ML20106B188

Proposed Ts,Deleting Table 3.6-1, Containment Isolation Valves

ML20106B188
Person / Time
Site:	Summer
Issue date:	09/23/1992
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20106B179	List: ML20106B175 ML20106B188
References
NUDOCS 9210010039
Download: ML20106B188 (20)

Text

. _ - , _ _ _ _

Attachment 1 to Document Control Desk let' 1SP 9?0003 Page 1 of 1

& ,,.f g9 PROPOSED TECHn! CAL SPECIFICATION CHANGE - TSP 920003 VIPGIL C. SUMMER NUCLEAR STATION t151 Of AFFECTED PAGES d fl age Spfcificalion Cngr_iptjon of (hanqq V~

1-2 1.7 Removed reference to Table 3.6-1 from definition for Containment Integrity.

'3 3/4 6-1 3/4.6.1 Removed reference to lat - E 3.6-1.

3/4 6-17 3/4.6.4 neuoved reference to Table 3.6.1 ' rom LCO and Survellie,ce Requirements.

Relocated 3.0.4 statement from Table to Actions.

Relecated footnote from lable to LCO.

11 3/4 6-5 Bases 3 '4 6.4 Added the considerations of administrative control to the bases.

9210010079 9 "' j eon noucx o ' gp

DEFINITICNS CONTAINMENT INTEGRITY

1. 7 CONTAINMENT INTEGRITY snall exist wnen:

a.

All penetrations reouirea to be closea during accident conaitions are either:

1) Cacable of being closea by an 0?ERABLE containment automatic isolation valve system, or

2) Closea by manual valves, blind flanges, or deactiva*. automatic valves secured in their closea positions,-excect a ;a eiced "

appu Apow's THgebk 3. 6-1 c+ Speci f ic, ation 3. 6. 4.

n <.wem m p w,,estgiry S w W M v.8.vt/ m c M N _

b. All equipment hatches are closea and sealed, i

f'- c. Eacn air lock is in comoliance with the reouirements of Specification 3.6.1.3.

9-

d. The containment leakage rates are within the limits of Specification 3.6.1.2, and e.

The sealing mechanism associated with each peaetration (e.g., welds, bellows or 0 rings) is OPEP.ABLE.

CONTROLLED LEAXAGE

1. 8 CONTROLLED LEAKAGE snall be that seal water flow supplied to the reactor coolant pump seals.

CORE ALTERATION

1. 9 CORE ALTERATION shall be the movement or manipulation of .ny comoanent -

within the vessel. the reactor cressure vessel with the vessel head remobad and fuel in s Suspension af CORE ALTERATION snall not praclude completion of movemen. of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT

1. 9 a The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document that provides core operatir.g limits for the current operating reload cycle, The cycle specific core operating limits shall be determined for ea:n reload 4 cycle ir accordance with Specification 6.9.1.11. Plant operation within trmse opersting limits is addressed in individual specifications.

DOSE E0V! VALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /gr; -

which alone would proouce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133, I-134, ana I-135 actually present. The thyroic dose Conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power .ind Test Reactor Sites.

SUMMER - UNIT 1 1-2 Amenament No. 8E l

I

__ - - _ _ - _ - _ - - - - - - - - - - - ~ - - - - - - - - -' ' - - ~ ~ ~ ' _ _ __ _ _ _ _ _ - _ _ - _ _ - _ - - - - _ - - _ - - - -

l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION F3R OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

AP_PLICABILITY: MODES 1. ?, 3 and 4.

I ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

S'J,PVEILLANCE REQUIREMENTS 4.6.1.1 Pc' mary CONTAINMENT TNTEGRITY shall ue demonstr a. u:

a. At least once per 31 days by verifying that all penetrations

• not careble f being closed by OPERABLE containment automatic isolation va.ve, and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as-prov4ded in -Table-3,6-4-o'-

cwit?t. AS ?WWi%f Specification 3.6.4. Rfawf5tantsarfW n't'M AyngiW M W.

b. By verifying that each containment air lock is in compliance with the requirements of Spacification 3.6.1.3.

c. After each closing of each penetretion subject to Type B testing, except the containment air lccks, if opened following a Type A or B test, by leak rate testing the seal with gas at Pa (47.1 psig) and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.d i for all other Type 6 and C penetrations, the combined leakage rate is less than 0.60 L,.

