ML20077A621

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Proposed TS 3/4.6.1.2,adopting Wording for Primary Containment Integrated Leak Rate Testing Consistent W/ Requirements of BWR-4 Improved STS (NUREG-1433)
ML20077A621
Person / Time
Site: Brunswick  
Issue date: 11/16/1994
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20077A614 List:
References
RTR-NUREG-1433 NUDOCS 9411250087
Download: ML20077A621 (11)
v • d • e


Text

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ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS CONTAINMENT INTEGRATED LEAKAGE RATE TESTING MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 9411250087 941116 POR ADOCK 05000324 P.

PDR

C0tRAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) c.

The leakage rate to less than or equal to 11.S scf per hour for any one main steam line isolation valve.

l prior to increasing reactor coolant system temperature above 212 F.

SURVEILLANCE REQUIREMEfRS in accordance ut h the 4.6.1.2 The primary containment leakage rates shall be demonstrated 1et the fcilowing schedule and chall be determined -in confer +ance-with-the criteria specified in ?^^cndix J cf 10CFR50fMppendi=J,os mod @ed by ceprend exemp&ns.

The provisicos of Yechnice SpeciRea&m 4.o.1 are not yk'ecue tu the lese interals specMed in

-Threc Type A OvcFa14 Integrated.cntair, ment Leakage Rate test + ' AC'8 %

a.

10 month intervals during shutdem et ffendN J-

< hall be conducted at 40 P

49 psig, or P 25-ps4Mur4ng-each-10 -year-ser" ice period.

Th,ethirdtestc/,eachsetshall ha conducted durinn +ha c h"+ d~n

-for the 10 year plant inservice inspeet4en- (Deleted.)

b.

4f any periodic Type A test f 41s-tc meet either 0.75 L, cr-0.75 L. the test schedule for subsequent T c A tests shall bc

-rev4ewed and appr4ved by the Cc-ission.

IYtwo consceutive T3pe-t i

e test fai' to meet 0.75 L cr 0.75 L a Typa A test shall bc t

-per-for+ed at cash-plant-shuldown-for refueling cr cycry 10 montha-

-whichever--occurs f4rst until two consecut4ve Type A tect: mcct-0.75 L cr 0.75 '

at-which-t4me the abeve-test schedule may bc

-resucc6*- (Delei'e,d.)

l c.

The accuracy of each Type A test eb=H be verified by :

-supplemental test which+- (Deleted) 1.

Conf 4rms-the-accuracy of the test by ver4fying that the

--4ata-ts-within-MS-L,- or E.lemental data and the T;pe ^ tsst-

-dtf4erence-between -the sepa 254r-2.

Mes duration sufficient to-establich seeuPately-the-ehange-l

-a leakage rate hetween-the Type A test-and the suppicmcatet

-testy 3.

Require: the quantity-of gas injected into the conta4nment-

-or-bled-foc the containment-dur4ng-the supplemental test to-

-be-equivalent-te-at-least-25-percent-of-the-total mescured

-leakage at P,. 49 psig er D,. 25 psig.

)

[ Pays 3/4 G._3A ord 3/4 G,-33 hcwe hen cleigg;,c[,)

r A one tinEexempt from the accelerated testing recultenentror-Specification 4.6.1.2.

ranted m

nit 1 Type A test will be performed durin a after which two consecutive Ty>e A test i.lu re required to resume t n ee - ated test so w M.

BRUNSWICK - UNIT 1 3/4 6 3 Amendment No. 167

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t CONTAIhMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

[d.

Type B and C tests shall be conducted with gas at P,,

49 psig at intervals no greater than 24 monthsfexcept for tests involving:

l-

\\

Move To 1.

Air locks, PAGE

'1 2.

Main steam line isolation valves, 3/4 fo-3 Air locks shall be tested and demonstrated OPERABLE per Surveillance e.

l Paquirement 4.6.1.3.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months. W l

g.

All test leakage rates shall be calculated using observed data a converted to absolute values. Error analyses shall be performe'd to select a balanced integrated leakage measurement system.

h.

The provisions of Specification 4.0.2 are not applicable to 24 month

> An t in - rh surveillance intervals.

1

~ - - -.

  • i end of the current surveillance narind for the surveillance req c1Ements spect below may be extended beyond the ti.:.. limit specified echnical Specificat 4.0.2.

Af ter April 1,1985, the plant shall n e operated k

in Operational dicions 1, 2, or 3 until the surveilla requirements listed below have completed.

Upon accomplishme f the surveillances,

/

the provisions of Techn-Specification 4.0.2 s 1 apply.

Technical Specification 4.6.1.2.

as app able to the penetrations and f

valves which correspond to the Test t listed in Table 4.6.1.2-1.

i

    • The end of the current surve11 ce period for e surveillance requirements j specified below may be exte ed beyond the time lim specified by Technical j

Specification 4.0.2a.

