Text

Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments
	ML20140D220
Person / Time
Site:	Hope Creek
Issue date:	05/30/1997
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20140D203	List: LR-N970324, Provides Revised marked-up Pages to Address NRC Reviewer Comments; ML20140D220;
References
	NUDOCS 9706100297
	Download: ML20140D220 (14)
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i Document Control Desk LR-N970324 Attachment LCR H97-08 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)

TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES l

The following Technical Specifications for Facility Operating l

License No. NPF-57 are affected by this change request:

Technical Specification Pace License Condition 2.D Page 6 of License f

4.6.1.1 3/4 6-1 3/4.6.1.2 3/4 6-2 3/4 6-3 3/4 6-4 3/4.6.1.3 3/4 6-5 3/4 6-6 4.6.1.5.1 3/4 6-8 4.6.1.8.2 3/4 6-11 Section 6.8.4.e 6-16a Bases for 3/4.6.1.2 B 3/4 6-1 Bases for 3/4.6.1.3 B 3/4 6-1 Bases for 3.4.6.1.5 B 3/4 6-2 l

l 9706100297 970530 PDR ADOCK 0500035*

P PDR

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+

(

(13) Safety Parameter Display System (Section 18.2, SSER No. 5)

Prior to the earlier of 90 days after restart from the first refueling outage or July 12, 1988, PSE&G shall add the following parameters to the SPDS and have them operational:

a.

Primary containment radiation b.

Primary containment isolation status 4

c.

Combustible gas concentration in primary containment d.

Source range neutron flux 0.

The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticality alarm require-ments of 10 CFR 70.24 was granted in Special Nuclear Material License No.

1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER. This previously granted exemption is continued in this operating license. An exemption from certain require-ments of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER. This exemption is a schedular exemption to the requirements 4

of General Design Criterion 64, permitting delaying functionality of t'he Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent po'wer for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5). Exemptions from 4

certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (:) :n ::::;ti:n fr:: the r ;uf r::: t :f Per:gr:ph !!!.D.2(b)(f') Of ?.pp:ndi: J. ::::pting :;;r:1' centainment :f r !cek !eeks;e tectin; er!::: ::inten:nt: 5:: 5::n per-f:r::d :n th: Ofr 10:k that ::ald :ff::t :fr ?::S :::!'n; ::ptb?'ity (5::ti:n 5.2.5 Of SSEP, 5); (b) an exemption from the requirement of P:r:;r:ph III.C.2(b) 6 Appendix J, exempting main steam isolation valve leak-rate testing.at 1.10 Pa (Section 6.2.6 of SSER 5); fe)- an exemption from Pere;r ph III.D.? ef Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5);

46t} an exemption from P:r:gr:ph III.O.2(:) Of Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and fe) an exemption from P:r:;r:ph III.C.2(:) :f Appendix J, exempting Type C testing of thermal relisf

^

valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue t'sk to the public health and safety, and are consistent with the common cufense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these axemptions, the facility will operate, to the i

extent authorized herein, in conformity with the application, as amended.

the provisions of the Act, and the rules and regulations of the Commission.

s Amendment No. 13 4

x 4

s

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+

3/4.6 CONTnINMENT SYSTEMS i

1(.

3/4.6.1 PRIMA.9" CONTAINMENT

. PRIMARY CONTAINMENT INTEGRITY 4

i LIMITING CONDITION FOR OPERATION 4

3. 6.1.1

{

PRIMARY CONTAINMENT IJIE,GRITY shall be maintained.

APPLICA8* '.ITY:

OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

i s.

within I hour or be in at least HOT SHUT 00 i

Y COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i n

n 7

)

-SURVEILLANCE REQUIREMENTS' 1

'4

4. 6.1.1

)

PRIMARY CONTAINMENT INTEGRITY shall be demo After each closing of each penetration subject to Type 8 a.

except the primary containment air locks, if opened following j

russar l

,' r -

_ or 8 test, by-leak rate testing.t':

in occordonc e,

t' ::: :t P:, '" 1 ;:';;,.

r: :r7;1:; it:t 2:n t': rtend ! P:;; rt:_

r th::: cr 6

4 w,w h Fhey ided te t': '-9 :: --t r t t---d --d i

coweg. L,4up

- ud-^n-t ' " 1 ? d " : !' et'^- ? purrrt t: !:rn'"rr ?:

g4 eam

" 4--d

: 5 --d C ;:=t :t'r:, th t ': ' r S ia er 21 t: 0.50 L:.