^Except valves, blind flanges, and deectivated automatic valves which are located inside the contair. ment and are locked, sealed or otherwise secured in the closed position. These peneti + ions shall be verified closed during each COLD SHUTDOWN except that such ve ification need not be performed more often than once per 92 days.

S'J hMER - UNIT 1 3/4 6-1

CONTAINMENT SYSTEMS 3/4.6.4 CCNTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION _

A00~'6Ac//

3.6.4 4he-containment isolaticn valves +pect'ied-4n-Table-3r64 shall be OPERABLE .w4b4 solatica tim-et-eewn-4m& bled-6+- #g 1100 APPLICABILITY:  % DES ' 2, 3 and 4 ACTION:

With one or more of the isolation valve (s) 49ec4'4 ed '- T2ble-3r64 i nope rao l e , ,

maintain at least one isolatt :n valve OPERABLE in each af fected penetration that is open and either:

a. Restore the inoperaole valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

b. Isolate eacn affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one cesctivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by usc of at least one closed manual valve or blind flange; or

d. 3e in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ana in COLD SHUTDCVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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SURVEILLANCE REOUIREMENTS ADO ~

"ggy a.wrAtuMrwr 4,6. 4.1 -hi solation valves 49ee4fied-in-Table-ar64. shall be demonstrated OPERABLE prior to returning the valve to service af ter maintenance, repair or replacement worr is performed on the velve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time.

APb c:wrA rNin t s'?*

4.6.4.2 Each^i solation valve -spect-f4ed-in-Table-3r6-1 shall be demonstrated CPERA'lE u during tne COLD SHUTDOWN or REFUELING H00E at least once per 18 montns by:

a. Verifying that on a Phase A containment isolation test signal, eacn Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase B containment isolation test signal, each Phase 8 isolation valve actuates to its isolation position,

c. Verifying that on a Reactor Building Purge and Exhaust isolation test

/100 /WTNorf signal, eacn Purge and Exhaust valve actuates to its isolation

(.,a wurt e) y _

position.

SUMMER - UNIT 1 3/4 6-17

I l

. CONTAIHl4ENT SYSTEMS SURVEILLANCE REOUIREMENTS (Contin' sed) grymnwrpr isnsnew 4.6.4.3 The isolation time of eacn power operated or automatic ^ valve +f-

-tem; 3.0-1 shall be cetermined to be within its lis't wnen tasted pursuant *a Specification 4.0.5.

lvs EA T l : s c e r t2 :: x S E A L n 9 v : n it? i m e r 5 s'tx," 5 cf s k ED Osv ny ir.TFR M i : E N C SA3 /.5 . tNC)F4' /,Jp,*tte if t/ A rive :: MEA'GL -

4 SUMMER - UNIT I 3/4 6-1B

C)EL E T E ,

g _- _ _ . _ _ _ __ __ _ _ _ _ _ _______ ,_ _

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, TABLE 3.6-1 (Continued) /

m s h s CONTAll04ENT ISOLAllCN VALVES -

/

g \ p i

N / HAXg c VALVE HUMBER ,

ISOLATION TIME g E. REMOTE MANUAL-(xContinued) FUNCTION j' (SEC) g 5. 8107-CS \ Charging the To Regenerative lleat Exchange ' N/A 6.

7.

60508-ilR 6051A-llB N

's' Hydrogen Analyzer Return Line Hydrogen Analyzer Supply Line , '/

HIA N/a

3. 6051F :12 s  !{ydrogen Analyzer Supply Line / N/A

9. 6051C-HR lt

'N ydrogen Analyzer Supply Line / N/A

10. 6052.".-!!R 'ltydrogen Analyzer. Return Line/ N/A

11. 60528-liR HfdogenAnalyzerReturnLjr4 t

i:/A

12. 6053A-IIR Hydr'o gen Analyzer Supply tine N/A

13. 60538-11R flydrog3n Analyzer Suppip Line M/A

34. 8701A-RHJ RHR Puw 5uction from Reactor Coolant Loop A N/A I

15. 87018-Rite on from Reactor Coolant Loop C N/A i y 16. 8801A-SI - EllR Baran Pump Injectio Suht[KTank To Reactor Coolant imops N/A

