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AMENDMENTNO. 24

SHEARON HARRIS )A)CLEAR POWER PLANT

Caf o) Ina Powor 3( Ll()ht Company

FINAL SAFETY ANALYSIS REPORT

GENERAL ARRANGFJAENT CONTAINMENTBUILDING SECTIONS

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TABLE 6!2.4-lCONTAiNMENT ISOLAT ON SYSTEM DATA

SHNPP FSAR

VALVE DATA

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HYDROGENANALYZER

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GL SO A

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6.2.4 —31b ~NDMENT NO- 40

881 031 026[

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I40

)40

40

40

SHNPP FSAR

6 ' ' COHBVSTIBLE GAS CONTROl. IN CONTAINt'fENT *

Following a maximum hypotheti.cal accident, hydrogen gas may be generatedi.nside Containment by reactions such as Zirconium metal wit:h water, corrosionof materials of construction, and radiolysis of aqueous solution f,n t:he coreand containment sump. This subsection describes t:he systems Lhat are providedi.n accordance with General Design Cri.teria 41 to conLrol the bu:Lldup ofhydrogen within the Contai.nment.

Four mechanisms for monitoring and controlling hydrogen inside the Cont:ii.menttaee considered in t: he SHNPP rlesign:

a) Hydrogen recombiners.

b) Containment hydrogen purge.

c) Containment hydrogen mixing and,

d) Containment'hydrogen monitoring.

The design basis for each of L'hese mechanisms is described in t:he followingsubsections.

6.2.5.1 Desi n Bases

6.2.5.1.1 Electric Hydrogen Recombiners

The following design bases apply to the electric hydrogen recombiners:

a) The hydrogen recombinees are designed to sustain al1 normal loads aswell as accident loads including sei.smic loads (safe shutdown earthquake) andtemperature and pressure transients feom a design basis loss-of-coolantaccMent.

b) The hydrogen recombinexs aee protected from damage by missiles or jetimpingement.

c) The hydrogen recombiners are located away fxom high velocity aiest:reams, such as the fan cooler exhausts, or are protected from the directimpingement of such high velocity air st:reams by suitable barriers, such aswalls or floors.

d) 'he hydrogen recombiners are designed foe a lifetime consist:ent wi.ththat of t:he plant.

e) All materials used in t:he hydrogen eecombiners aee compatible with L'he

environmental conditions inside t:he Containment: during normal operation andduring accident conditions.

f) The hydrogen recombiner capacity is such that the containment hydrogenconcentration will not exceed 4 peecent by volume utilizing t:he eadioactivLtyrelease model as 'indicated in NRC Regulatoxy Guide 1.7, "Control of

* Further information is contained i.n the THI Appendix

6.2.5-1Amendment No. 14

SIQIPP FSAR

Combustible Gas Concentrations in Containment Following a Loss-of-CoolantAccident."

6.2.5.1.2 Post Accident Hydrogen Purge System

The following design bases apply to the post accident hydrogen purge system.

a) The system up to the first isolation valve outside Containment isSafety Class 2, Seismic Category I, designed to retain its integrity and

operability under all conditions following a design basis loss-of-coolantaccident. The remainder of the system is not designed for safety design basissince it serves as a backup system to the hydrogen recombiners.

b) The system is designed to exhaust the air and hydrogen from theContainment and repLace it with air from the outside.

c) Functional and operational redundancy of the system is not provided, asthe system serves only as a diverse means of backup to the already redundantcontainment hydrogen recombiners. However, the system is capable ofcontrolling hydrogen inside Containment foLLowing a LOCA independent ofoperation of recombiners.

27

d) If purging is necessary following a LOCA, the system wiLL operate tomaintain the volume of hydrogen, generated by cladding-water reaction,radiolysis and corrosion below four percent by volume in the Containment toprevent a hydrogen explosion.

'

e) Since the control power is disconnected by a remotely operated keyLocked switch, the air-operated cbntainment hydrogen purge isoLation valveinside containment is "sealed closed" during normal plant operation, The

keyLock switch will restore the power and allow the remote manuaL opening ofthe vaLve from the main controL room. Valve status and keylock switchposition indication is provided in the main control room.

