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I'EQUL
Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
>Q ACCESSION NBR: 86061102b0 DOC. DATE: 86/06/04 NOTARIZED: NO DOCKET 0FACIL: 50-400 Sheav'on Hav v'is Nucleav'owev Planti Unit ii Carolina 05000400
AUTH. NAj'fE AUTHOR AFFILIATIONZINMERNANiS. R. Cav olina Power 5 Light Co.
RECIP. NAI'lE RECIPIENT AFFILIATIONDENTON> H. R. - Office of Nuclear Reactor. Reguiationi Directov'post 851125
SUBJECT: Forwav'ds mav ked-up FSAR Section 6. 2. 4 v e containmentisolation valves. FSAR thrill be formallg v evised in futuv eamend ~
DISTRIBUTION CODE: B001D COPlES RECEIVED: LTR ENCL SI 2E:TITLE: Licensing Submittal: PSAR/FSAR Amdts 8r Related Cov'respondence
NOTES: Application for pev mit renewal filed. 05000400
RECIPIENTID CODE/NANE
PWR-A ADTSPWR-A EICSBPWR-A PD2 LABUCKLEY,B 01PWR-A RSB
INTERNAL: ADN/LFNBIE FILEIE/DGAVT/GAB 21NRR PWR-B ADTS
R D FT/HFIBR C FIL 04R I/l'/IB
EXTERNAL: 24XDl'1B/DSS (Al'lDTS)NRC PDR 02PNL CRUEL> R
COPIESLTTR ENCL
1
2 21,
2 21 1
01 1
11 01 1
1 1
1 0
1 1
1
1 1
REC IP IENTID CODE/NAI'fE
PWR-A EBPWR-A FOBPWR-A PD2 PDPWR-A PSB
ELD/HDS1IE/DEPER/EPB 36NRR BWR ADTSNRR ROE'. LNRR/DHFT/NTBRQN2
BNL(ANDTS ONLY)LPDR 03NSI C 05
COPIESLTTR ENCL
11
01
011
3 3
TOTAL NUMBER QF COPIES REGUIRED: LTTR 33 ENCL. 28
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SINKCarolina Power & Light Company
SERIAL: NLS-86-178
Mr. Harold R. Denton, DirectorOffice of Nuclear Reactor Regulation .
United States Nuclear Regulatory CommissionWashington, DC 20555
SHEARON HARRIS NUCLEAR POWER PLANTUNIT NO. 1 - DOCKET NO. 50-000CONTAINMENTISOLATION VALVEFSAR CHANGES
Dear Mr. Denton:
Carolina Power i'.r. Light Company submits marked-up changes to FSAR Section 6.2.0regarding Containment Isolation Valves. These changes are submitted to provide theNRC with an advance copy for their review. The FSAR willbe formally revised in afuture amendment.
If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.
Yours very truly,
GAS/pgp (3916GAS)
Attachment
cc: Mr. B. C. Buckley (NRC)Mr. G. F. Maxwell (NRC-SHNPP)Dr. 3. Nelson Grace (NRC-RII)Mr. Travis Payne (KUDZU)Mr. Daniel F. Read (CHANGE/ELP)Wake County Public Library
S . Zi ermanM ager
Nuclear- icensing Section
Mr. Wells EddlemanMr. 3ohn D. RunkleDr. Richar.d D. WilsonMr. G. O. Bright (ASLB)Dr. 3. H. Carpenter.(ASLB)Mr. 3. L. Kelley (ASLB)
8b06iio o gOOOOOO.,pDR ADOCH O5 @DR,A
411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602
SHNPP FSAR
'anual
valves, closed remote~anual valves, and closed automatic valves whichremain closed after a loss-of-coolant accident. Locked closed isolationvalves are under administrative control to assure that they cannot beinadvertently opened.
6.2.4.2.4.2 General Design Criterion 55
Lines which are connected to the reactor coolant pressure boundary are shownin Table 6.2.4-1. Each penetration is provided with one of the following
'valve arrangements conforming to the requirements of 10CFR50, Appendix A,General Design Criterion 55, as follows:
a) One locked-'closed-isolation valve inside and one locked-closed-isolation valve outside Containment; or
b) One automatic-isolation valve inside and one locked-closed-isolationvalve outside Containment; or
c) One locked-closed-isolation valve inside and one automatic-isolationvalve outside Containment; a simple check valve is not used as theautomatic-isolation valve outside Containment; or
d) One automatic-isolation valve inside and one automatic-isolation valveoutside Containment; a simple check valve is not used as theautomatic-isolation valve outside Containment.
Isolation valves are located as close to the Containment as practical and,upon loss of actuating power, solenoid and air-operated automatic-isolationvalves fail closed.
An exception of GDC 55 is taken for the RHR suction lines. The lines from the'CShot legs to the RHR pump suctions each contain two remote manual (motor
operated) valves, which are locked closed during normal plant power operationand are under administrative control to assure that they cannot beinadvertently opened, in accordance with SRP Section 6.2.4 Item II.f. Thevalves are interlocked such that they cannot be opened when the RCS pressureis greater than the design pressure of the RHR system. This valve arrangementis provided in accordance with Westinghouse Systems Standard Design Criteria,Number 1.14, Revision 2 and Appendix B of ANSI Standard N271-1976.