• 17. 8801B-51 Boran injection lack To Reactor Coolant Loops N/A

18. 8811A-SI RHR Pump _A' Suction'Frca Recirc.1ation Sump N/A

? RilR Pudf 9 Suction Frsa Recirculation Sump N/A g 19. 88110-SI o 20. 8884-SI Higtv11ead Safety injectlbq To Reactor Coolant Loops N/A

21. 8885-51 liigh Head Safety Injection'To Reactor Coolant Loops K/A

22. 8886-51 e N/A

/ lligh Low llead Safety Head Ssfety injaction InjectionTd' ToReactor Rehqtor Coolant Loops Coolant Loops M/A 4

23. 8888A-SI

24. 88888-51 / Low flead Safety Injection To Reacts [ Coolant Loops N/A

25. 88C9-55

' Low Head Safety Injection To Reactor' Coolant Loops N/A

26. 30D3A-SP Supply To Reactor Building Spray Hozzi'es. N/A

27. 3003B-SP Supply To Reactor Building Spray Nozzles \ N/A

/ Spray Pump A Suction From Recirculat!M Sap. N/A

28. 3004A-SP

[ 29. 30048-SP / Spray Pug B Suction Frca Recirculation Soap \s Service Water From Reactor Boliding Cooling Unit'4 N/A N/A L o 30. 3103A-SW E 31. 3103B-SW j / Service Water From Reactor Building Cooling Unit BN N/A Service Water To Reactor Butiding Cooling Unit A N g/A E 32. 3106fb59

33. 310 Sit-W 3ervice Water To Reactor Building Cooling Unit 8 M/A

~

E 34. 3110A-SW Service Water To Reactor Building Coolfog Unit A' N/A 35 / 31108-SW Service Water le Reactor Building Cooling Unit 8 R/A .

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TABLE 3.6-1 (Continued) ,'

CONTAINMENT ISOLATION VALWS -

I

. M lHUM e VALVE NtEBER - ISOLATIDN TIME c- O EXCT F BUI ING PURGE SUPPLY (SEC) ' l y AND EXHAUST 150MTION FUNCTION 5

f 9 1.

2.

0001A-f#.

00018-hi

\ Reactor Building Purge Supply Reactor Building Purge Supply '

/

5 Reactor Building Punje Exhaust , 5

3. 0002A-All 5

4. 00028-1]l Reactor Building Purge Exhaust / 5

5. 6.456-lG Alternate Reactor Buf1 ding Purge Sypply Line Alternate Reactor Building Purge Supply Line 5

6. 6057-lE 5

7. 6066-llR llernate Reactor Building Purge Exhaust Line 5

8. 6067-1E Alth nate Reactor Building Phrge Exhaust Line l III ,'

D'. HANUAL N/A w 1. 8767-DN _DemineralizeA ater'Line .N/A Demineralized r Line

) 2. 8768-DN Fire Serv!cp4iose el Supply N/A m 3. 6772-FS N/A e

4. 6773-FS Firs Service Hose Ke (Supply l A Breathirfg Air Supply Li- WA R 5. 2679-1A N/A f 6. 2680-1A Brepth'ing Air Supply Line N/A

7. 6587-MG Bitrogen Supply To Steam Gene ators N/A

8. 2912-5A ,Aleactor Building Service Air N/A

9. 6671-SF / Refueling Cavity Drain Line N/A

10. 6672-5F / Refueling Cavity Drain Line N/A

11. 6597-5F / Refueling Cavity Fill Line N/A

12. 6696-5F / Refueling Cavity Fall Line N/A Reactor Coolant Drain Tank Discharge To Was _

13. 7135-WL j/

E. REH0TENAMUAL.32)

N/A

1. 9602-CC / Component Cooling To R. C. Pumps N/A Seal Infection To Reactor Coolant Pmp A s NE/A

$ 2. 3102A-CSE Seal Injection To Reactor Coolant Pump B

3. 8102ff-CS# N/A I Seal Injection To Reactor Coolant Pump C  ;

. 4. ,3102C-CS# s\

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TABLE 3.5-1 (Continued) w

\ CONTAINHENT ISOLATION VALVES I / IHtm p VALVE NtNBER F. CHECK \ FUNCT g ISOLATION TIME (SEC) q H 1. 7541-AC CPDH Coolant Water Inlet Line M/A N

