ML20154J299

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Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B
ML20154J299
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Site: San Onofre  Southern California Edison icon.png
Issue date: 10/09/1998
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NUDOCS 9810150211
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ENCLOSURE 1 CORRECTION PAGES FORPROPOSEDCHANGENPF-10/15-468, SUPPLEMENT 1 l

l 9810150211 981009 PDR ADOCK 05000361 P PDR

6,t, a 4 .As a s A a --+s- _ --L.m-a&-we-a , 4.c 3-J,2 4 1m,-,as--- J ---.- h, O

E ATTACHMENT A EXISTING PAGES UNIT 2 i

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, Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.12 Ventilation Filter Testing Program (VFTP) (continued)

The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are applicable to the VFTP test frequencies.

5.5.2.13 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:

a. At least once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-04057-81 has a water and sediment content of less than or equal to 0.05 volume percent, an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 0 40 C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance with ASTM-D975-81.
b. At least once every 92 days by obtaining a sample of fuel oil in accordance with ASTM-D4057-81 and verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

5.5.2.14 Configuration P.isk Management Program (CRMP)

The Configuration Ri d Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed Completion Time has been granted. The program shall include the following elements:

a. Provisions for the control and implementation of a Level 1 at power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
b. Provisions for performing an assessment prior to entering the c LC0 Conditien for preplanned activities.
c. Provisions for performing an assessment after entering the LC0 Condition for unplanned entry into the LC0 Condition.

4 SAN ON0FRE--UNIT 2 5.0-20 Amendment No. 139

.- - - . . . . .. .. - - - . . - - . - . ~ . - . - - - - - . - . - - - - . .- - ..

. Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.14 ConfigurationRiskManagementProgram(CRMP) (Continued)

d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LC0 Condition,
e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.

i SAN ON0FRE--UNIT 2 5.0-20a Amendment No. 139

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9 ATTACHMENT B EXISTING PAGES UNIT 3

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Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.12 Ventilation Filter Testing Program (VFTP) (continued) l The provisions of Technical Specification Surveillance Requirement l 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are

applicable to the VFTP test frequencies.

5.5.2.13 Diesel Fuel Oil Testing Program l

This program implements required testing of both new fuel oil and ,

stored fuel oil. The program shall include sampling and testing '

requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following: ,

a. At least once per 92 days and from new fuel oil prior t?

addition to the storage tanks by verifying that a sample .

obtained in accordance with ASTM-D4057-81 has a water and sediment content of less than or equal to 0.05 volume percent, an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 0 40 C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance with ASTM-0975-81.

b. At least once every 92 days by obtaining a sample of fuel oil
in accordance with ASTM-04057-81 and verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

5.5.2.14 Configuration Risk Management Program (CRMP)

The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed Completion Time has been granted. The program shall include the following elements:

a. Provisions for the control and implementation of a Level 1 at power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
b. Provisions for performing an assessment prior to entering the LC0 Condition for preplanned activities. c
c. Provisions for performing an assessment after entering the LC0 Condition for unplanned entry into the LC0 Condition.

l SAN ON0FRE--UNIT 3 5.0-20 Amendment No. 131

a e Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.14 Configuration Risk Management Program (CRMP) (Continued)

d. Provisions for assessing the need for additional actions after the discovery of-additional equipment out of service conditions while in the LC0 Condition.

C

e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.

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i SAN ON0FRE--UNIT 3 5.0-20a Amendment No. 131

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l ATTACHMENT C PROPOSED PAGES REDLINE AND STRIKEOUT UNIT 2 f

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Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs,'and Manuals (continued) i l

i 5.5.2.14 ' Configuration Risk Management Program (CRMP) (Continued)-

d. Provisions for assessing the need for additional actions after l the discovery of additional equipment out of service conditions while in the LC0 Condition. i 1

'e . Provisions for considering other applicable risk significant  !

contributors such as Level 2 issues, and external events, i qualitatively or quantitatively. l l

si5:2[1'5 C6hisinmestleiksge[RstilTiiMiii!Pfoghiiii l l

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I A L prosfiihis hil l %sTestibliihidit6Msplinisnist b'eysikig e fritiTtes tiiig ofstheNontsinfndnt7asLrequired:Iby1101CFR150!54(o)iand#10iCFRi50, ~~ l rovedfexempti6nshLThis i

.AppendixiJH0ptidn!BMistmodified?by?

p rog ranilshalli besi n f accopdancs]wi t h (t he app (guidelines (c6ntaihed(in Reg ul a t o rf ?Gui de t11163 R" Perfo rms.nce-Ba s e d f' Co n t a i nme n t (Le aksTes t.