P
An exception to Criterion 55 is taken for several isolation valves in lineswhich penetrate Containment and are required to perform safeguards functionsfollowing an accident. Lines which fall into this category include the RHR
and safety injection lines, and RCP seal injection lines. Since these valvesmust remain open or be opened, a trip signal cannot be used. Instead, each ofthese motor operated valves is capable of remote manual operation Upon
completion of the safeguards function of the line, the operator can close theisolation valve from the Control Room. Leak detection capabilities for theseines is discussed in Section 5.2.5.
ee. Inset~ C o4 a.++a.ch~en4 2.~ ~ ~ ~ ~ enera es gn Criterion 56
The lines that penetrate the Containment and communicate directly with boththe atmosphere inside and outside of the Containment are of two types. The
6.2.4-5 Amendment No. 14
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t ~ SUPP FSAR
SIGNAL INDEX FOR TABLE 6.2.4-1
1 - Containment isolation Phase A (Signal 'T')
2 - Containment isolation Phase B (Signal 'P')
3 - Safety injection actuation (Signal 'S')
4 — Two out of four RWST low-low level
5 — Main steam line isolation
6 - Two out of three low-low level in any steam generator
7 — Loss -of main feedwater pumps
8 - Containment ventilation isolation
9 - Containment inside/outside differential pressure < - 2.5 in. wgo
10 - Containment inside/outside differential pressure < — 0o25 in. wg.
11 — Containment spray actuation
12 — Two out three reactor coolant pump undervoltage
13 — Two out three low-low level in any steam generator
jg 14 — Main feedwater line isolation
15 — Main steam line isolation + steam generator low pressure
16 — Steam generator low-low level + excessive auxiliary feedwater flow tosame generator
«<ili0.rg Feed ~a4er ISolakIon~+ — I- oSS of oAsihe PowerI5 — Any Zj earn generakov. Low- Lo~ Level
6.2.4-11
SKIP
FSAR,'EFINITIONS
FOR TABLE 6.2.4-1
ACCIDENT SIGNAL —A signal which automatically initiates positioning ofvalves other than containment isolation valves to positions required toperfor'm their safety-related function.
2o AUTOMATIC ACTUATION — Initiation of a powex-operated valve by automaticmeans without any action by a plant operator upon receipt of anaccident/isolation signal from a protection system.
3% CLOSED SYSTEM —A safety-related piping system which penetrates and isa closed system either inside or outside the Containment. The system issubject to the pump and valve operability test requirements and theinservice inspection requirements of the APifE Code Section Xl. Undernormal operating or LOCA conditions for closed systems insideContainment, the fluid in the system does not communicate directly witheither the Reactor Coolant System or containment atmosphere. Undernormal operating or LOCA conditions for closed systems outsideContainment, the fluid in the system does not communicate'directly withthe environs.
4. CONTAIRKNT ISOLATION SIGNAL - A signal which automatically initiatespositioning of valves other than engineered safety feature valves topositions required to perform their containment isolation function.
CONTAINMENT ISOLATION VALVE — A valve which establishes a mechanicalbarriex in appropriate fluid systems penetrating the Containment; whichcould otherwise represent open paths to the environment from inside theContainment for fission product
6. LEAKAGE PATH — A penetration that is not part of a safety-related closedsystem and that could provide a direct path to the environment.
7 ~ LOCKED CLOSED ISOLATION VALVE — A valve that is in a closed position byadministrative controls by one of the following:
(1) A mechanical device locking the valve in the closed position.
(2) A normally closed valve with a seal or lock on any manual override,if present, and a seal or lock on the power breaker or power source in amanner that prevents power from being supplied to the valve.
POWER TRAIN —The source of emergency electrical power from one or bothof the redundant A and B emergency buses. See'ection 8.3
REMOTE MANUAL ACTUATION — Initiation of a power-operated valve by adiscrete manual action such as operation of a control switch.
MaximumRESPONSE TIME - Stro e time for a valve to move to its safety-related'position.
sec inscv5 R o4:otkaehrnenp 'f
TYPE C TEST — 10CFR50 Appendix test as described in Section 6.2.6o
6.2.4-12
Atkci.ch men P
lNSeRT A
UCXlv~~ 44~4 Clos~ c n au.@ma4ic. ~4akiovi <"n~vio< veau-i'red +o dose. within speci4c. pi~ep
<~~~~P*one ivi o.cc.iden<. annlq~g ~<eGS cl os(ng i l less 4 la.n Qo Recon<(s a-s ccqu.lied~~cIaef PeVle~ Pla~ Sec+oA
lHSEQT 5Yg.ives which do noh requlve o. +pe
do none. o f the allowing;7) provide g clii ec.b Connection be4meen <he, inside
ou.t side a 4vnc sphere~ o4 +~e- prt~o.~ reactor'onkcLinment u.vider. nor~a( operas(on.
77) Qie, r~u.<red ko Cloae a.u4c ~a+i'ca.((Q ~po~"~~c-'p~ o~ G. Conic <n'neck i'solokio~ signa.( qadir Spo ice. ~ COn+rOIS fnHndZd. +O e~eCq COn~ii men/t 5 co t ch+ oi
jj j) A~ r~ctu.ired +a operate. in &e~~iktenklqu~d.ee pos 0 a cc,iden t Qo~ i+ i one.
SEEP FSAR
NOTES FOR TABLE 6. 2. 4-1
The inside containment barrier is a closed system inside Containment.The closed system is subject to the inservice inspection requirements ofAPifE Section XI. The system remains at a pressure greater than 45 psigpost-LOCA.