~ ~ ~ d b.

At least once penetrations **per 31 days by verifying that all primary containment s'

not capable of being closed by.0PERABLE containment automatic isolation valves and required to be closed during accid conditions are closed by valves, blind flanges, or deactivated

}

automatic valves secured in position, except as, provided in Table 3.6.3-1 of Speelfication 3.6.3.

s By verifying each primary containment air lock is in compliance w c.

the requirements of Specification 3.6.1.3.

t 3

d.

By verifying the suppression chamber is in compliance with the 1

requirements of Specification 3.6.2.1.

2

See Special Test Exception 3.10.1 i

- Except valves, blind flanges, and deactivated automatic valves whic in the closed position.inside the primary containment, and are locked, each COLD SNUTDOWN except such verification need not be i

' g' primary containment has not been de-inerted since the last verification or j

more often than once per 92 days, a

HOPE CREEK i

3/4 6-1 j

I l

l CONTAIhMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION

3. 6.1. 2 Primary containment leakaae rates shall be limited to:

mes va+w An overall integrated leakage ratep f !r :

a.

thir er equ:! te L

nt:f nn. ;ir p;r 21 h;;r; ;t p,,18, 0.5 ;=

.I4SELT

t by.; i;ht Of th:

m o "* * * * '

b.

A combined leakage rate I!r th:n er egn! t: 0.50 L for all Ac[.y 4e penetrations and all valves listed in Table 3.6.3-1, ex8ept for main ce steam line isolation valves *, valves which form the boundary for the RA A #

l long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C i

tests. *.:n prr ri:cd te P,, 19.1 pri;.

Less than or equal to 46.0 scfh combined through all four main steam c.

lines when tested at 5 psig (seal system AP).

d.

A combined leakage rate of less than or equal to 10 gpm for all con-tainment isolation valves which form the boundary for the long-term sea of the feedwater lines in Table 3.6.3-1, when tested at 1.10 Pa, 52.9 p j

A combined leakage rate of less than or equal to 10 gpm for all other e.

penetrations and containment isolation valves in hydrostatically i

tested lines in Table 3.6.3-1 which penetrate the primary contain-l ment, when tested at 1.10 Pa, 52.9 psig ap.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

ACTION:

With:

The measured overall integrated primary containment leakage rate (T pe A a.

y

=nding 0.75 L, :r des +)no+ r or A

o l

b.

The measured combined leakage rate for all penetration's and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydro per Table 3.6.3-1, subject to Type B and C tests"" statically tested g r " ; 0.50 L '

I a

The measured leakage rate exceeding 46.0 scfh combined through all c.

four main steam lines, or d.

The measured combined leakage rate for all containment isolation valves l

which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 exceeding 10 gpm, or The measured combined leakage rate for all other penetrations and e.

I containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment exceeding 10 gpm, restore:

(rype. A +.M +w be.

a.

The overall integrated leakage rate (s) +^ 'r : th: :: :;x! t; 0 2 L,,

rd and

Exemption to Appendix."J" of 10 CFR 50.

HOPE CREEK 3/4 6-2 Amendment No. 32

.~

. - ~_-.... -.

CONTAXNMENT SYSTEMS I

LIMITING CONDITION FOR OPERATION (Continued) h l

ACTION (Continued) b.

The combined leakage rate for all penetrations and all valves listec in Table 3.6.3-1, except for main steam line isolation valves", valves which form the boundary for the long-term seal of the feedwater lires, a c other valves which are hydrostatically tested per Table 3.6.3-1, sucje::

l to Type 8 and C tests to A9%s s

h=a equel to 0.60 L, and a"

1

>r a

The leakage rate to less than or equal to 46.0 scfh combined througn c.

l t n u a crsg,nic all four main st.e,am lines, and l

i Wah the Po,$y d.