2. 7544-AC CROH Coolant Water Outlet Line WA

3. 9570-CC

\- Component Cooling To R. C. Ptap 8 earing M/A

4. 9689-CC Component Coollag From R. C. Purg Beafings N/A

5. 3103-C5 Reactor Coolant Puop Seal Water yefurn N/A

6. 8368A-CS# 5eal Injection To R. C. Pump JV M/A

- 7. 83688-CS4 SealsInjection To R. C. Pump b M/A

8. 87 BC-CS# Seal Injection Tu R. C. Pdnp C WA Charging'Line To Regeperative Heat Exchanger M/A

9. 8381-CS Fire Servite. Del do Charcoal Filters N/A

' 10.

6799-FS

11. 2661-IA Instrur it Alb ly To Reactor Building M/A R 12. 65BB-NG Nitrogen Suppl o Steam Generators ' - N/A

• PressurizeyRelief Ignk Hakmp Water Lir.e N/A

13. 8046-RC ServiceAfr Supply To' Reactor Building N/A i 14. 2913-SA N/A

@ 15. 3009A-SP Supply'To Reactor Building Spray Mozzles

" 16. 30098-SP $ M(A (9pply To Nitrogen Reactor Supply Building Spray Houles

17. 89(7-51 ccualator Nx N.~A Il/A

18. 8861-51 Fill Line To Accumulators

s

's i

Valve not subject t ype "C" leakage test.

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be opened on an interuittent basis under administrative control.

(1) Hanual valves;r

'N

{a (2) Remote a ual f valve positions are maintained by administrative control. 'x N 5 (3) IF& ro'Irisions of Specification 3.0.4 are not applicable from December 23, 1982, until Ju'ly 1.1983.

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CONTAlnHENT SYSTEMS BASES H ?Hutc'D St' T#t SAffTt'M'JWf/S 3/4.6.4 CONTAINMEh'T IS0i.ATION VALVES 73 The OPERABILITY of tne containment isolati valves ensures that the reactor building atmosonere will be isolated om the outside environment in the event of a release of radioactive mater i to the reactor building atmos-phere or pressurization of the reactor b ' ding and, is consistent with tne requirements of GDC 54 thru 57 of Appapdix A to 10 CFR Part 50. Conta hment isolation within the time limits spec 444ed-for those isolation valves designeo to close automatically ensuret that the release of radioactive material to the environment will be consistent with the assumptions 'Jsed in the analyses for a LOCA.

3/4.6.5 COMBUSTIBLE GAS CONTkOL

' The OPERABILITY of the equipmen*, and systems required for the detection

.' and control of hydrogsin gas ensures that this equipu.ht will be available to

[ maintain the hydrogen concentration within the reactor building below its flammacie limit curing pc t-LOCA conditions. Either recomoiner unit (or the gt)n l/ purge system) is capaole of controlling the expected hydrogen generation i

associated with 1) zirconium-watea reactions, 2) radiolytic decomposition of water and 3) corrosion of metals within con *ainment. These hNrogen control systems are consistent with the recommendations of Regulatory Guide 1.7,

" Control of Comoustible Gas Concentrations in Containment Following a LOCA,

Maren 1971.

The hydrogen nixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent

\ localized accumulations of hydrogen from exceeding the flammable li! nit.

The opening of locked or sealed c'losed containment isolation valves on an intermittent basis under ocministrative control includes the following considerations: (1) stationing an operator, ,vno is in constant communication with control room, dt the VoIVe Controls, (2) instruCIing this operator to CICse these volves in an acc1 dent situation, and (3) assuring that environmental conditions will not preclude access to close the valves l

l S'.1MMER - UNIT 1 8 3/4 6-5

DEFINIIlQNS I

CONTAINMENT INTEGRITY a 1.7 CONTAINMENT INTEGRITY shail exist when:

a. All penetrations required to be closed during accident conditions are either:

1) Capable oeing closed by an OPERABLE cc , tainment automatic isolat'sn valve system, or

2) Closed by manual calves, bl:nd flanges, or deactivated automatic valves secured in their closed positions, except for valves that art open under administrative control as permitted by Specificetion 3.6.4,

b. All equipment hatches are closed and sealed,

c. Each air lock is ir compliance with the requirements of Specification 3.6.1.3,

d. The containment leakage rates are within the limits of -

Specification 3.6.1.2, and ,

e. The sealing mechanista associated with each penetration (e.g.,

welds, bellows, or 0-ri"gs) is OPERABLE.