2 ~
Sce in S.ergof o~. )
The outside containment isolation barrier is a closed ESF system outsidethe Containment. The system is subject to the pump and valveoperability test requirements and the inservice inspection requirements
5f the ASNE Code Section XI.
inment valve which is not relied u ontaznmentisolation functxo s not relied upon for containmentisola ype C test is required.
4 ~ Remote manual instrument isolation valve. Valve is maintained open forboth normal and post-LOCA operation.
5. i&nual or remote-manual which is locked (physically locked oradministratively controlled) and remains locked post-LOCA.
6.
7.
I
The valve is used periodically during operation. Any leakage throughthe valve would 'be detected during normal operation.
Valve is only opened when adding water to the pressurizer relief tank orRCP standpipe. It is interlo'eked to cl'ose on a Phase A containmentisolation signal.
8. Valve is only opened when adding water to the accumulators. It isinterlocked to close on a Phase A containment isolation signal.
Valve is opened only to verify leaktightness of accumulator checkvalve. It is interlocked to close on a Phase A containment-isolationsignal.
10 Valve is opened only when charging nitrogen to the accumulators it isinterlocked to close on a Phase .A containment isolation signal.
~ay c,
Center shaft butterfly valve tested in the reverse direction Leakageis equivalent since the same sealing surfaces are tested when testpressure is applied from either direction.
12.
13
Wedge-disk gate valve tested in the reverse direction. Results obtained'in this configuration are equivalent to testing in the accidentdirection. Because of the disk seat design, testing in either directionmeasures the leakage across both seating
surfaces.'lobe
valve tested in the reverse direction. The results obtained areconservative since test pressure tends to unseat the valve disk.
14. Diaphragm valve tested in the reverse direction. Leakage is equivalentsince the same seating surface is tested when test pressure is appliedfrom either direction.
SHNPP FSAR
NOTES TO TABLE 6.2.4-1 (CONT'D)
15. These penetrations are connected directly to the sump. During an
accident, they will be filled with water. This water seal will existduring the entire post-accident period.
16. Both the pressure sensor and the hydraulic isolators have an internalbeLLows which serve as isolation barriers for the capillary tubes.
17. The isoLation valve is sealed with a seal.-fluid with sufficient fluidinventory to assure the sealing function for at Least 30 days at 1 ~ 10 P
5 W C ) wloq Q Q oped eg Iog oping ~~~Wcc'<d<'~ t= l on.~- $ervn coo(in'.
~'I. V~l<<5 are ClOSel orl CO~<ainvneng phag Q ~ ~*'C<50 c, o~ Slqnat
a pened pcrno~e- Mo.n~](L for>~mpling
a ves AF- g)~ l90 O,nJ IRl3~«~+<o~ We,< - La.qu p
6.2.4-13a Amendment No. 25
SHiilPP FSAR
ABBREVIATIONS FOR TABLE 6. 2.4-1
Fluid
A- Air
G — Gas
S — Steam
W — Water
CF-Capillary Filling
Valve Tv e
BF — Butterfly
CK — Check
DA — Diaphragm
GA - Gate
GL — Globe
RG — Regulating
RL — Relief
XC — Excess FlovCheck Valve
Actuator,
AO — Air Operator
EH — Electro-hydraulic
M — Manual
i'lO — Motor. Operator.
SA — Self-Actuating
SO - Solenoid Operator.
Primary/Secondary
Actuation Modes
A - Automatic
— Manual
Valve Position
AE — As Es
C - Closed
Cy - Cycle
LC — Locked Closed
LO — Locked Open
0 - Open
TH - Throttled
TL - Locked Throttled6. 2. 4-14
RF — Reverse Floe
RM — Remote Manual
Amendment No. 8
TABLE 6.2.4-2
CONTAINMENT.ISOLATION VALVE POSITIONFOLLOWING AN ACCIDENT