The combined leakage rate for all containment isolation valves wnien ':re (cntofuncob Lola the boundary for the long-term seal of the feedwater lines in Taole 3.5.3 '.

ReddOg P634rn to less than or equal to 10 gpm, and The combined leakage rate for all other penetrations and containment I

isolation valves in hydrostatically tested lines in Table 3.6.3-1

)

which penetrate the primary containment to less than or equal.to 10 gpm, prior to increasing reactor coolant system temperature above 200*F.

i i

SURVEILLANCE REQUIREMENTS.

4.6.1.2 4AThe primary containment leakage rates shall be demonstrated a+-the

/

,- g -_),

fel'cwia; test schedule sad tha!' be deter ined 4-cen# re:::: with th crit:ri:

f

2. yPd $ c'd SE::.*fied f r.^fpendin J ' 10 CF" 50 u:ing th:

thed; :nd previ;ien; c' ANS:

I. T Pc A lot S

- 1972,e, or the fo tfowang:

l Thre: Typ:

Over:!' Integr:ted Cer*:' e:nt L :k:g: " t: t:ste-sna4&

^

C tots 0nchdm) a. b; : nducted :t 'O ^ 10 centh 'nt:-

asr Ic Lks

':"" dur'n; :hutd:vr :t '1,

~

t0.1 p;ig, during : -h 10 y r : rvi : peri d.

Th: third t;;; c'

h ::t 05:!' b: conducted dur n; the :hutdee-for the 10 year ? !n:

i 4, - - m. 4.,. -

4.,.

4.m.

Cyg\\gkec(

b;n's'. - - - - v~.'--

~ "s

^. ' - - ' ' '. '. ' - -

- ' ^ ' " '

-vz

. r

- ~ - - -

~g,

~~ ~-- -~~~-- -

'er :eb::;u:nt Type 8 te:t Sha!! b^ r vf r::d 3rd appreved by the Cerrf:: fee

!? tre con:: utive Type 8 t=5t fe!' te e::t 0.75 L,,

a 1

Type ^ tett th:!' be perfereed at !ee:t every 19 centh: unt!' te centecutive Ty;c ^ teet tet 0 75 L,. et 'hich

+4== +ha =bava +^et echedul: ::y be rete d.

l c.

'h: ::: r::y Of ess5 Typ:

t::t :h:!' be v:rf:d by : Supp!:eente!

^

m_ &. 4.,. w..

1.

00

' :: th: :::ur::y ' th: t::t by v:ri'ying th:t th: di'f r:n s bete::n the tupp!- :9te! det: and the Type 8 test det 1: "!!hia-

o...e.,

" Exemption to Appendix "J" of 10 CFR 50.

EThe ix4=u per-ie f b!e test 49terv:! f:r th: ::::nd Typ: ^ t::t :" th: "ir:

l 4en y a-seruf ee peried te extended te 56 eenth. Yhte enten: fen N; free upea l

-c::p!:tien :f th: ::::nd Typ: ^ t::t :f th: f.fr:t ten year service perfed.

1 l

i HOPE CREEK 3/4 6-3 Amendment No. 43 i

1 l

l l

CONTA!NMENT SYSTEMS

)

SURVEILLANCE REQUIREMENTS (Continued) 9

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DUire; the ';U:ntity Of g:: ' nj : t ed i a tO--th ^ C o ^.tafomen t--O fi.-

b!:d '. rem the cent:1^ ent dur n; th: uppl:.::nt:! t :t t0 be j

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u. <........, u... <,.,.+u.....,....,

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7..

f.

Main. steam line isolation valves shall be leak tested at least once l

per 18 months.

l g.

Containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 shall be hydrostati-l cally tested at 1.10 P,,. 52.9 psig, at least once per 18 months.

i h.

All containment isolati:n valves in hydrostatically tested lines in Table 3.6.3-1 which pe,trate the primary containment shall be leak l

tested at least once pa-18 months.

i.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and* demonstrated OPERA 8LE per Surveillance Requirements 4.6.1.8.2.

