystemReliability

AN0-182, Rancho NASeco, PrairieIsland 162,Crystal River-3,Ft. Calhoun

A-13 (8017) Snubber Operability Assurance-Hydraulic Snubbers

A-13 (8022) Snubber Operability Assurance-Hechanical Snubbers

A-16 (0012) Stem Effects on WR CoreSpray Distribution

A-35 (8023) Adequacy of Offsite PeterSystems

All Plants

All Plants

Oyster Creek8 NHP-1

All Plants

NC

NC

The Units 1 and 2 Combined Technical Specifications.issued Aug. 26, 1985. Specification 3/4.7.7provide operability and surveillance requirementsfor Diablo Canyon consistent with the WestinghouseStandard Technical Specifications. (Same statusfor Unit 2.)

The Units 1 and 2 Combined Technical Specifications,issued Aug. 26, 1985. Specification 3/4.7.7provide operability and surveillance requi.rementsfor Diablo Canyon consistent ~1th the MestinghouseStandard Technical Specifications. (Same statusfor Unit 2.)

PG6E letters dated Jan. 24, 1978, June 13, 1978,and Oct. 4, 1978, provided infomation regardingsystem protection for degraded voltage conditions.(Same status for Unit 2.)

8-10

8-36

Behavior of NN Hark IIIContainments

Develop Design, Testing andMaintenance Criteria forAtmosphere Cleanup SystemAir Filtration and AdsorptionUnits for Engineered SafetyFeatures Systems and forNormal Ventilation Systems

All SIR Hark IIIPlants

All Plants withOL ApplicationsAfter 4/1/80

8-63 (8045) Isolation of Le< PressureSystems Connected to the ReactorCoolant System PressureBoundary

See Attachment for Coding Definition31975/0084K-5

All Plants P(4E letters DCL-85-320. dated Oct. 11, 1985,OC-88-003, dated Feb. 13, 1986, DCL-86-238, datedAug. 12, 1986, and DC-88-112, dated June 8, 1987,provided information regarding periodic testing ofRCS pressure isolation valves in accordance withTS 4.4.6.2. NRC letter dated July 27, 1987. issuedAmendment No. 16 for Unit 1 to include additionalvalves in TS Table 3.4-1. (Same status for Unit 2.)

0~ i

FACILITY NAHE: Di bl n n P w r Pl n ni 2DOCKET NO ~ .'- 2 -OPR- 2LICENSEE: P ifi nd El ri an

'!' '"—'"'"'"'a-'JLJ"""RE LVEO N TH IH ITI N F RE IREHENT R RRE TIVE A TI N

HP~AN .

40 (B065)

41 (8058)

43 (8107)

51 (L913)

Safety Concerns Associated WithPipe Breaks In The SN Scram System

WR Scram Discharge Volume Systems

Reliability Of Air Systems

Improving the Reliability ofOpen-Cycle Service Mater Systems

A~PPLI ABILITY

All BWRs

All Bus

All Plants

All Plants

TAT *

I12/91

PQE letters OCL-89-041, dated Feb. 21, 1989, andDC-88-115, dated June 6, 1989, provided PQE'sresponse to Generic Letter 88-14. The letterprovided PGCEBs actions and schedule to implement ~the GL 88-14 reconnendations. NRC letter datedJune 12, 1989, provided acceptance of PGCE'sactions regarding GL 88-14. GL 88-14 actions arecompleted, however, PGSE is continuing an effort toidentify air system improvements for enhancedsystem performance. (Same status for Unit 1.)

PGLE letter OCL-90-027, dated Jan. 26, 1990,provided PGCE's plans and schedules regarding theestablishment of programs to implement GL 89-13recannendations. The comi tments are beingcompleted consistent with the schedule provided inOCL-90-027 with expected completion of the Unit 2and conan Units 1 and 2 actions during the 4threfueling outage of Unit 2 (December 1991). (Samestatus for Unit 1.)