PenetrationNo. Penetration Name
Essential or>1
Non EssentialValve
Position
MlM2
M3
MS-SG AHS-SG B
MS-SG C
NENENE
CLOSEDCLOSEDCLOSED
M4
M5
M6
FEEDWATER SG A
FEEDWATER SG B
FEEDWATER SG C
NE
NENE
CLOSEDCLOSEDCLOSED
Ml
HB
M10MllH12
M13M14
M15M16
M17
m M18c. H19
M20n M21
M220
M23H24
NO L LETDO N
C-UCS Nor~a.lCHARG NG
SEAL INJECTION RC PUHP ASEAL INJECTION RC PUHP B
SEAL INJECTION RC PUMP C
RC PUHP SEAL INJECTION AND EXCESSLETDOWN EXCH OUTLET
LOW HEAD SI TO COLD LEGLOW HEAD SI TO COLD LEG
RHR LOOP 1 (NORMAL OPERATION MODE)RHR LOOP 2 (NORHAL OPERATION MODE)
N i h Head Sy ~ Cold LeLOW HEAD SI TO HOT LEGSPAREHIGH HEAD SI TO HOT LEGHIGH HEAD SI TO HOT LEGHIGH HEAD SI TO COLD LEG
CONTAINMENT SPRAYCONTAINMENT SPRAY
NE
NE
E
E
E
NE
NE
NE
$E
peE
CLOSED
CLOSEDOPENEDOPENEDOPENEDCLOSED
OPENED
OPENED
CLOSEDCLOSED
OPENEDCLOSE (S P BY 0 OR
N/A ACTION LONG
CLOSE (5) T COOLINCLOSE (5
Ca.o>CO (~ )
OPENED:"OPENED:""-
25
TABLE 6.2.4-2 (Cont'd)
CONTAINMENT ISOLATION VALVE POSITIONFOLLOWING AN ACCIDENT
PenetrationNo. Penetration Name
Essential orNon Essential
ValvePosition
M25M26M27M28M29M30M31M32M33M34M35M36M37M38M39M40M41M42M43M44
M45M46M47M48M49M50M51M52M53M54M55
CONTAINMENT FAN COOLER AH3-SW INCONTAINMENT FAN COOLER AH2-SW INCONTAINMENT FAN COOLER AH1-SW INCONTAINMENT FAN COOLER AH4-SW INCONTAINMENT FAN COOLER AH3-SW OUTCONTAINMENT FAN COOLER Af SW OUTCONTAINMENT FAN COOLER AHl-SW OUTCONTAINMENT FAN COOLER AH4-SW OUTPOST ACCIDENT GAS SAMPLE RETURNILRT ROTOMETERCOMPONENT COOLING WATER — RC PUMPCOMPONENT COOLING WATER — RC PUMPCOMP COOLING WATER EXC LETDN & RCDTCOMP COOLING WATER — EXC LETDN & RCDTCOMP COOLING WATER - RC PUMP THERM BARRMAKEUP WATER TO PRESSURIZERSERVICE AIR SUPPLYRCDT PUMP DISCHARGESPARES F PURIFICATION PUMP TO REFUELING
CAVITYREFUELING CAVITY WATER CLEANUP- OUTSPARESUMP RECIRC (RffR A)SUMP RECIRC (RHR B)SUMP RECIRC (CONT SPRAY A)SUMP RECIRC (CONT SPRAY B)SG A BLOWDOWN
SG B BLOWDOWN
SG C BLOWDOWN
SG A BLOWDOWN SAMPLESG B BLOWDOWN SAMPLE
E
E
E
E
E
E
NENE
NEE
NENENE
NE
NE
E
E~ E
E
NENENE
. NENE
C.to&ED
CLoSEO
OPENEDOPENEDOPENEDOPENEDOPENEDOPENEDOPENEDOPENED
CLOSE <3)CLOSED
.0CLOSED
20
SIGNAL)-'-':-" cn
CLOSEDCLO ED
CASED
CLOSEDCLOSEDCLOSEDN/ACLOSED
CLOSEDN/AOPENE +)OPENEOPENE f'f)OPENECLOSEDCLOSEDCLOSEDCLOSEDCLOSED
LLY C
PEN 0 ATERIN RWST
TABLE 6.2.4-2 (Cont'd)
CONTAINi1EifT ISOLATION VALVE POSITIONFOLLOWING AM ACCIDENT
PenetrationNo. Penetration Name
Essential orNon Essential
ValvePosition
H56L157
i~f58
H59H60H61H62H63H64H65H66-H68H69H70H71H72
SG C BLOWDOWN SAHPLECONTAINMENT PURGE HAKEUPCONTAIi%1ENT PURGE EXHAUST
VACUUH RELIEF ASPARE
H2 PURGE HAKE-UPCONTHT LEAK RATE TEST PRESS INDIC.H2 PURGE EXHAUSTSPAREFUEL TRANSFER TUBESPARE
CONTAINHENT PRESSURE SENSING ACONTAINHENT PRESSURE SENSING B
CONTAINlfENT PRESSURE SENSING C
CONTAINHENT PRESSURE SENSING D
NENE
NE
NE
NE
CLOSEDCLOSEDCLOSEDCLOSEDCLO E
CLOSEDCf.OSED
N/ACLOSEDN/AN/AN/AN/AN/A
H73AH73BH74H75?176A
H76BH77AH77BH77CH78AH78BH78CH78DH79H80H81-fif85
CONTAINHENT ATH H2 RADIATION HONITORCONTAINHENT ATH H~ RADIATION HONITORCONTAINHENT SU'fP PUHP DISCHARGESPARE
ACCUHULATOR FILLACCUHULATOR TO RWST
Ng TO~CCUHULATORPRT Hf & CDT CONNECTIONRCDT H2 SUPPLY & GAS SAHPLERC LOOP 2 & 3 SAHPLEPRESS. LIQUID SAHPLEPRESS'TEAH SAHPLEACCUHULATOR SAHPLEFIRE PROTECTION-STANDPIPE SUPPl Y
INSTR AIR SUPPLYSPARES
p/ ~ E
pNE
NE
NENE
NENE
NE
NE
NE
NE
NE
NE
CLOSED*CLOSED*CLOSEDN/ACLOSEDCLOSEDCLOSED
CLOSEDCLOSEDCLOSE (3)CLOSEDCLOSEDCLOSEDCLOSED
CLOSEDN/A
TABLE 6.2.4-.2 (Cont'd)
CONTAINMENT ISOLATION VALVE POSITIONFOLLOWING AN ACCIDENT
PenetrationNo.