The outside containment isolation valves are normally Locked cLosed and aremanually operated locally.

f) All materials and equipment required by this system inside Containmentare compatible with the environmental conditions anticipated during normaloperation and accident conditions and are suitable for a lifetime consistentwith that of the plant.

6.2.5.1.3 Post Accident Hydrogen Monitoring System

The following design bases appLy to the post accident hydrogen monitoringsyst'm.

a) The Hydrogen Analyzer is classified as a Class 1E, Seismic Category Imonitoring instrument qualified to IEEE-323-1974 and is designed to retain itsintegrity and operability under all conditions following a design basisaccident.

6.2.5-2 Amendment No. 27

SHNPP FSAR

b) " 'The sample valves, containment penetration and piping up to andincluding the outermost containment isolation valves for the sample feedheader'nd sample return line are ASHE Section III, Safety Class 2, SeismicCategory I and are designed to retain their integrity and operability underall conditions following a design basis accidents

c) All materials and equipment required by this system are selected to becompatible with the environmental conditions anticipated during accidentoperation and are suitable for a lifetime consistent with that of the plant.

d) The system samples containment air, providing the means to measure thecontainment air hydrogen concentration and to alert the operator in the eventthat a high hydrogen concentration is detected, in accordance with therequirements of Regulatory Guide 1.7.

e) All containment isolation valves for the hydrogen analyzers arenormally open and fail closed on loss of electrical power. Means are providedto reopen valves, when required, after power is restored. In the event of acontainment isolation signal, valves 2SP-V301 SA-1 and 2SP-V349SA-1 close andisolate containment penetration 73B. Valves 2SP-V300 SA-1 and 2SP-V348 SA-1close to isolate penetration 73A. On power failure, all valves fail closed,insuring isolation.

The hydrogen analyzer cabinet, tag number AT-1SP-7438-SA, is qualified forpost-accident operation. The sample line coming from and going topenetrations 73A and 73B respectively, contain only safety train A associatedvalves. Likewise, containment penetrations 86A and 86B use only safetytrain B associated valves on the hydrogen analyzer sample lines.

As a result, if one safety train fails then the required redundancy for post-accident hydrogen sampling is still provided. If the associated valves failto close when they should close, safety is not compromised since the hydrogenanalyzer is qualified for post-accident operation.

f) The Hydrogen Analyzer System consists of two identical units which arecompletely'independent of each other and are powered from independent onsitesources. Therefore, assuming a single failure, process capability isavailable to monitor the hydrogen concentration in the Containment. SeeTable 6.2.5-7 which provides a failure modes and effects analysis.

g) The system is designed for remote-manual sampling capability with anintermittent cycle of Hydrogen indication for six (6) different sample

6. 2 ~ 5-3 Amendment No. 40

SHNPP FSAR

points. The Hydrogen Analyzer will have a continuous sampling and indicatingcapability for a single sample point. The sample point locations are asfollows:

1) Dome

2) Reactor Coolant Pump and Steam Generator lA

3,) Reactor Coolant Pump and Steam Generator 1B

4) Reactor Coolant Pump and Steam Generator 1C

5) Pressurizer

6) Area Below Flux Mapping Room Floor

These points are located on various elevations providing a broad coverage ofthe Containment for monitoring of Hydrogen Concentration in a Post LOCACondition.

h) Remote control, readout, alarm, and recording will be from the MainControl Room. An alarm will be. activated for the Hydrogen Analyzermalfunction, loss of power, and high H2 Concentration.

i) The H2 Analyzers will be capable of measuring in the 0-10 percent H2range by volume, with an accuracy of + 2.0 percent of full scale and a,sensitivity of 0.1 percent H2 by volume.

j) Provisions will be made for Containment air grab sample via RemoteSample Dilution Panel to be diluted, cooled, and transported to the laboratoryfor analyses.

The Remote Sample Dilution Panel is designed in accordance with the criteriastated in Regulatory Guide 1.97 Rev. 3 and NUREG-0737, Section II.B.3 to meetthe following requirements'.