67.3.3 (A017) Improved Accident Honi toring All Plants PQE letters of Sept. 9, 1983, and OCL-84-298,dated Sept. 4, 1984 supplemented by lettersOC-88-002, dated Jan. 25, 1984, and OCL-85-243,dated July 18, 1985, provided PQE's response toSupplement 1 of NUREG-0737 sumariaing compliancewith Regulatory Guide 1.97, Rev. 3 for Unit 2. Inletter OCL-86-086, dated Harch 27, 1986, PQEprovided information regarding the unavailabilityof acceptable radioactivity concentration monitorsand boric acid charging flow meters. In PQEletter OCL-90-121, dated Hay 7, 1990, PQE informedthe NRC of installation of a qualified flowmeter inUnit 2. (Same status for Unit 1.)

75 (B076) Item 1.1 - Post-Trip Revie~(Program Description andProcedure)

All Plants NC PGSE letters DCL-84-034. dated Feb. 1, 1984, andOCL-85-025, dated Jan. 24, 1985, provided PQE'sresponse to this item. NRC letter datedHay 15, 1985, provided acceptance of PQE's actionsregarding this item. (Same status for Unit 1.)

See Attachmen t for Codi ng Def ini t i on

31975/0084K-1

~ ~

FACILITY NAME'. D~ibl ~e~non P w r Plan niDOCKET NO.: ~323~0L-OPR-82LICENSEE: Pa ifi nd El ri om ~an

~TAT ~FLI~EN EE INPLENENTATI~N F ENERI AFETY I E

ggQN~PA N ~75 (8085)

75 (8077)

75 (8086)

75 (L003)

75 (8078)

75 (8079)

75 (8087)

75 (8088)

Item 1.2 - Post-Trip Review-Data and Information Capability

Item 2.1 - Equipment Classifi-cation and Vendor InterfaceData and information Capability(Reactor Trip System Components)

Item 2.2.1 - Equipment Classifi-cation for Safety-Related Components

Item 2.2.2 - Vendor Interfacefor Safety-Related Components

Items 3.1.1 C 3.1.2 - Post-Haintenance Testing (ReactorTrip System Components)

Item 3.1.3 —Post~intenanceTesting-Changes to Test Require-ments (Reactor Trip SystemComponents)

Items 3.2.1 C 3.2.2 - Post-Haintenance Testing (All OtherSafety-Related Components)

Item 3.2.3 - Post-HaintenanceTesting-Changes to Test Require-ments (All Other Safety-RelatedComponents)

APP I ABILITY

All Plants

All Plants

All Plants

All Plants

All Plants

All Plants

All Plants

All Plants

TAT

NC

E9/90

PQE letter OCL-84-242, dated June 27, 1984,provided PQE' response to this item. NRC letterdated June 25, 1984, provided acceptance of PQE'sactions regarding this item. (Same status forUnit 1.)

PGCE letters OCL-85-151, dated April 18, 1985, andDCL-87-057, dated Par. 24, 1987, provided PQE'sresponse to this item. NRC letters datedOct. 27, 1986 and July 24, 1987, providedacceptance of PQLE's actions regarding this item.(Same status for Unit 1.)

PG4E letter OCL-87-156, dated June 30, 1987,provided PGSE's response to this item. NRC letterdated Oct. 30. 1987, provided acceptance of PGEE'sactions regarding this iten. (Same status forUnit 1.)

PQE letter OCL-87-156, dated June 30, 1987,provided K4E's response to this item. GenericLetter 90-03 provided a relaxation of the NRC

Staff's position on this item. PQE's response isdue to the NRC by Sept. 25, 1990. (Same status forUnit 1.)

PQE letter DCL-85-151, dated April 18, 1985,provided PQE's response to these items. NRC

letter dated April 10, 1986, provided acceptance ofPQE's actions regarding these items. (Same statusfor Unit 1.)

KAE letter DCL-85-151, dated April 18, 1985,provided PQE's response to this item. NRC letterdated Narch 16, 1987, provided acceptance of PQE'sactions regarding this item. (Same status .forUnit 1.)