2

r. u... r.... u.. s....a..e,... s. o, s..,.. u.. a. n......

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HOPE CREEK 3/4 6-4 Amendment No. 48 i

t

-~.-.

i CONTAINMENT SYSTEMS 3

PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE with:

Both doors closed except when the air lock is being used for normal a.

transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate :f 1::: th x er :.;l t: 0.05 L ct

^ in a ccenbace usik;h Pr;meNng n

so

,~u a

'a'

' - ' - " ~"'

conh;n,w.nt t.eakage RakTes APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

With one primary containment air lock door inoperable:

I a.

l l

1.

Maintain at least the OPERABLE air lock door closed and either l

restore the inoperable air lock door to OPERABLE status within 24 j

hot.rs or lock the OPERABLE air lock door closed.

l 2.

Operation may then continue until performance of the next required

?

overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l 4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary containment air lock inoperable, except as a result of an inoperable air, lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be i

in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l l

"See Special Test Exception 3.10.1.

1 I

)

HOPE CREEK 3/4 6-5 I

l l

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS l

4.6.1.3 Each primary containment air loc shall be demonstrated OPERABLE:

By vec6rying sul \\eakage rafe.

a.

"ith'- 72 'cu"5---fehlee'n; :: ' c' :'";, ^ ~^^+ ' hen-+h^ ' 4 r 1 ^^

4" hn4nn gegd far er v ii + 4 n 1 9 entrige, + hen s+

19se+ nnen ngr 79 hnure, hy ve 4*y 22' ' 92; r:t ler: + 5 2- ^- ^^u s' te 5 : f pe-h ^"-

4 g pg-,97

- yrget,ga

+n in n ne4 1,

te 7n g +.,g g a

+h k

ohne

+hn 7

\\

395GRT

/

b.

By conducting an overall air lock leakage test :c"

S.1 ;;i g,

t iN Ei.'.f y!ng th:t the :.

21' ci-lock le:h:g: 9:,tc!: ithin j

c in occordonce

)

udk Ae Primoy

~

cosQsme O At least once per 6 months #, and

%g ae.

g T.shs PrayoM 2.

Prior tablishing PRIMARY CONTAINMENT GRITY when maintenance en pe ap% d on t r lock that could affect 3

the airlock seali g b1 Tit

nd O@

3.

Prior to estalishi IMARY C T MENT INTEGRITY when main-tenance has n een performed on the ock that could affect the air sealing capability, a seal test e performed in li the overall air lock leakage test. The acc ce criteria and test pressure shall be as specified in 4.6...

c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.**

The prc';ici : ef !; rie: tier ' O.? :

^^t :;;12:91 e.

Ey^-^ tic" t i;;:ndi

f 10 CF" 50.

- Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the p'imary containment has been de-inerted.

HOPE CREEK 3/4 6-6 l

l

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 1

3.6.1.5 The structural integrity of the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.1.

)

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits 1

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at icast HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment shall be determined dur' g the de-fe ese" Type ^ centei-ment !eekage rete test by a "isue' inspee+ inn

""+d^"a c ' + ', e r e r ". ' e e t 7"!c 4 :pectier che!' be pe-'e-ed prie-te the Typa A

,mm.

4m_mm 3 - t., m....

.m,+

+m

,,4<,

em emm

.mm+

rs,mmm, 4.

.mmm,,sm-m m.

mthae shmmemsl An. ends +4nn 1

4.6.1.5.2 Reports Any abnormal degradation of the primary containment struc-i ture detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.9.2 within 30 days. This report shall j

include a description of the condition of the containment, the inspection pro-cedure, and the corrective actions taken.

T AJ SE.P T" in acc cPclonce, td e, hritnohf l

ce,nbinmed Leakage RakeTe.ckog Progran l

t i

HOPE C.TEEK 3/4 6-8 1

COS"*AINMEN"' SYSTEMS Op yWELL Ab"D SUPPRESSION CHAVBEF P'_"R O E SYSTEM l

LIMITING CONDITION FOR OPERATIONS 3.6.1.8 The drywell and suppression chamber purge system, including the 6 inch nitrogen supply.ine, may be in operation for up to 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months each 365 l

i l

days with the supply and exhaust isolation valves in one supply line and one l

exhaust line open for containment prepurge cleanup, inerting, deinerting, or pressure control.*

i APPLICABILI*Y:

OPERATIONAL CONDITIONS 1, 2 and 3.