" "' ' ~ " ' ' ' "

Program)"idated]Septemb.erfl9957'"

T6h 'cil culitid ?peikEEosihihniidf?Idie"rnin pre's s ureiriliisd i f6TE hs design basishioss{ofpcoolant:6anidentWPMis155?1?psigi(P2:Will conservatively;belassumedito;befequalito2thescalculated peak c con tai ninen6i nte rnaRpressurei for; theides i gn t bas i s !Mai siSt eanil.f nd

, Breakj(56s6fpsig)if6bthefpurpossieficontlinmentitsstingsin ~ ~ ' ' '

accordancelwiththisVechnica.liSpecification)k T6Ellisisi' m snifill6iiabli 04 0 %oficontainmentia?c'6 Miin56stM eik;igs Wit;s HI M E M E lha irlwei@tiperldayR

- _.~ - n ,.

Le.akag,n

. egateg,acceptancej,criter}a_ tare:

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ThiiC0hfiihiiisifE60eFil l31 eikigeli^rsis Fadhejifihde TcfTieHbh fisL his ahcord 0 %sndelwi thit hi sfyr6d rain S t hlejl eskag ej fs telaccep ~ ~ ~

l ' riteri.alarelM0;60il.nfonithelType c AandgypelCitesthand

! 001751LnferithelTypejAlte.sts; 6I KlRiddk3s5EIhg yidEepiinEEMijiABildrEj L I)' 07Erill7sMi nc kjl eikigelfilij i sid01053dhidifts s tid at::W Pg

2) F6% Eidhid66F, $t hili da kigeirstisliiM0j01Mhen pressut;i zed!to M 9;0lpsigi i

i SAN ON0FRE--UNIT 2 5.0-20a Amendment No. H 9

4 1 l Procedures, Programs, and Manuals l 5.5 l 1

5.5 Procedures, Programs, and Manuals (continued) l I

5.5.2,15 Con ta i nme n t (Le_a kag e1Ra ts ?Te s t;i ng 2 Prog ramM(Cb h fi n u ed) 1 1

The provisions {oflSurveillancelRsquifementi3!012Td6;notlapplyctofths t'es tJf requenci es 2 s peci fi ed ki n:L thelCon t ainmen t iLeak~ age :- Rat e : Te s ting l

Program Q Howeverbtes tl: fre'quenci es;ispebi fi ed k:1.n; thi s? Prog ram ;may;: be extended

" Industry Guideline0onsistent:iwithithelguidanceiprovidedFin'NEIt94401,h70f 2For?Implementihg;Performande-Based Optio '

10C FR . 50 ; fApp ehd i x fJ ; " L'a s : endo rs ed i bfi Recj ul a tc ry[Gu i d e -: 1.163.

S p eci fi c al ly , [N E I j 94-01[: h as ;t h.es ej.p rov i s i o n_s ;f orit es t.lf reque n c i e s extension-11 Con sist sni si t h ? s'taiidaid ?sc6sadl i hg s pf adnees 5foFJTeini cal SpecificationsLRequiredlSurveillancessintervals5for . . . . .

recommendediTypelA testingimay beTextended:by)upitol151 months.s Thisloptionsshould:be used!onlyfinicases;where refueling, schedules;haveibeenTcha'ngedstoiaccommodateiotherbfactors.

2. C6nsi sten f Mi thlitindsEsElisdul i ng 1pract i css iforlieshdi cal Speci fi cat 16nsfRequi red (Surv eil l. ances ,fi nte rval s ifor.: the l recommended;surveillancesfrequency;for; Type-BHandLTypeiC testing ~mayl.befextendedbyupftol2SipercentLoffthel. test interval;s notjtol exceed 15imonth12

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Th eip rofi 51 o n s%fiSu ry si l linc ElR5q u i reidd nO3!0!3 ?a be ;^a ppl i ss bl. e f to t.h e ; . Con t;ai nme n tilea ka g e [Ra t elTe s t i ngl P rog ram. ~ '

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, SAN ON0FRE--UNIT 2 5.0-20b

Containment B 3.6.1 BASES i

BACKGROUND 2. closed by manual valves, blind flanges, or l

' (continued) de-activated automatic valves secured in their closed gositions,exceptasprovidedinLC03.6.3, Containment Isolation Valves."

b. Each air lock is OPERABLE, exceat as provided in LC0 3.6.2, " Containment Air Locks."