PGCE letter DCL-86-227, dated Aug. 1, 1986,provided PGLE's response to this item. NRC letterdated Oct. 21. 1986, provided acceptance of PQE'sactions regarding this item. (Same status forUnit 1.)

PCAE letter OCL-86-227, dated Aug. 1, 1986,provided PQE's response to this item. NRC letterdated Narch 16, 1987. provided acceptance of PQE'sactions regarding this item. (Same status forUnit 1.)

See Attachment for Coding Definition31975/0084K-2

0

FACILITY NAHE: i bl n n P r Pl n ni 2KBXEi8- '—

LICENSEE: P ifi nd El ri a~n

TAT F LI EN EE INPLEHE~NTATI M F ENERI AFETY I E

A~ELVER TIITH IIIP ITI N I'E IRENENT R RRE TIVE A TI M

HPA N .

75 (8080)

75 (8081)

75 (8082)

75 (8090)

75 (8091)

75 (8092)

Item 4.1 - Reactor Trip SystemReliability (Vendor-RelatedHodifications)

Items 4.2.1 4 4.2.2 - ReactorTrip System Reliability-Haintenance and Testing(Preventive Maintenance andSurveillance Program forReactor Trip Breakers)

Item 4,3 - Reactor Trip SystemRel iabi1 i ty - Desi gn Hodi fica tions(Automatic Actuation of Shunt TripAttachment for Mestinghouse and 8&8Plants)

Item 4.3 - Reactor Trip SystemReliability - Tech Spec Changes(Autonatic Actuation of ShuntTrip Attachment for Westinghouseand B4V Plants)

Item 4.4 - Reactor Trip SystemReliability (Improvements inHaintenance and Test Proceduresfor SCN Plants)

Item 4.5.1 —Reactor Trip SystemReliability-Diverse Trip Features(System Functional Testing)

All Plants

All PMRs

All N and BLMPlants

All N 8 BENPlants

All BEN Plants

All Plants

TAT

NC

NC

ENT

PGCE letter dated Nov. 7, 1983, provided PGTE'sresponse to this item. NRC -letter datedJuly 8, 1985, provided acceptance of PQE's actionsregarding this item. (Same status for Unit 1.)

PQLE letters dated Nov. 7, 1983, DCL-85-070,dated Feb. 21, 1985, and DCL-85-151, datedApril 18, 1985, provided PG6E's response to theseitems. DCL-88-132, dated Hay 17, 1988, providedadditional information for Item 4.2.1. NRC letterdated June 24, 1985, provided acceptance of PGCE'sactions regarding these i tems. (Same status forUnit 1.)

PRE letters dated Dec. 20, 1983, OCL-84-.194,dated Hay 24, 1984. DCL-84-211, dated June 6, 1984,OCL-84-24'1, dated June 27, 1984. DCL-84-347, datedNov. 7, 1984, OCL-86-336, dated Nov. 20, 1986, andOCL-88-298, dated Dec. 9, 1988, provided PG4E'sresponse to this item. NRC letters datedHay 16, 1984 and Jan. 6, 1989, provided acceptanceof PGtEEs actions regarding these items. (Samestatus For Unit 1.)

K4E letters OCL-84-194, dated Hay 24, 1984,OCL-85-360, dated Dec. 6, 1985, DCL-88-307, datedOec. 19, 1988, and OCL-89074, dated Har. 23, 1989,provided ALE's response to this item. NRC lettersdated Hay 16, 1984 and Jan. 6, 1989, providedacceptance of PGSE's actions regarding this item.(Same status for Unit 1.)

PGEE letters OCL-84-241, dated June 27, 1984,OCL-84-347, dated Nov. 7, 1984, OCL-85-025,dated Jan. 24, 1985, and OCL-85-151, datedApr. 18, 1985, provided PGLE's response to thisitem. NRC letter dated July 8. 1985, providedacceptance of PQE's actions regarding this item.(Same status for Unit 1.)