CONTROLLED tEAKAGE  ;

1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

CORE AtTERATION l.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspem .cn of CORE ALTERATION shall not preclude completion of movement of a cor .nent to a safe conservative position.

_ CORE OPERATING LIMITS REPORT ,

1.9a The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document that provides core operating limits for the current operating reioad cyc'le.

Th9 cycle specific core operating liinits shall be determined for each reload c, in accordance with fpecification 6.9.1.11. Plant opera'. ion within

b $

operating limits is addressed in individual specifications.

DOSt EQUlVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentratio. of I-131 (micrecurie/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14b44, " Calculation of Distance Factors for Power and Test Reactor Sites."

SUMMER - UNIT 1 1-2

1 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONlAINMENT IN1EGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRfTY shall be maintained.

1 APPL ICABil lTY: MODEc '

2, 3 and 4 ACil0N:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STnNDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD-j SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITV shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

• not capable of being closed by OPERABLE containment automatic isolation l valves and required to be closed during accident conditions are closed by valves, blind flatiges, or deactivated automatic valves i secured in tridir positions, except for valves that are _open under i administrative control as permitted by Specification 3.6.4.

b. By verifying that each contcinment air lock is in compliance with the requirenents of Specification 3.6.1.3.

c. After each closing of euch penetration _ subject to Type B testing, except the containment air locks, if opened following a Type A or B l test, by leak rate testina'the seal with gas at Pa (47.1 psig) and verifying'that when-the. measured leakage rate for these seals is added to the leakage rates determined pursuhnt to Specification ,

4.6.1.2.d for all other fype B and C penetrations, the combined -

leakage rate is less than 0.60 La.

• Except valves, blind flanges, and deactivated automatic valves which are L located inside the containment and are locked, sealed.or otFerwise secured in the closad position. These penetrations shall be verified closed during each COLD SHUTDOWN cxcept that such verification need not be performed more-often than once 7er 92 days.

SUMMER - UNIT 1 3/4 6-1

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1 CONTAINMENT SYSTEMS.

3/4.6.4 LONTAINMENT ISOLATION VALVES l LIMITING CONDITION FOR OPERATION 3.6.4 Each containment isolation valve sha'<1 be OPERA 8LE.*

APPLICABILITY: MODFS 1, 2, 3 and 4. l ACTION:

With one or more of the isolation valve (s) inoperable, maintain at least one-isolation valve OPERABLE in each affected penetration that is open and either:

a. Restore the inoperable valve (s) tr OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

b. .solate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least

, one closed manual valve or blind flange, or

d. Be in at lear t HOT STANDBY w". Sin the next 6 hot'rs and in COLD SHUTDOWP witnin the following 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />.

i The provisions of Specification 3.0.4 do not apply.

! SURVEILLANCE REQUIREMENTS

'.. 6.4.1 Each containmen' isolation valve shall be demonstrated OPERABLE l prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by pe*'ormance of a cycling test and verification of isolation time.

, 4.6.4.2 Each containnent isolation valve shall be demonstrated OPERABLE

during the CGLD SHUTDOWN or REFUELING MODE AT LEAST ONCE PER 18 MONTHS BY:

a. Verifyiro that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position,

b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation p]si1 .m.

l c. Verifying that on a Reactor Building Purge and Exhaust isolation i test signal.-each Purge and Exhaust valve actuates to its. isolation position.

• Lucked or sealed closed valves may be opened on an intermittent basis under administr ve control.

i .

. SUK'3R - UNIl 1 3/4 6-17

CONTAINMENT SYSTEMS SURVtILLANCE REQUIPEMENTS (continued) 4.6.4.3 lhe isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specif; cation 4.0.5.