M86AM86BM87M88M89M90
M91M92M93M94A,BM95A>BM94CM95CM96M97M98M99-M102M103AM103BM103CM104M105M106M107AM107BM107CM108M109M110
Penetration Name
CONTAINMENT HYDROGEN ANALYZERCOHTAINMEHT HYDROGEN ANALYZERSPAREPOST ACCIDENT LIQUID SAMPLE RETURNSPAREDEMIN. WATER TO FUEL TRANSFER SYSTEMCONTR PANEL & REFUELING CAVITY DECONCONTAINMEHT FAN COIL UNITS SW — OUTCONTAINMENT FAN COIL UNITS SW - INSPARECONTAINMENT VACUUM RELIEF SENSING LINESCONTAINMENT VACUUM RELIEF SENSING LINES
o~h ltJ)vlEMT OUTSibE'IFFEREnlTIRCpRGssukB se>sic&
CONTAINMENT LEAK RATE TEST SUPPLY 6 EXHAUSTSPAREVACUUM RELIEF B
SPARESRVLISRVLIS
RVLIS
SPAREFIRE PROTECTION SPRINKLER SYS HDRSPARERVLISRVLI8RVLISAUX FEEDWATER TO SG AAUX FEEDWATER TO SG B
AUX FEEDWATER TO SG C
Essential orNon Essential
NE
NENE
E
NE
NE
NE
ValvePosition
CLOSED*CLOSED~N/ACLOSED (3)N/ACLOSED
CLOSEDCLOSEDN/AOPENOPEN
OPE~<
N/ACLOSEDN/ACLOSEDN/AN/AN/AH/AN/ACLOSEDN/AN/AN/AN/AOPENED +OPENED +
OPEHED +
g20
20
20
TABLE 6.2.4-2 (Cont'd)
CONTAINMENT ISOLATION VALVE POSITIONFOLLOWING AN ACCIDENT
2)
ISOLATION VALVE CLOSED ON PHASE A CONTAINMENT ISOLATION SIGNAL. REOPEN MANUALLY FOR POST ACCIDENTH2 SAMPLING.NORMALLY CLOSED. OPEN ON CONTAINMENT SPRAY ACTUATION SIGNAL.A "P" SIGNAL IS DEFINED AS A CONTAINMENT PHASE B SIGNAL.WILL BE CLOSED TO ISOLATE FAULTED STEAM GENERATOR (ie., LOSS OF SG PRESSURE BOUNDARY)
ESSENTIAL: LINES REQUIRED TO MITIGATE AN ACCIDENT, OR WHICH, fF UNAVAILABLECOULD INCREASE THEMAGNITUDE OF THE EVENT.NON-ESSENTIAL: LINES WHICH ARE NOT REQUIRED TO MITIGATE AN ACCIDENT, AND WHICH IF REQUIRED AT ALLWOULD BE REQUIRED FOR LONG TERM RECOVERY ONLY; ie., DAYS OR WEEKS FOLLOWING AN ACCIDENT.
3) Aft.UES CtM'>PLEO gd~GRm >rrENrLy +OR'cS7 - +cC1Deu'7 SAmpzinjc
IQI7 rlHLc y cc.osEu op&/ on/ Low %8rEH c,E'vEL w sp(n/57-
Or-'E~CD i3Y CP~~+rDR 4C770hl FO+ LO~'Q
SHNPP FSAR
During a type A test, the steam generator'econdar side is to be ventedoutside the containment atmos here.
Thesystems connected to the secondary side of the steam generator are identifiedin Table 6.2.4-1.
6.2.6-2a Amendment No. 26
SHNPP FSAR
6.2.6.3 Containment Isolation Valve Leaka e Rate Tests (T e C Tests)
Table 6.2.4-1 lists aLL valves which are associated with the penetratingpiping systems. Table 6.2.4-1 also indicates for all valves listed which areconsidered to be containment isolation vaLves and which of the containmentisolation valves are to be subjected to Type C test The EoLlowing criteriawere used to determine which containment isolation valves are Local leaktested:
a) The penetrating system provides a direct connection between the insideand outside environments of the Containment under normal operation.
b) The system is isolated by containment isolation valves which closeautomatically to effect containment isoLation in response to a Phase Acontainment isolation signal.
26
c) The system is an engineered safety features system which does notrequire leak testing because the system is a closed system outside ofContainment in accordance with SRP 6.2.4 and because the isoLation valve issealed with a seal-fluid with sufficient Eluid inventory to assure the sealingfunction for at least 30 days at 1..10 Pa.
, ~ 'H
d) The system is an engineering safety features system which has only asingle isolation valve located outside Containment requiring testing becausethe system is a closed system outside of Containment in accordance withSRP 6.2.4o~ ~
~
The engineering safety features systems and penetrations which are notleak tested because they are in accordance with item "c" are: ECCS low headsafety injection to the cold legs (M-13 and M-14), the Containment sump water.supply .to the ECCS low head (RHR) pumps (M-47 and M-48), and the Containmentsump water supply to the Containment spray pumps (M-49 and M-50). The fluidseal within the pipe and the closed system outside of Containment precluderelease of containment atmosphere to the environment. No containment airleakage can occur due to a single active failure in any of these systems.
The engineered safety features and penetrations which are leak tested inaccordance with item "d" are: ECCS high head safety injection to the coldlegs (M-17 and M"22), ECCS low and high head safety injection to the hot legs(M-18, M-20, and M-21), and the CVCS seal water supply to the Reactor CoolantPumps (M-9, M-10, and M-11). The single isolation valve outside Containmentand the closed system outside Containment preclude release of the containmentatmosphere to the environment. No containment air Leakage can occur due to asingle active failure in any of these systems.
26
Service Water to and from the fan coolers is a closed ASME Class 2 systeminside containment in accordance with FSAR paragraph 6.2.4.2.4.4. No singleactive failure of any component could provide a potential leakage path Eorpost-LOCA containment atmosphere. This system is described in FSARSection 9.2.1. General Design Criterion 57 is applicable to this system asdiscussed in FSAR Section 6.2.4.