See Attachment for Coding Definition3197S/0084K-3

I

FACILITY NAHE: Oi bl n n P w r Pl n niDOCKET NO.: - 2 L-OPR- 2LICENSEE: Pa ifi and El ri n

TAT F LI EN EE IHPLEHENTATI N F NERI AFETY I E

RE LVEO MITH IH ITI N F RE IREHENT R RRE TIVE A TI N

~I~MP~AN~75 (8093)

86 (8084)

93 (8098)

99 (L817)

Items 4.5.2 4 4.5.3 - Reactor TripSystem Reliability - Test Alterna-tives and Intervals (System FunctionalTesting)

Long Range Plan for Dealingwith Stress CorrosionCracking in WR Piping

Steam Binding of AuxiliaryFeedwater Pumps

RCSflNR Suction Line ValveInterlock on WRs

APPLI ABILITY

All Plants

All SNs

All PMRs

All WRs

TAT *

NC PQLE letters dated Nov. 7, 1983 and DCL-84-241,dated June 27, 1984, provided PQE's response toItem 4.5.2. PGCE letter OCL-84-364. datedNov. 30, 1984, provided PQLE's response toItem 4.5.3. NRC letter dated Har. 18, 1987,provided acceptance of PGLE's actions regardingItem 4.5.2 ~ NRC letter dated Hay 30, 1989,provided acceptance of PGCE's actions regardingItem 4.5.3. (Same status for Unit 1.)

ALE letters DCL-86-047, dated Feb. 25, 1986 andOCL-88-135, dated Hay 23, 1988, responded toGL 85-01 and GL 88-03 respectively. NRC letterdated Feb. 23, 1989, indicated that PGEE's responseto GL 88-03 was satisfactory and that procedureimplementation had been verified by NRC Region V.(Same status for Unit 1.)

PGCE letter OCL 87-187, dated Aug. 4, 1987,submitted KAP-11117 which provided )ustificationfor removal of the RHR System Autoclosure Interlock(ACI) Function. NRC letter dated February 17,1988, provide the NRC Staff's safety evaluation andacceptance for removal of the ACI. Removal of theACI and procedural enhancements have been completedfor Unit 2.

PQE letter OCL-87-233, dated Sept. 18, 1987,responded to GL 87-12 regarding loss of RHR whilethe RCS is partially filled. PQE lettersOCL-89-005, dated Jan. 6, 1989, and DCL-89-030,dated Feb. 6, 1989, responded to GL 88-17 regardingloss of decay heat removal and expeditious actionsand prograxxned enhancements. NRC letter datedApril 26, 1989, provided acceptance of PQLE'sexpeditious actions and provided ceenents on PME'sactions'

See Attachment for Coding Definition3197St0084K-4

P

FACILITY NAKE: i bl n P w r Pl nDOCKET NO.: - -DPLICENSEE: P i fi nd El ri

ni

an

TAT F I EN EE IHPLEHENTATI N F ENERI FETY I E

RE LVED MITH IH ITI N F RE UIREHENT R RRE TIVE A T N

HPA N

124 Auxiliary Feedwater SystemRel iabi1 i ty

APP I BILITY

AN0-182, RanchoSeco, PrairieIsland 152,Crystal River-3,Ft. Calhoun

TAT HH NT

A-13 (8017) Snubber Operabili ty Assurance-Hydraulic Snubbers

A-13 (8022) Snubber Operability Assurance-Hechanical Snubbers

A-16 (D012) Stem Effects on BN CoreSpray Distribution

A-35 (8023) Adequacy of Offsite PowerSystems

All Plants

All Plants

Oyster Creek8 NHP-1

All Plants

NC

NC

The Units 1 and 2 Combined Technical Specifications.issued Aug. 26, 1985. Specification 3/4.7.7provide operability and surveillance requirementsfor Diablo Canyon consistent with the WestinghouseStandard Technical Specifications. (Same statusfor Unit 1.)