APPLICABLE The safety design basis for the containment is that the SAFETY ANALYSES containment must withstand the pressures and temperatures of the limiting DBA without exceeding the design leakage rate.

The DBAs that result in a release of radioactive material within containment are a loss of coolant accident, a main ejection accident (rlef). 2). steam In theline breakof(MSLB analysis each of, and a control elem these accidents, it is assumed that containment is OPERABLE such that release of fission products to the environment is controlled by the rate of containment leakage. The containment was designed with an allowable leaka 0.10% of containment air weight aer day (Ref. 3)ge rate

... .. T hi s of leakage rate is defined in 10 CFl 50, Appendix J,iOption_LB (Ref. 1), as L the maximum allowable containment leaka'ge rate at the cal:culated maximum peak containment pressure of55.5pjig,whichresultsfremthelimitir.gDBA,..

$w is a dco - 'to thedr_ basis ",SLC (Ref. 5) ._ inte velate.,)ch_dlesignibasis o .

?lossfof-coolantiacci dent E P n at 55 :li psigs(Ref h 5) l;PJ wil l tconservativelyibef assumed doi be eg'ual ato ithe ical cul ated s peakicontai'nment .f i nternal ? pres sure ofithedesignibasis)MainiSteamlLinelBreakh56;6psigX(Reft c 5)hforsthe1 purpose;of2 containment withithisiTechni. cal.1Specificati.onstestingiin;accordance~

Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY.

The containment satisfies Criterion 3 of the NRC Policy Statement.

I LC0 ,gn C ginm pt OPERABILITY js mainta,ine,d p ] miting 1,9akage to nisu n snu oussy sonum mi sci t o vo iv.wiiu v, nyyunuia v, (Re f . Eils 0 i L$ exceptlprior%toitheV fi rs tis t a rtupl af ter performingfairequired!ContainmentsLeakage: Rate l Testing Programileakage s testMAtithis: time,tthef applicableileskage

~ ' ~ ~ ~ ~ ~ ' ' ' *'

limits mustibeimet; '

Compliance with this LC0 will ensure a containment configuration, including equipment hatches, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis.

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(continued)

SAN ON0FRE--UNIT 2 B 3.6-2 Amendment No. 127 05/31/97

. Containment Air Locks i

B 3.6.2 BASES,(continued)

APPLICABLE For atmospheric containment, the DBAs that result in a SAFETY ANALYSES release of radioactive material within containment are a loss of coolant accident (LOCA), a main steam line break (MSLB) and a control element assembly (CEA) ejection l accident (Ref. 2). In the analysis of each of.these l accidents, it is assumed that containment is OPERABLE such that release of fission products to the environment is controlled by tne rate of containment leakage. The containment was designed with an allowable leaka 0.10% of containment air weight per day (Ref. 2)ge This ,

rate of leakage rate is defined in 10 CFR 50, Appendix J,10ptionLB (Ref.1), as L : the maximum allowable containment. leakage rate at the calculated maximum l pressure r (-P.) Of 55.5 psig, "hi peak containment internalh rc:ults from 00A,jhichjs designesi3JiSLO }' Ref de s i gn ; bas i s tl os s aoficcol ant #acc J.._relatedttd!the dent;mP., fat 9551?psig _.,

(Ref G 3) h ; P/wil UconservatiVelylbe? assumed itolbe ( equal & to the:calculatedye'ak2containmentrinternalipressureof;the'.L f design 5 basis 1MainKSteam1Line;Breakp56;6Lpsig;(Ref.s3)',ifor e theJpurpose:oflcontainmentitestinglin accordance withsthis ~

l TechnicaliSpecificationE This sllowable' leak 5ge pate forms l GeTW'ifWe'icceptance criteria imposed on the SRs '

associated with the air lock.

The containment air locks satisfy Criterion 3 of the NRC Policy Statement. ,

LC0 Each containment air lock forms, Jart of the contai_nment vessure boundary. As part of tie containment? pressure

)oundar I of 'the~containment y, the air lock safetyrate leakage fu'nction is related~'to'~'

resulting from a DBA. control Thus, each air lock's structural integrity and leak tightness are essential to the successful mitigation of such an event.