6.2.6-6 Amendment No. 26
SHNP P FS AR
26
t PLL portions o the secondary side o t e steamgenerators are consxdere an extension oE the Containment. These systemspenetrate the containment shell at penetrations numbered 1 through 6, 51through 56, and 108 through )10. ~
L (hlSCgT' o $ ~++~+~enThe test, vent and drain (TVD) connections that are used to facilitate localLeak testing are under administrative controL, and subject to periodicsurveiLl.ance, to assure their integrity and verify the efEectiveness ofadministrative controls. These procedures meet the requirements of SRPSection 6.2.6 Item II.
7
The containment pressure transmitters are designed to meet the requirements ofRegulatory Guide 1.11 and are described in Section 7.3. These lines have noisolation valves and rely on closed systems both inside and outside of theContainment to precLude the release oE the containment atmosphere. Theintegrity oE these cLosed systems is verified during the periodic Type Atests'hese Lines penetrate the Containment at penetrations 69, 70, 71, and72.
/fl5a P ~As noted in Subsection 6.2.4.2.4.4,e
o8 a,/hJ.3
The test equipment to be used during the Type C tests consists oE a connectionto an air supply source, pressure regulator, pressure gauge, flow indicator,and associated valving or equivalent test setup.
Isolation val.ves are positioned to their post-accident position by the normalmethod with no accompanying adjustments. Fluid systems are properly drainedand vented with the valves aligned to provide a test volume and atmosphericair back pressure on the isolation vaLve(s) being tested.
The test volume is pressurized to the test pressure P , 41.0 psig. Thepressure regulator(s) maintain the test volume at a minimum of 41.0 psig. Theair flow rate into the test volume is recorded, as is the pressure reading, atthe intervals specified on the data Eorm. These records are utilized todetermine the l.eakage rate in cubic centimeters per minute.
26
For Larger test volumes, a pressure decay method may be util.ized to determinethe leakage rate.
The total leakage rate for Type B and C tests will be Less than 0.6 l. . Theindividual testing performed on valves requiring a Type C test isdescribed in Technical Specifications.
In accordance with 10CFR50 Appendix J III.C.1, valves may be tested in thenon"accident pressure direction when it can be determined that the resultsfrom the tests for the pressure applied in the non-accident direction wil.lprovide equivalent or more conservative results.
Fi.2.6-7 Amendment No. 26
The Containment Isolation Valves on the Component Cooling Waterlines which provide cooling water to the Reactor Coolant DrainTank and CVCS Fxress Letdown Heat Exchangers via penetrations0-V7 and H-38 are not leak tested. The components insidecontainment provide a closed system designed in accordance withGeneral Design Criteria 57. Two simultaneous passive failures ofClass 2, or better, systems is not considet ed a credible event.A LOCA is a passive failure of the Reactor Coolant System, andtherefore it is not credible to assume a .imultaneous passivefailure of'he CCM closed system. Therefore, the closed systeminside containment is sufficient, to insure that the Containmentatmospher e is not released to the environment. following anaccident.
These systems provide a clo .ed system designed in accordance with...General Design Criteria 57. They are not leak tested because the