1 l

ACTICNt l

i

a. With a drywell or suppression chamber purge supply and/or exhaust isolation valve and/or the nitrogen supply valve open, except as permitted above, close the valves (s) or otherwise isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1

i or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD I

SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With a drywell purge supply or exhaust isolation valve, or a suppression chamber purge supply or exhaust isclation valve or the nitrogen supply valve, with resilient material seals having a measured leakage rate l

s...ee ding t....

.. of Surveillance Requirement 4.6,1.8.2',

restore the Inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least y

)

HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the j

following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust, and nitrogen supply butterfly isolation' valves shall be verified not to have been open for more than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in the previous 365 l

days.*

4.6.1.8.2 At least once per 6 months **, but no more than once per 92 days ***,

the 26-inch drywell purge supply and exhaust isolation valves and the 24-inch suppression chamber purge supply and exhaust isolation valves and the 6-inch l

n:.trogen supply valve with resilient material seals shall be demonstrated OPERABLE by '?:rifying that th: ?:::ur:d 1::k ;: :::: i: 1:;; th;.. :.: q c.1 ts 0.C5 i, per pe etriti:n & precturi::d te ?, '".1 prigs ln accordone.e i )& de. 9thery JWitT / C*MMedx4e R&.Tesk Prs $ mas.

Valves open for pressure control are not subject to the 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per 365 l

days limit, provided the 2-inch bypass lines are being utilized.

1 Provided that the valve has not been operated since the previous test.

Applies only to a valve which has been operated since the previous test.

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MOPE CREEK 3/4 6-11 Amendment No.84 l

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ADMINISTRATIVE CONTROLS d.

Erelosive Gas Monitorino This program provides controls for potentially explosive gas -

i mixtures contained in the Main Condenser Offgas Treatment System. The program shall include the limit for hydrogen l

concentration in the Main Condenser Offgas Treatment System and l

a surveillance program to ensure the limit is maintained. This t

l limit shall be appropriate to the system's design criteria l

(i.e., whether or not the system is designed to withstand a hydrogen explosion).

l The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are t

I applicable to the Explosive. Gas Monitoring Program surveillance frequencies.

l INSERT A l

l d

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i Amendment No.91 HOPE CREEK 6-16a I

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INSERT A 6.8.4.e Primary Containment Leakage Rate Testing Program i

A program shall be established, implemented, and j

maintained to comply with the leakage rate' testing of the containment as required by 10CFR50.54(o) and 2

i 10CFR50, 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.

l The peak calculated containment internal pressure for the design basis loss of coolant accident, P.,

is 48.1 psig.

The maximum allowable primary containment leakage rate, L.,

at P.,

shall be 0.5% of primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a.

Primary containment leakage rate acceptance criterion is less than or equal to 1.0 L..

During the first unit startup following testing in accordance with this program, the leakage rate J

acceptance criteria are less than or equal to 0.6 L.

for Type B and Type C tests and less than or equal to 0.75 L. for Type A tests-i b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is less than or equal to 0.05 L. when tested at greater than or equal to P.,

i 2)

Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

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3/4.6 CONTAINw!NT SYSTEws k

BASES 3

3/4.6.1 DR! MARY CONTAINMENT 3/a 6.1 1 PRIMARY CONTAINMENT INTEGRITY 1

PRIMARY CONTAINMENT INTEGRITY ensures that the release of racio

{

rials from the containment atmosphere will be restricted to those leakage patts and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with the leakage rate limitation, will limit the site bouncary radiation doses to within the limits sf 10 CFR Part 100 during eccident concittons.

3/a.6.1.2 PRIMARY CONTAINMENT LEAKAGE e.g.,n do,,, t.oca movimm peak cenknmd z u or The limitatio on primary containment leakage rates ensure that the total containment les e volume will not exceed the value assumed in the accident analyses at the peek accident pressure of 44.1 psig, P"further lim

. As an added conserva-tism, the seasured overall integrated leakage rate is than or equal to 0.75 L,the con'ainment leakage bar t es during performance of the riodic tests to account for possible degradation of ers between leakage tests.