The Units 1 and 2 Combined Technical Specifications,issued Aug. 26, 1985. Specification 3/4.7.7provide operability and surveillance requitementsfor Diablo Canyon consistent with the Nesti'nghouseStandard Technical Specifications. (Same statusfor Unit 1.)

PGLE letters dated Jan. 24, 1978, June 13, 1978,and Oct. 4, 1978, provided information regardingsystem protection for degraded voltage conditions.(Same status for Unit 1.)

8-10

8-36

Behavior of BN Hark IIIContainments

Develop Design, Testing andHaintenance Criteria for-Atmosphere Cleanup SystemAir Filtration and AdsorptionUnits for Engineered SafetyFeatures Systems and forNormal Ventilation Systems

All SN Hark III NAPlants

All Plants withOL ApplicationsAfter 4/1/80

8-63 (B045) Isolation of Low PressureSystems Connected to the ReactorCoolant System PressureBoundary

See Attachment for Coding Definition3197S/0084K-5

All Plants PQE letters DCL-85-320, dated Oct. 11, 1985,DCL-86-033, dated Feb. 13, 1986, OCL-86-238, datedAug. 12, 1986, and DCL-87-129, dated June 8, 1987,provided information regarding periodic testing ofRCS pressure isolation valves in accordance withTS 4.4.6.2. NRC letter dated July 27, 1987, issuedAmendment No. 15 for Unit 2 to include additionalvalves in TS Table 3.4-1. (Same status for Unit 1.)

Attachment

l. NA - GSI 1s not applicable.

2. NC - GSI 1s applicable but no changes were necessary to implement theresolution, or the GSI 1mplementation was completed prior to issuance ofthe operating license and no post-licensing changes were necessary.

3. C - GSI is applicable; submittal of information and/or changes werenecessary and such submittals were made or changes are complete.

4. I - GSI is applicable and changes were necessary but such changes are notyet fully implemented.

5. E - Implementation guidance for a resolved GSI was issued recently and isstill being evaluated.

3197S/0084K

0 l ~

~ rC

FACILITY NAME: Diablo Canyon Unit 1DOCKET NO.: 50-275LICENSEE: Pacific Gas and Electric Company

GSI Status Summary

ENCLOSURE 2

GSI/MPANo.

40 (B065)

Title

Safety ConcernsAssociated WithPipe Breaks In TheBWR Scram System

Licensee StaffStatus StatusDetermination Determination Remarks

BWRs Only

41 (B058)

43 (8107)

51 (L913)

BWR Scram DischargeVolume Systems

Reliability OfAir Systems

Improving theRel iabi 1 ity ofOpen-Cycle Servi ceWater Systems

C (06/90)

I (12/91)

NA

C (06/90)

I (12/91)

BWRs Only

Modifications to meet GL 88-14are complete.

Unit 1 modifications to becompleted 05/91. Unit 2 andcommon area modifications tobe completed 12/91.

67.3.3 (A017) Improved AccidentMonitoring

C (02/90) gualified flowmeter installed.Staff position on this issue isbeing re-evaluated.

75 (B076) Item 1.1 - Post-TripReview (ProgramDescription andProcedure)

No hardware changes required.

l

eA

)

GSI/HPANo.

75 (8085)

Titie

Item 1.2 - Post-TripReview - Data andInformation Capability

Licensee StaffStatus StatusDetermination Determination

NC

Remarks

78 (8077) Item 2.1 - EquipmentClassification andVendor Interface(Reactor TripSystem Components)

C (03/87) C (03/87)

75 (B086) Item 2.2.1 - Equipment C (06/87)Classification forSafety-RelatedComponents

C (06/87)

75 (L003)

75 (8078)

Item 2.2.2 - VendorInterface forSafety-RelatedComponents

Items 3.1.1 & 3.1.2-Post - MaintenanceTesting (Reactor TripSystem Components)

E (09/90)

NC

E (09/90) PG&E response to GL 90-03 isscheduled to be submitted onSeptember 25, 1990.