closed system inside containment is sufficient to insure that theContainment atmosphere is not released to the environmentfollowing an accident.
mERTlR% ~0 AvuuabIe Ou
Aperture Card
PENETRATlON DATA
TABLE 6.2.4-lCONTAINMENT ISOLATION SYSTEM
SHNPP I FSARDATA
VALVE DATA
PENETRATION DETAIL
~4v
'V
vOy
cP A.
o~ o~o ~o
4( C'y
e8.~ ~O
e~~ e~~o e
VALVE POSITION~tv ~4m
o+ 4Og
~e. ~4 o
NOTE
IRC ORC
MS.V1
MSI'1
042 57 S YES NO MAIN STEAMLOOP A
Rl-R4R7R10R13P18V1F1V59V122
L&BA&BE&BJ,&B
4161
8'01
37125'
RL
RL'GL
GLGL
cGLGL
SASASASASAEHAOAOAOAO
AAAAA
5i0PK<
(I
C
C
C
.CC
C
0C
0"0
C
C
C
C
C
C
C
C
C
C
C
C
C
C
YES
YESYESYESYES
NO
NO
NO
NO
HO
YG
~YeJy6~~
YE
YESYESYESYESYES
NO~ 0
0NO
0NO
NO
NO
NO
NO
s
IRC ORC
MSR11 P)
>I > TC
57 S YES MAIN STEAMLOOP B
R2R5R8R11R14P19V2F2V60V8V124
IB
A&BA&B
A
6810
~ 1
73gl6'LIGA
~GL
SASASASASAEHAOAOAOMO
AO
AAAAAA
51
(tPO 3C
C
C
C
C
C
C
0C
0C
0
C
C
C
0C
C
C
C
C
C
C
C
C
C
AIC
C
C
C
C
C
C
C
C
C
C
YESYESYESYES
YESNO
NONO
NOYESNO
YESYESYE
YES
00000
NO
NO
NO
NO0
NO
IRC ORC
a
FQ>j TC
MS4l1Z + )MSR15 ~ * 042 S YES NO MAIH STEAM
LOOP C
R3R6R9R12R15P20V3F3V61V9V126
A
P&BJI&BA
Q&B
46810
7
RLRLRLRLRGLGLGLGIGAGl
SASASASASAEHAOAOAOMO
AO
AAAAAA
C
C ~
C
C
C
C
0C
0C
0
C
C
C
C
C
~cy'
C
C
0C
C
C
C
C
C
C
C
C
C
AIC
C
C
C
C
C
C
C
C
C
C
YESYESYESYESYESNONO
NONO
YESNO
YESYESYES
S
'/f'ES
NO
0000
NO
NO
NO
NO
NO
NO
6.2A—l5 8606» O260-0 Amendment N0. ~4
)
I= y
~ 1
c~~ Jock'%a~
V «~»sq
r) ~
T'APER RE. ~ ~ ~,bI, P,
Aperture Carl
PENETRATlON DATA
TABLE 6.2.4- I
CONTAINMENT= ISOLATION SYSTEM DATASHNF P,, FSAR
VALVE DATA
IRC
PEHETRAT)OM DETAIL
ORC
o+
4/ ~v
4(g
e OO OO4
I, 4 ~ B' cFW ev e
VALVE POSITIOM
+ A,
k~v
~4/
A. ~Col c
~4 o
NOTE
SGB
IRC
TC
ORC
TC
TC
FW-V24 TC
SEENOTE A
044
57
W
NO
NO
FEEDWATERLOOP A
FEEDWATERLOOP B
V26V123V89V90
V27V124V91V92
A&BA&B
A&BA&BA&BA&B
g qlg 25'A L
EHAOAOAO
EHAOAOAO
AAAA
AAAA
4a~I3
l3
+6jA'I3gl
5IO
0C
00
0C
01~0
C
C
)-CC
NONO
NONO
NO
NO
NONO
YESYESYESYES
YESYESYESYES
NO
NO
NO
NO
NO
NO
NO
NO
FWVI2l SEENOTE A
IRC
TC,
ORC
TC
TC
044 W NO FEEDWATERLOOP C
V28V125V93V94
A&BA&BA&BA&B
glgfI
25'/q /
yq/ gL
EHAOAOAO
AAAA
5IO
50gC
0C
0rgO
C
C
C
C
C
C
C
C
HO
NO'O
NO
YESYESYESYES
NO
NO
NO
HO
C ) RV-VINSEO NOTE A
Cs.VSI1
I
IRC PRC
CLVS14
803 55 W NO CVCS-NORMALLETDOWN
R500V511V512V513V518
AAA
l7
17
1
GL
GLGL
SAAOAOAOAO
AAAA
10101010
C
CY0CY
0
HONO
HONO
NO
YESYESYESYESYES
YESYES
YESYESYES
IRC ORC
CS VSI0
803 NO CVCS-NORMAL
CHARGING
V515V610
CKGA
SAMO 10 AZ
NO
NO
YESYES
YESYES
NOTE A The arrangement is shown as detail C "Typical Bypass at Feedwater IsolationValve" of FSAR Figure 10. 1.0-3 6.214 —16 SC06 > > 0360 Amendment No. 14
I
t
1-
C',C-'ee
t~l II
, 1p,
i:"4 N
e> P
f~
C
4
0TI
TA8LE 6.2.4- I
>rg ~b ~ g~j CONTAINMENT ISOLATION SYSTEM DATA'SHNPP ! FSAR
'ENETRATIONDATA VALVE DATA
PENETRATION DETAIL
o+
Qaa+o
+o+
>e-
~4v ~ ~4vv o g+ vv
O~ v~o @o
~o+I e~ A~ O'A~ Oo~Z
A. ~44.Q +o goo o
v
4vPi
VALVE POSITION~4v
O4v
'A,~4 o
NOTE
IRC ORC
VC.
[sg9
803 NO CVCS-SEAL WATERTO RCP
'A'25V522 B
CKGL
SAMO AI
YESYES
IRC ORC803 NO CVCS-
SEAL WATER
TO RCP'B'26V523
CKGL
SAMO
00 AI
YESYES
f46 b)0'AS'S
~S
)23
IRC ORC
803 NO CVCSSEAL WATERTO RCP
'C'27V524CKGL
SA
MO AIYESYES
NO
ES
)VO
YES
I 23
TC
M
IRC ORC
TC
g803 NO NO CVCS-
SEAL WATER,RETURN &EXCESSLETDOWN
V67V516V517
AB
2CKGLGL
.SAMO
MO
AA
1010
C
00
AIAI
NO
NO
NO
YES YESYES YESYES YES
IRC ORC
TC TC
13
810 NO SAFETYINJECTION-LOW HEAD TOCOLD LEGS
V581V579
CKGA
SAMO
C
0 AIYES NO
YESNO
NO 2 3
IRC ORC
810 NO SAFETYINJECTION-LOW HEAD TOCOLD LEGS
V580V578
CKGA
SA
MO AIYES N
YESNO
NO 2 3
Py
)23
g]
RH RH.V503
iIQ
IRC ORC
R 501
!