Each air lock is required to be OPERABLE. For the air lock to be considered OPERABLE, the air lock interlock mechanism must be OPERABLE, the air lock must be in compliance with the Type B air lock leakage test, and both air lock doors must be OPERABLE. The docr seals and sealing surface are considered a part of the air lock. The interlock allows only one air lock door of an air lock to be opened at one time. This provision ensures that a gross breach of containment does not exist when containment is required to be OPERABLE. Closure of a single door in each air lock is sufficient to provide a leak tight barrier following postulated events. Nevertheless, both doors are kept closed when the air lock is not being used for normal entry into eftd o'r exit from containment.

(continued) l SAN ON0FRE--UNIT 2 B 3.6-6 Amendment No. 127 0S/31/97

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l ATTACHMENT D l PROPOSED PAGES t REDLINE AND STRIKEOUT UNIT 3

l t . Procedures, Programs, and Manuals l 5.5 l 55 Procedures, Programs, and Manuals (continued) 1 5.5.2.14 Configuration Risk Management Program (CRMP) (Continued) )

d. Provisions for assessing the need for additional actions af ter the discovery of additional equipment out of service conditions while in the LC0 Condition.
e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.

5.5.2.15 Containment { LAaksgelRate?TOstingl.P.rogram A'progfami shsil ? beles~tabl ishsditiinyilSment?the?l saksge . fats? testing of the containment ~as; required byJ10:CFR 50.54(o) sand 110 CFR.50, Appendix::J, Option:Bn ns. modified by approved exemptions. LThis program shall bepinlac;ordanceiwith;the guidelines. contained in Regulatory Guidell.163,4" Performance-Bas,ed:; Containment.., Leak-Test Program."i. dated; September 1995.-

Thecalcul'aind:p'eakiontainmentlinsesnali design basis loss-of-coolant accident,:P.,psessufe :is :55.1'psig :(P relatEd to the i will ,

conservatively be assumed to be equaldto the calculated. peak I containment:internalDpressure forRthe design basis Main Steam Line ~

c Break:(56.6 psig)nfor:the purpose:of containmentitestingji.n l accordancewithlthisjTechnical; Specification). l

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l The maximumisllbwablsicontainmentileskige3rateMLj: Eat lPl,jhs.11?;bi 1 0.10%;of; con.tainmentzair weight;per day.:- l

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Leakigedate lacceptariceic8 tsFialar;si ai ThelContainmenkoverallEleakasje ratefacceitan'ce criterion is (l' 0. Lg. .:During:theffirstlunit'startupfollowingutesting.in~

accordance with this program,;thelleakaget ratesacceptance criterialare 40.60 L,ifor3theJTypeLBL;and -TypelCitest.s land s 0 75:Lf;for thejType3Aitests; z

b? Affil64kftestingTaccep.tancsicri.tefiRare: 1

^

1)~ Ov'ersl1iair:11ockl1.eaksg'efpsieJis sl07.05Ttfwhenitested at M.P,

2) Forfeach tdoor, . the-: leakage). rate is 4 0101 Ll: when pressurized to..f 9;0~ psig.

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SAN ONOFRE--UNIT 3 5.0-20a Amendment No. 4-3+

. Procedures, Programs, and Manuals 5.5 55 Procedures, Programs, and Manuals (continued)

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. C'ohtiihmelntileikigs2RAMTssii ng]Pfog rM(Cdhlfiiu ed) I i

The?p F69i sionsiof[SUEVE111 side? liiiii rimenE 3f072IdolnblEa ppl97tolthe test; frequencies 3pecifiedsin theiContainmenti.LeakagesRate):; Testing .

Programh:(HoweverJtest{freque;nciesis'pecifiedtinithislProgram;may;be .

extended:consistentiwithLthe guidance <provided2iniNEls94-01 L  ;

" Industry Guideline:wForilmplementing4 Performance-Basedi0ptionf0f

~

10CFR:)50,TAppendix % "fassendorsed;by) Reg'~ulatory; Guide 1.12163 L -  ;

Specif1cally;iNElf9,4-01 has;;gtheseiprovisio.nsjforftest1 frequencies '

extension:

L 'CansisfedHsiiO:slifidiFUishiddllhgipfiesihhstforl:Tsehhisal SpecificationssRequiredSurve111ancesbintervalsifor'i.l...?._

~

recommended 1 Type: Attesting (may:belextendedibylupcto?l5imonthsl ~~

This" option ishouldlbe:used;on19.Aini:casestwheref refueling ' l schedul es ;havel beenichanged ito; accommodate .:othertfactors.

I

2. C6ns~istEndsith?stAhdsedis~chedulin'gl.pradneenfoNTedhhical SpecificationstR_equiredSurveillancesnintervalsi:for.:1the recommended surveillance 3frequencylforjTypetBHandaType'C testingJmay.::belextended:by;up(to:;25ipercent(of gthe test interval ,inot!to; exc.eed jl5 : months. .