2smer cryp. M=an Operatinit experience with the main steam Ifne isolation valves has indicated that degradation has occasiona11).......d in the lea.

.v tness of the valves; therefore the special requirement for-tasting these valves.

a The

__..,surveillan,ce._ testing f..or m,ea.suring leaka.ge rates is consis, tent,with

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Pii'i : p? E'W5F:tiU:55:55 'idri'55Eti5'~;~5Eli:Ih; t'

2'-! 9 2't r : t ;:-i"; Ae. PMmacy conbimed Leab e kkTisb Prosmn.

usser t 9

9 r

3/4.6.1.3 PRIMARY CONTA! WENT AIR LOCKS The limitations on closure and leak rate for the primary containment air

- h mJ locks are re and the?' quired to meet the restrictions on PRIMARY CONTA!*ENT INTEGRITY n;g

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?- ' ;: :t: ':::

8-c..nk,nmed 3 '. '.. :. 'h; :;;;::t':: d : 1? r: ;:::

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':r W " et th:t W -- ry 5 t,eaage.94 kn; ;;r'::: : ? t ' -

^_t it :'- h:2 d" h ' : md W : ~ rd TQ N,ge ~ " ' " ""' "O "'O t "- -- e t i

?% Only one closed door in each air lock krequired to maintain the integrity of the containment.

3/4.6.1.4 MSIV $[ALING SYSTEM Calculated doses resulting from the maximus leakage allowance for the sain steam 11ne isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steos line system from the isolation valves up to and including the turbine condenser remains intact.

Operating experience has indicated that degradation has occasionally occurred in the leak tightness 6f the M5!V's such that the specified leakage requirements have not always been maintained continuously. The sealing systee will reduce the untreated leakage from the MSIVs when isolation of the primary system and

,y containment is required.

HOPE CREEK B 3/4 6-1 1

OS* A!!. HEN

SYSTEMS

'5ASES 3 4 6 ; 5 PPIMARY CONTAINHENT STRUCTT7AL INTEGRITY j

This limitation ensures that the structural integrity of the containment w:.1 te

,intained comparable to the original design standards for the life of

-he unit.

Structural integrity is required to ensure that the containment will withstand the maximum pressure of 48.1 patg in the event of a LOCA.

A visual inspection in cr ;'--* -

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'"*"a"

- =*=

4=

""'*4""*

h accordone.c usth h Phany Con %me6+ LeaQe Ehe am.--,...

s, 4.

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rasttT'A Teshnj PresmM ;s suOded 3 4 6 1 6 OPYWELL AND SL"dPRESSION CHASER IN*EPRAL PRESSL7E The limitations on drywell and suppression -hamber internal pressure ensure that the :entainment peak pressure of 48.1 psig does not exceed the design pressure of 62 psig during LOCA conditions or that the external pressure differential does not exceed th,e design maximum external pressure differential of 3 paid.

The limit of -0.5 to +1.5 psig for initial positive s

containment pressure will limit the total pressure to 48.1 psig which is less than the design pressure and is consistent with the safety analysis.

3/4 6.1.7 DRYWELL AVERAGE AIR TEMPERATL7E T'a limitation or d-vwell average air temperature ensures that the c:nta.nment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the safety analysis. The 135'F average temperature is conducive to normal and long term operation.

3 '4 6.1 8 URYVELL AND SUPPRESSICN CHAMBER PL9GE SYSTEM The 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months /365 days limit for the operation of the purge valves and j

the 6" nitrogen supply valve during plant Operational Conditions 1, 2 and 3 is intended to reduce the probability of a LOCA occurrence during the above operational conditions when the applicable combination of the above valves are open.

Blow-cut panels are installed in the CpCS ductwork to provide additional assurance that the FRVs will be capable of performing its safety function subsequent to a LOCA.

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l MOPE CREEK B 3/4 6-2 Amendment No. 84 g

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ML20140D220

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