1S ~~
NO RHR SUCTIONFROM HOT LEG
R501V502V503
B
A1012
SAMO
MO
MM
AIAI
S
YES0
NO
NO
NO
* Exception to GDC 55 See Section 6.2.4.2.4.2 62 't7 8 uoe s ~ 0260-03 Amendment No 23
P
0
C
J
VI't I
~ .
ij t
4'
-':-':- JmVERTU%
,CAlRB
Also Available Oa,Aperture Cagg
PENETRATION DATA
TABLE'.2.4- I
CONTAINMENT ISOLATION SYSTEM DATA'SHNPP, FSAR
YALYE DATA
PENETRATION DETAIL
IRC ORC
o+
O
r
o ooCy V
eP ~+ ~ 4,gc < ~e
e~ ev
Cy~Co
VALVE POSITION~4v
4.CO 4 ~++
~4o
NOTE
g R
NO RHR SUCTIONFROM HOT LEG
R500V500V501
112
SAMO
MO
M
M
C
C
C
AIAI
YESNO
NONO
2,3,I8
RH-VSOOr
TC
p5St-yq
gI - V sI3 a.vn
cf Ia.va
~s<- vsse p
ORC 808 * W NO SAFETYINJECTION-HIGH HEAD TOCOLD LEGS
V17V23V29V440V439V438V30V505V506
BA
14432
3
CKCKCKGLGLGLGLGA
GA
SASASAMMM
ifMO
MO
MM
MMAA
1010
C
C
C
TLTLTLLCC
C
C
C
C
TLTLTLLCC
C
000TLTLTLLC00
AIAI
C
C
C
TLTLTLLCC
C
YESYESYESYESYESYESYESYESYES
NO
NO
NO
NO
NO
N
Y
YESYES
NO
NO
NO
NO
NO
NO
NO
YESYES
IRC ORC
TC
5 10,8
Q-V511
TCM
5 I.V587
$ 10
SAFETYINJECTION-L(M HEAD TOHOT LEGS
V510vsaaV587
5355a
CKCKGA
SASAMO AI
YES
YESYES
NO
NO
YES
NO
No Is g~sYES
19 SPARE
IRC
TC
I„5I 'V t3O 5i vie
Sl Vee (4tVSO
5 I -V'ItO'I
ORC
808 NO SAFETYINJECTION-HXGH HEAD TOHOT LEGS
V84V90V96V431V430V429V500 A
8236a4081351391
CKCKCKGLGLGLGA
SASASAMMMMO
MM
MRM
C
C
C
TLTLTLC
C
C
C
TLTLTLC
~C.|gi C
'CTLTL
Qc AI
C
C
C
TLTLTLC
YESYESYESYESYESYESYES
NO
NO .
NO
NO
NONOYES
NO
NO
NO
NO
NO
NOYES
* Exception to GDC 55 See Section 6.2.4.2.4.26.2A—18
8 606 11 0260-OgAmendment No. 14
,r
„Cy
e
I al
1 lgI
e
ta",
k
4'.I,yg
APER 'o Avoilub1e Ou
Cpmo 'e~e G
PENETRATION DATA
TA8LE 6.2.4- I
CONTAINMENT ISOLATION SYSTEM DATA'SHNPP ~ FSAR
VALVE DATA
PENETRATION DETAIL
o+
o
~cv
ce'
~+
cvgV
I cv cv ~( vO O + +
e+ + < co+< ~o y ~+ v
e~ e~ 4 > e +
VALVE POSITION~cv
cvco
4~o
g~ ecv p+ ~ ecv
NOTE
IRC ORC
SI-V 88
Qsa
808 * W YES NO SAFETYNJECTION-
HIGH HEAD TOHOT LEGS
V39V45V51V434V433V432V501
- lViB
~8'g8
IjP131
CKCKCKGLGLGLGA
SASASA
M
MMMO
M
M
MRM
C
C
C
TLTL =
TLC
C
C
C
TLTLTLC
g'5~Cgi'C,
'L
TL
AI
C
C
C
TLTLTLC
YESYESYESYESYESYESYES
NO
NO
NO
NO
NO
NO
YES
NO
NO
NONO
NO
NO
YES
Sl-V51
'Si-V I
Sl-VlI3lIRC
~~i—~n
.I,I
V(I3$
ORC
TC
808 W YES NO SAFETY
HIGH HEAD TO/COLD LEGS
YtI3IVMS
V63V69V
j~cV502
0a
CKCKCKGLGLGLGA
SASASAMMMMO
MM
M
RM
C
C
C
TLTLTLC
C
C
C
TLTLTLC
yrOTLTL
AI
C
C
C
TLTLTLC
YESYESYESYESYESYESYES
NO
NO
NO
NO
NO
NO
YES
NO
NO
NO
NO
NONO
YES2 .5 iS
(RC ORC
TC TC TC 050 56 YES NO CONTAINMENZSPRAY
V27V21
P'g CKP'g GA
SAMO ao
C
,C AIYESYES
YESYES
YESYES
CT-V51
IRC ORC
CT V43
050 56 NO CONTAINMENTSPRAY
V51V43
CKGA
SAMO 10 AI
YESYES
YESYES
YESYES
IRC 0RC
TC pAM 25
047 57 W NO NO SERVICEWATER TO FANCOOLER AH-3
B46 1 BF MO RM 0 0 0 AI 0 YES
YesNO
* Exception to GDC 55 See Section 6.2.4.2.4.2 6.2.4 —19
8606 3 1 0260 05Amendment No. 14
4
'I
C l
r
II
s
TI'APERARE
CMM Pp~~, sea
PENETRATlON DATA
TABLE 6.2A-.ICONTAINMENT ISOLATION SYSTEM DATA
sHNpp FSAR
VALVE DATA
PENETRATION DETAIL
IRC ORC
o+
y 'V
~+
4
Cy
cP A.
A% 0
Co vv
AJ4v
oo oo g+ ++ +4v4
Q e o QQ o~4k g A.
ev ev 4 > e
VALVE POSITION
A,
e F
~4v ~4v
oe+~4o
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