J Thelpiovisi3hs96ffSdrvsillanceiRes;u1FeisssS3!013Ca~re applichle to ' '

thejContainmentileakagerRateiTestingjProgram!'"

SAN ON0FRE--UNIT 3 5.0-20b

l . Containment l B 3.6.1 BASES .

BACKGROUND 2. closed by manual valves, blind flanges, or (continued) de-activated automatic valves secured in their closed gositions,exceptasprovidedinLC03.6.3, Containment Isolation Valves."

b. Each air lock is OPERABLE, exce)t as provided in LC0 3.6.2, " Containment Air Loc (s."

APPLICABLE The safety design basis for the containment is that the SAFETY ANALYSES containment must withstand the pressures and temperatures of the limiting DBA without exceeding the design leakage rate.

The DBAs that result in a release of radioactive material within containment are a loss of coolant accident, a main steam line break (MSLB), and a control element assembly ejection accident (Ref. 2). In the analysis of each of these accidents, it is assumed that containment is OPERABLE such that release of fission products to the environment is controlled by the rate of containment leakage. The containment was designed with an allowable leaka 0.10% of containment air weight per day (Ref. 3)geThis .

rate of leakage rate is defined in 10 CFR 50, Appendix J,L0ption.B (Ref.1), as L.: the maximum allowable containment leakage rate at the calculated maximum peak containment pressure (P.) of 55.5-psig, which results from the limiting DBA, I i-whichisadusln.basisfiSLO(Ref.5).internalpressure related to the esign# basis ^1oss-of-coolant? accident, P., at

~

will? conservatively be: assumed .to'be 55.1/7 psi.g equal to.the(Ref.15)..

calculate P'd peak' containment internalLpressure c ofi:theidesign-basis' Main Steam Line Break,c56.6'psig4(Ref.

5), 'for the:. purpose. ofc containment testing in :accordance withithis TechnicallSpecification.

Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY.

The containment satisfies Criterion 3 of the NRC Policy Statement.

LCO Containment OPERABILITY is maintained by limiting leakage to within the-etteptance criteria of-10.CIR 50, Appendix J (Ref.1)(l'.0 Li, except prior to thel first;startup after performing a required Containment:-Leakage Rate Testing.

Program leakage test. : Atc this. time,'the. applicable leakage limits must be met.

Compliance with this LC0 will ensure a containment configuration, including equipment hatches, that is

structurally sound and that will limit leakage to those l leakage rates assumed in the safety analysis.

l (continued)

[

SAN ON0FRE--UNIT 3 B 3.6-2 Amendment No. 116 05/31/97

Containment Air Locks l B 3.6.2 J l BASES,(continued)

APPLICABLE For atmospheric containment, the DBAs that result in a  !

SAFETY ANALYSES release of radioactive material within containment are a ,

loss of coolant accident (LOCA), a main steam line break '

(MSLB) and a ctntrol element assembly (CEA) ejection accident (Ref. 2). In the analysis of each of these accidents, it is assumed that containment is OPERABLE such that release of fission products to the environment is l controlled by the rate of containment leakage. The containment was designed with an allowable leakage rate of 0.10% of containment air weight per day (Ref. 2)'. . This__

leakage rate is defined in 10 CFR 50, Appendix J R0ption B i (Ref.1), as L.: the maximum allowable containment, leakage rateatthecalculatedmaximumpeakcontainmentinternall 1ressured.) of 55.5 p;ig, wh.ch recu'ts .from thc' Tibiting 00A yhich.is desi design basisflossof;-coolantiact gn bis JiSLO_}'Rc( _3)._L55.11 dent,JPgiat related?

psigtb)_ the l

the2al)ulatedipeakTcontainmsnttinternal?pressureofithe~~~~(R(f.13 c

desiin!basisLMaintSteam:LineBreakp56.6ipsig(Ref$3)sfor C the: purpose?ofscontainmentotestingLin^accordance with this" TechnicalLSpecification: This' allonble'leakagelate forms

~

the~ basis"for'the~ acceptance criteria imposed on the SRs associated with the air lock.

The containment air locks satisfy Criterion 3 of the NRC Policy Statement.

LC0 Each containment air lock forms aart of the containment 3ressure boundary. As part of tie containment pressure i

)oundar of~ the'y, the air lock containment safetyrate leakage function is related resulting from a DBA. to control Thus, each air lock's structural integrity and leak tightness are essential to the successful mitigation of such an event.