1) To provide, with sufficient rapidity, a sample of containmentatmosphere, so that analysis can be completed within 3 hours from thetime of decision to take a sample, without requiring the use of anisolated auxiliary system.

2) To obtain samples suitable for analysis for hydrogen, and forgamma spectrum analysis for noble gases and iodines.

3) To obtain, and permit analysis of, a sample without a dose to anyperson exceeding the criteria of GDC-19 of Appendix A.to 10CFR50 (i.e.,5 rem whole body, 75 rem extremeties) assuming a fission productrelease per Regulatory Guide 1.4, Rev. 2.

4) To provide samples such that background radiation,wi11 be lowenough to permit sample analysis with an error of approximately afactor of two.

~

~

5) To be capable of providing at least one sample per day for sevendays and at least one sample per week for the duration of the accidentcondition.

6.2.5-4 Amendment No. 27

SIII<PP FSAR

6) To give designconsideration,'a)

provisions for purging, reducing plateout, and preventingblockage in sample Lines.

(b) samples that are representative of the containment atmospherefollowing a transient or accident.

(c) minimizing the volume of gas taken from containment andreturning residues to containment.

(d) providing ventilation exhaust from the panel filtered withcharcoal'and HEPA filters.

7) The RSDP is classified in Regulatory Cuide 1.97 Rev. 3 asCategory 3 which specifies "high quality commerciaL grade" const'ruction"selected to withstand the specific service environment." Thisequipment is, therefore, classified as Non-Nuclear Safety and isnon-seismic Category I. The valves isolating this system from theContainment Hydrogen Analyzer System are.,'Class LE and operated from aClass LE power source.

k) - Capability will be provided Eor obtaining samples under both positiveand negative containment pressure condition.

1) Proper shielding and other provisions wiL'1 be incorporated into thedesign to assure that personneL exposure does not exceed the Limits of CDC-19,and that the required radiological analysis can be performed on thecontainment air sample.

m) The system will have the capability to provide a 100 percent finalreading of hydrogen concentration in the containment within five minutes afterthe system has been activated.

1)2)3)

Warm up time — 1 minuteSample transit time to the sensor — 0.2 minutesTime to reach 100 percent of final reading after sample entersanalyzer " 3 minutes (2 minutes for 90 percent of final reading).

n) Turnover time for one sampLe, including stabil.ization, is threeminutes.

6.2.5.1.4 Containment Hydrogen Mixing

The following design basis applies to mechanisms or systems for mixing ofhydrogen bearing gases inside the reactor containment.

a) Local hydrogen concentrations inside the reactor containment shalL bemaintained at less than 4 percent by volume.

b) The Containment Cooling System which provides heat removal and activemixing of containment air meets the redundancy, environmental, seismic, andquality requirements described. in Section 6.2.2.1.

6.2.5-4aAmendment No. 27

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AMENDMENT NO. 42

SHEARON HARRIS NCLEARPOMER PLANT

Caro13naPower 5 Light Co.

FINAL SAFETY ANALYSIS REPQRT

CNTAIQlENT PRESSURE(OECLa Cn~.4)

FI6URE

6.2.1-302.

IOOO

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AMENDMENT NO. 42

SHEARON HARRISNUCLEAR POWER PLANT

CarolinaPower 5 Light Company

FINALSAFETY ANALYSISREPORT

CONTAINMENTWALLHEATTRANSFER COEFFICIENT

FIGURE

6.2.1-304

210

180

?'i%0

120

120 100 200 240 200

IllgKC)

AMENDMENT NO. 42

SHEARON HARRIS NUCLEARPOMER PLANT

Carol)naPowar h Light Co.