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T

_ SUMMER - UNIl 1 3/4 6-18

TABLE 3.6-1 ONTAINMENT ISOLATION VALVES Deleted t

4 a

L Pages 3/4 6-19, 3/4 6-20, 3/4 6-204, 3/4 6-20b,and 3/4 6-20c deleted 9

7 di SUMMER - UNIT 1 3/4 6-19

f CONTAINMENT SYSTEMS ,

BASES

]/4._6.4 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the reactor building af91 sphere will be iso!ated from the outside environment la the event of a release of re ; active material to the reactor bJilding atmos-phere or pressuritation of the reactor building and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.

Containment isolation within the time limits required by the saf2t3 analysis

- for those isolation valves designed to close automatically ensuies that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

The opening of locked or sealed closed containment isolation valves on en intermittent basis under administrative control includes the foilowing considerations: (1) stationing an operator, who is in constant communication with control room, at the valve centrols (2) instructing this operatur to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves.

1/4.6.5 COMbOSTIBLE GAS CONTROL ,

The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within the reactor building below its flammable limit during post-LOCA conditions. Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. These hydroger. control j' systems are consistent with the recommendations of Regulatory Guide 1.7,

" Control of Combustible Gas Concentrations in Containment following a LOCA,"

l March 1971.

i

-The hydrogen mixing systems are provided to ensure adequate mixing of

, the containment atmosphere following a LOCA. This mbing action will prevent

localized accumulations of hydrogen from exceeding the flammable limit.

l l

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- SUMMER - UNIT 1 B 3/4 6 '

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Attachment 2 to Document Control Desk letter TSP 920003 Page 1 of 2 PROPOSED TECitNICAL SPECIFICATION CHANGE - TSD 920003 VIRGIL C. SUMMEF NUCLEAR STA110N DESCRIPTION AND SAFETY EVALUATION DESCRIPIION Of AMENDMENT REQUESI Technicai Specification (TS) 3/4.6.4, Containment Isolation Valves, currently applies to only those valves listed in Table 3.6-1. Table 3.6-1 is comprised of valves classified as containment isolation valves (CIVs) by the plant -

licensing basis. However, a change to the plant licensing basis could cause a change to the list of CIVs and, therefore, would require a change to TS. ,

Generic Letter (GL) 91-08, Removal of Component Lists from Technical Specifications, prnvides NRC approved guidce for the removal af Table 3.6-1 from TS. This amendment request followi the example and guidance of GL 91-08 regarding remival of Table 3.6-l from the VCSNS TS. The result of removing Table 3.6-1 is that the Limiting Condition for Operation, Action Statements, and Surveillance Requirements of TS 3/4 6.4 will apply to all valves classified as CIVs by the plant licensing basis. The list of applicable valves will be identified and matitained via the control of plant procedures. .

A list may also be contain'4 in the FSAR, but the FSAR list cannot be used as the controlling list to a, T5 requirements.

SAFELY EVALUA110N This eva' ation is based on following the guidance given in GL 91-08.

Demonstrating that this amendment request models the NRC approved requirements of the GL will assure that there are no safety implications associated with the amendment. -

Applicability This amendment request does not affect the technical requireuents of the specification, but rather allows the list of applicable valves to be controlled by plant procedures In lieu of being listed in TS. Therefore, the intended scope of applicability related to the specification requirements does not change.

TS 3.0.4 Table 3.6-1 does not include a footnote which excludes certain valves from the provision of TS 3.0.4. However, this exclusion has been incorporated into the amendment request in order to model tne gu-idance presented in GL 91-

08. Also, as stated in GL 91-08, this exception is acceptable and consistent with the guidance provided in GL 87-09.

Att'chment a 2-to Document Control Desk Letter TSP 920003 Page 2 of 2 locked or Sealed Valves Table 3.s-1 includes a footnote which allows locked or sealed valves to be opened under administrativ3 control. The amendment request addresses this footnote by 1) relocating the footnote ;o apply to the Limiting Condition for Operation, 2) modifying thc Containment Integrity definition by removing the reference to Table 3.6-1 and adding a reference to the locked or sealed valves that are permitted to be ooened under administrative controls per Specification 3.6.4, and 3) including the flRC guidance for administrative control in the bases for this specificatinn. A portion of the last sentence  ;

I of this guidance was omitted to prevent any misunderstanding as to what the administrative controls are to accomplish. These modification ,neet the direction given in GL 91-08 which endorses them as an acceptable alternative.  ;

I Remote-Manual Valves Table 3.6-1 also includes a note regarding administrative control of remote manual valves. A remote manual valve is always ender administrative control and meets GDC 57 Closed System Isolation Valves, requirements of these i valves. Opening these valves does not contradict their operability requirements. Therefore, per the instruction of GL 91-08, which states that this footnote may be eliminated, the amendment request has omitted the footnote.