Each air lock is required to be OPERABLE. For the air lock to be considered OPERABLE, the air lock interlock mechanism must be OPERABLE, the air lock must be in compliance with ,

the Type B air lock leakage test, and both air lock doors  !

must be OPERABLE. The door seals and sealing surface are considered a part of the air lock. The interlock allows 1 only one air lock door of an air lock to be opened at one time. This provision ensures that a gross breach of containment does not exist when containment is required to i be OPERABLE. Closure of a single door in each air lock is i sufficient to provide a leak tight barrier following postulated events. Nevertheless, both doors are kept closed when the air lock is not being used for normal entry into endor exit from containment.

I (continued)

SAN ON0FRE--UNIT 3 8 3.6-6 Amendment No. 116 05/31/97 l _

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ATTACHMENT E UNIT 2 PROPOSED PAGES

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.14 Configuration Risk Management Program (CRMP) (Continued)

d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LC0 Condition.
e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.

5.5.2.15 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The calculated peak containment internal pressure related to the design basis loss-of-coolant accident, is 55.1 psig (P will conservatively be assumed to be equal to P.,t he calculated pe,ak containment internal pressure for the design basis Main Steam Line Break (56.6 psig) for the purpose of containment testing in accordance with this Technical Specification).

The maximum allowable containment leakage rate, L., at P., shall be 0.10% of containment air weight per day.

Leakage rate acceptance criteria are:

a. The Containment overall leakage rate acceptance criterion is s 1.0 L During the first unit startup following testing in accordan,.ce with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and s 0.75 L, for the Type A tests;
b. Air lock testing acceptance criteria are:
1) Overall air lock leakage rate is s 0.05 L, when tested a t 2 P, .
2) For each door, the leakage rate is s 0.01 L, when pressurized to 2 9.0 psig.

SAN ON0FRE--UNIT 2 5.0-20a

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.15 Containment Leakage Rate Testing Program (Continued)

The provisions of Surveillance Requirement 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. However, test frequencies specified in this Program may be extended consistent with the guidance provided in NEI 94-01,

" Industry Guideline For Implementing Performance-Based Option Of 10CFR 50, Appendix J " as endorsed by Regulatory Guide 1.163.

Specifically, NEI 94-01 has these provisions for test frequencies extension:

2. Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for recommended Typa A testing may be extended by up to 15 months.

This option should be used only in cases where refueling schedules have been changed to accommcdate other factors,

2. Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for the recommended surveillance frequency for Type B and Type C testing may be extended by up to 25 percent of the test interval, not to exceed 15 months.

The provisions of Surveillance Requirement 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

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ATTACHMENT F UNIT 3 PROPOSED PAGES

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.14 Configuration Risk Management Program (CRMP) (Continued)

d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LC0 Condition.
e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.

5.5.2.15 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program", dated September 1995.

The calculated peak containment internal pressure related to the design basis loss-of-coolant accident, is 55.1 psig P will conservatively be assumed to be equal to P.,t he calculated (peak containment internal pressure for the design basis Main Steam Line-Break (56.6 psig) for the purpose of containment testing in accordance with this Technical Specification).

The maximum allowable containment leakage rate, L., at P,, shall be 0.10% of containment air weight per day.

Leakage rate acceptance criteria are:

a. The Containment overall leakage rate acce)tance criterion is s 1.0 L During the first unit startup "ollowing testing in accordan.,ce with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and s 0.75 L, for the Type A tests;
b. Air lock testing acceptance criteria are:
1) Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.
2) For each door, the leakage rate is s 0.01 L, when pressurized to 2 9.0 psig.

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Procedures, Programs, and Manuals I 5.5 5.5 Procedures, Programs, and Manuals (continued)

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5.5.2.15 Containment Leakage Rate Testing Program (Continued) l The provisions of Surveillance Requirement 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. However, test frequencies specified in this Program may be extended consistent with the guidance provided in NEI 94-01,

" Industry Guideline For Implementing Performance-Based Option Of 10CFR 50, Appendix J," as endorsed by Regulatory Guide 1.163.

Specifically, NEI 94-01 has these provisions for test frequencies extension:

1. Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for recommended Type A testing may be extended by up to 15 months.

This option should be used only in cases where refueling schedules have been changed to accommodate other factors.

2. Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for the recommended surveillance frequency for Type B and Type C testing may be extended by up to 25 percent of the test interval, not to exceed 15 months.

The provisions of Surveillance Requirement 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

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