FINAL SAFETY ANALYSIS REPORT

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11.5.2 '.2Described in Detector e

TABLE 11 5 '-2EFFLUENT RADIATION MONITORS

cont d

TypicalSensitivit

Accuracy(X)

Typical NighAlarm Set oints Location Pouer Automatic Actuation

Reactor Auxiliary Bldg. Emerg.Exhaust A

1AV-3532A 8 Particulate (11 ' '.5.8) 10 -10Iodine (11.5.2.5.10)Noble Cas (11.5.2.5.10)

1.08x10 CPM/pCi Cs-137 +15

1.01x10 CPM/pCi I-1311.84xl0 CPH/pCi/cc Xe-133

5.1x10 9 pCi/cc2.89x10 pCi/cc3I4x10 pCi/cc

Duct off Line) None

Reactor Auxiliary Bldg. Emerg.Exhaust B

1AV-35328 .8

Condenser Vacuum Pump Effluents 1TV-3534 .9 Noble Cas (11.5.2.5.5) u t4.3x10 CPH/pCi/cc, Xe-133 1.02x10 pCi/cc

40

Secondary Naste Sample Discharge 21NS-3542 ~ 12 Liquid (11 ~ 5 ~ 2.5 ~ 7) 1.28x10 CPM/pCi/cc Cs-137 2 08x10 pCi/cc f LineOf Effluent Discharge Terminated

Naste Processing Building Exhaust 5

Naste Processing Building Exhaust 5A

Safety Related AC Bus

fg Instrumentation AC Bus

*1WV-3546

*1NV-3547

.13

~ 13

Particulate (11.5.2.5.8)Iodine (11.5.2 '.10)Noble Cas (11.5.2.5.10)

1.08x10 CPM/pCi Cs-1371,01x105 CPH/pCi I-131 &

1.84x10 CPH/pCi/cc Xe-133

1.36x10 pCi/cc7.7xl( pCi/cc &

Bx10 pCi/cc

Discharge from Cas Decay TanksTerminated

None

11-5-2-24

SI,APERTURE

CARD

Amendment No. 40

Aho Available OnAperture Card

I

88' 3y PP gg: > ~y

t'

7

PRES I DENTCHIEF EXECUT I VE

OFF I CER 4 CHA I RMAN

SR EXECUTIVE VICE PRESIDENTPOWER SUPPLY AND ENGINEERING

CONSTRUCT I ON GROUPS

SENIOR VICE PRESIDENTFOSIL GENERATION 6POWER TRAHSMISS ION

SENIOR VICE PRESIDENTOPERAT I ONS SUPPORT

GROUP

SENIOR VICE PRESIDENTNUCLEAR GENERATION

GROUP

MANAGERCORPORATE QUALITY

ASSURANCE DEPARTMENT

MANAGERMAIHTEHANCE SUPPORT

SECTION

VICE PRESIDENTOPERATIONS TRAINING AM3

TECl+IICAL SERVICES DEPA)TMENT

VICE PRESIDENTBRUNSW I CK l4KLEAR

PROJECT DEPARTMENT

VICE PRESIDENTTRANSMISSION

DEPARTMENT

MANAGERMATER I ALS MANAGEMENT

DEPARTMENT

V I CE PRES I DENTHARRIS t4KLEAR PROJECT

DEPARTMENT

VICE PRESIDENTFOSSIL OPERAT I ONS

DEPARTMENT

GENERAL MANAGERSYSTEM OPERAT I OHS

DEPARTMENT

MANAGERFOSSIL ENGINEERING 4

CONSTRUCTIONDEPARTMENT

MANANUCLEAR SAFETY

AND ENV I ROt4lENTALSERVICES DEPARTMENT

V I CE PRES IDENTt4KLEAR ENG I NEER I NG

DEPARTMENT

MANAGER

lLICENSING 6 NUCLEAR FUEL

DEPARTMENT

VICE PRESIDENTRO6INSON NUCLEAR

PROJECT DEPARTMENT

MANAGERHUCLEAR STAFf

SUPPORT SECT I OH

SIAPERTURE

CARDI

~o Avaifable OnA&rtumCard

8$ 03g pp gg $ ga,

AMENDMENT NO 40

SHEARON HARRIS NUCLEAR POWER PLANT

Carolina Power 5 Light CompanyFINALSAFETY ANALYSIS REPORT

OPERATIONS AND ENGINEERING 4.CONSTRUCT I ON ORGAN I ZAT I ON

FIGURE 13e1.1-1

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