Type C Le6k Test Some of the valves in Table 3.6-1 are denoted as being exempt from Type C i

leak testing requirements of Appendix J to 10CFR50. This denotatko serves to clarify which valves have been granted exemptions from the NRC or which valves are non-applicable to Appendix J. These denotations are not requirements associated with this specification, but rather they serve as an aid to prcvide information related to Appendix J requirements. Therefore, in accordance with GL 91-08, this amendment request deletes these denotations.

. Valve Stroke Times The finai point to be addressed regarding Table 3.6-1 is the maximum isolation time listed for automatic valves. These times ure included and verified by the inservice testing (IST) requirements ot Spacification 4.0.5.

Therefore, per GL 91-08, these isolation times are not necessary and have not i beer included in the amendment request.

In summary, this amendment request only reformats TS 3/4.6.4 in that the technical intent of the specification bas not been altered, the requirements contained in the specification still apply to the same components, and the criteria which define the list of applicable components have not been affected. Therefore, the amendment request only differs from the current -

specification in that um I!st of c'omponents will be controlled in plant procedures.

Based on the above discussion and on the guidance of GL 91-08, SCE&G considers this amendment request to have no adverse impact or potential related to the plant or public's safety or health.

f m - -...r, . ~ ~ . _ - . . . - - . - - , < - ,, -- - - , - _

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o e e LAtt'achment 3 to Document Control Desk letter TSP.920003 Page-1 of 1 i

PROPOSED TECHNICAL SPECIFICATION CHANGE - TSP 920003 '

V'9GIL C. SUMMER NUCLEAR STATION DETERMINATION OF NO SIGN!f!CAN1 HAZARDS-CONS!0ERAi>0N i DESCRIPTION Of AMENDMENI REQUESI Technical Specification (IS) 3/4.6./., Ggntainment isolation Valves, currently applies to only those valves listed in Table-3.6-1. Table 3.6-1 is comprised of valves classified as containment isolation valves-(CIVs) by the plant licensing basis. However, e change to the plant licensing basis could cause a change to the list of CIVs and, therefore,-would require a change to TS.

L Generic Letter (GL) 91-08, Pemoval of Component Lists from Technical Specifications, prcvides NRC approved guidance for the removal of Table 3.6  ;

from 15. This amendment request follows the example and guidance of GL 91-08  ;

regarding removal of Table 3.6-1 from the VCSNS TS. The result of removing Tab'e 3.6-1 is 6 hat the Limiting Condition for 6peratirn, Action Statements, and Surveillance Requirements of TS 3/4 6.4 will apply to all valves classified as CIVs by the plant licensing hasis. The' list of applicable valves will be identified and maintained via the control of plant procedures.

. A list may also be contained in the FSAR, but the fSAR list cannot be used as the controll'.ng list to apply TS requirements.

L BASIS FOR PROPOSED NO SIGNIFICANI IlAZARDS CONSIDERATION i

l l 1) This amendment request does not involve a significant increase in the l, probability or consequences of 1 previously evaluated accident. This >

- request removes the list of valves (Table 3.6-1) from Technical Specifications, but it does not alter the application of the tecnnical

requirements which are contained in the specification. This amendment l does not require any modifications to plant hardware or oper ating l- practices. The efore, the amendment request has no effect on any L previously analyzed accidente.

2) This amendment request does not-create the possibil-ity of a new or different kind of accident from any accident previously evaluated. The amendment request does not affect any operating, maintenanca, er i surveillance practices or methods; also, there are'no desig., or nardware modifications associated with-the proposed change. Thecefore, .he possibility of a malfunction or failure or the possibility of a work practice rasulting in a new or different kind of accident remains unchanged.

3) This amendment request does act involve e. significant rcJuction in a margin of safety. The removal of Table 3.6-1 has no impact on the performance of the plant nor does it reduce the scope or the requirement of TS 3/4.6.4. Therefore, there is not a reduct' ion to any safety margins due to this amer.dment -0 guest.

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