<e

-3-

GSI/HPANo.

75 (B079)

Title

Item 3.1.3 - Post-Maintenance Testing-Changes to Test Require-ments (Reactor TripSystem Components)

NC

Licensee StaffStatus StatusDetermination Determination Remarks

75 (B087) Items 3.2.1 II 3.2.2 - C (03/86)Post-MaintenanceTesting (All OtherSafety-RelatedComponents)

C (03/86)

75 (8088)

75 (B080)

Item 3.2.3 - Post-MaintenanceTesting-Changes toTest Requirements (AllOther Safety-RelatedComponents)

Item 4.1 - ReactorTrip SystemReliability (Vendor-Related Modifications)

C (03/86) C (03/86)

GSI/MPANo. Title

LicenseeStatusDetermination

StaffStatusDetermination Remarks

75 (B081)

75 (B082)

75 (B090)

Items 4.2.1 & 4.2.2-Reactor Trip SystemReliability - Maintenanceand Testing (PreventativeMaintenance andSurveillance Program forReactor Trip Breakers)

Item 4.3 - Reactor TripSystem Reliability-Design Modifications(Automatic Actuationof Shunt Trip Attachmentfor Westinghouse and B&W

Plants)

Item 4.3 - Reactor TripSystem Reliability-Tech Spec Changes(Automatic Actuation ofShunt Trip AttachmentFor Westinghouse andB&W Plants)

C (05/88) C (05/88)

C (12/88) C (12/88)

C (03/89) C (03/89)

GSI/MPANo. Title

LicenseeStatusDetermination

StaffStatusDetermination Remarks

75 (B091)

75 (B092)

75 (B093)

86 (B084)

Item 4.4 - Reactor TripSystem Reliability(Improvements inMaintenance and TestProcedures for BOW Plants)

Item 4.5.1 - ReactorTrip SystemReliability-DiverseTrip Features (SystemFunctional Testing)

Items 4.5.2 8 4.5.3-Reactor TripSystem Reliability-Test Alternativesand Intervals (SystemFunctional Testing)

Long Range Plan forDealing with StressCorrosion Crackingin BWR Piping

NC

NA

NC

NA

BSW plants only.

BWRs only.

"T

.v

GS I/MPANo.

93 (B098)

99 (L817)

124

A-13 (B017)

A-13 (B022)

Title

Steam Binding ofAuxiliary FeedwaterPumps

RCS/RHR SuctionLine YalveInterlock on PWRs

Auxi liary FeedwaterSystem Reliability

Snubber OperabilityAssurance-Hydraul ic Snubbers

Snubber OperabilityAssurance - MechanicalSnubbers

LicenseeStatusDetermination

C (05/88)

I (05/91)

NA

NC

NC

StaffStatusDetermination

C (05/88)

I (05/91)

Remarks

Provisions for RHR pump motorcurrent trending will beinstalled 05/91.

Not applicable to plants withthree AFW pumps.

Covered in combined tech specsissued with Unit 2 full poweroperating license (08/26/85).

Covered in combined tech specsissued with Unit 2 full poweroperating license (08/26/85).

A-16 (0012)

A-35 (B023)

Steam Effects on BWRCore SprayDistribution

Adequacy of OffsitePower Systems

NC

BWRs only.

-7-

GS I/MPANo.

B-10

'0 8-36

Title

Behavior of BWR

Mark IIIContainments

Develop Design,Testing andMaintenance Criteriafor AtmosphereCleanup System AirFiltration andAdsorption Unitsfor Engineered SafetyFeatures Systems andfor Normal VentilationSystems

Licensee StaffStatus StatusDetermination Determination

NA

Remarks

BWR Mark III plants only.

Not applicable to plants withOL application tendered after04/01/80. Diablo Canyon OLapplication tendered in 1973.

B-63 (B045) Isolation of LowPressure SystemsConnected to theReactor Coolant SystemPressure Boundary

C (07/87) C (07/87)

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