- ter April 1, 1985, the plant s 1 not be operated in Operational Con ons 1, 2, or 3 until the surveillance uirements listed below h been completed. Upon accomplishment o f the su illances,'

I the provisi of Technical Specification 4.0.2a shall apply.

Tec cal Specification 4.6.l.2.f; as applicable to main steam iso'.ation ves B21-F022A, B21-F022B, B21-F022C, B21-F022D, B21-F028A, B21-F028B, B21-F0 28C, and B21-F028D.

BRUNSWICK - UNIT 1 3/4 6-3A Amendment No. 80

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1 ll CONTAINMENT SYSTEMS SUPNEILLANCE REQUIREMENTS (Continued)

TABLE 4.6.1.2-1 The ollowing Test Numbers correspond to those listed in Attachment of Caro na Power & Light Company's letter Serial: NLS-84-371 dated.ptember 4, I

I 1984.

1 CAC-1 E11-31 f

CAC-2 E11-32 j

CAC-9 E21-1 CAC-10 E21-2 i

CAC-11 E21-3 CAC-12 E21-4 CAC-14 E21-5 i

CAC-15 21-7 CAC-16 l-8 CAC-17 E4 2 CAC-18 E41 CAC

'.9 E41-6 CAC-10 E41-8 CAC-21 E51-2 CAC-22 E51-3 l

CAC-23 E51-4 CAC-24 SA-1 CAC-25 TIP-1 CAC-26 TIP-2 DEQTED CAC-39 IIP-3 i

I CAC-40 TIP-4 CAC-41 TIP-5 CAC-42 E11-1 Ell-2 l

E11-4 l

E11-6

]

Eil-11 l

Ell-12 I

Ell-15 Ell-16 E11-17 l

Ell-19 l

E11-20

)

E11-22 l

Ell-24

)

1 Ell-2 Ell- -

CA 43

)

E l-28 j

j Il-29 I

E11-30 4

i

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3/4 6-3B Amendment No. 80 l

BRUNSWICK - UNIT L 1

1 j

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ENCf.OSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS, DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS CONTAINMENT INTEGRATED LEAKAGE RATE TESTING MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

The leakage rate to less than or equal to 11.5 scf per hour for c.

any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212 F.

SURVEILLANCE REQUIREMENTS in accordance Wh the -

.m_

4.6.1.2 The primary containment leakage rates shall be demonstrated et the

-felleving schedule and shal rmined in confermance "ith t"0 criteria specified in Appendix J cf-10CFR5 Appendh J Hons The provisions of Technical SpecEceklon 4.,0.2.are nd @as rnoMied cable e f.est trAerw dm

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-shall be conducted at 40 i 10 month intervah during shutdown at' Aff'nd",

49 ps49, or "

Tb,e third test c/,each set shall25 psig.- during cach 10 year service period.

be conducted dur4ng the shutdown-

-for-the 10-year plant intervice inspection. (peteted )

b.

.T f..s..n.,s i y..r i. n A. 4.,, T. g r..A. + n,.e +. #..s 41..c., + n. m~a n. +. n 4. +..h. a.n na smn

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-reviewed and approved--by the Commiccion.

I, two con:ccetive Typc-A + n..e. +. e. f..a i. l + n. m.. ~a n + n.

7. C. f

.an n,,. 7, C

.s T. i,ma

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+ne+

e,,k s i, l, be-3, performed at each plant shu,down for refueling or every 18 months, r

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t

_'wh,ichever occurs first, until two consecutive Type A tests meet

n.., c., ' ^ r ^. ', c ' t. aMhP,..b., +. 4. =.~^ + h~^ ~ be.'^ +.~^.e +

.e, h a d ' ' '. ^

'a~',' ' ha-

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- re ume..- (Deteted.)

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-The-aeeeeeey-of each Type ^. test chel' be verified by a c.

-supplemental test which: (Delete).)

e n, < 4,,n,m - +un n,

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.x,,.,n.n 4. <,,,,4,,n, n+a,+

+wn m.,n _,.

m.

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3., ~... ~

-difference between-the cupplemental data and the Type ^ test

a.,2. +. =. 4. e wi. t.h. i..n n.. og i., nr n_. 9 4 i,.

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"at duration sufficient te establish accurately the change an l o w.. 2. nn, r.o..m. sa..m.. m a,, n4. s.m.T. g,r -

snn a

+ne+

enA

+w,,-,,,,,,,,,,,,~,+s, 4

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  • ' w' F r ' w " ~ ' ' v w '

-test--

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o m m.,4..e m e + h. n.

n,, 2. n. u.. s.,, n f. n,2e 4. n. a e rt ori in+n +hn ennb_ inmant.

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h i _n A #,,n a.m.. &bn

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&,,L a e.. m ni. n.m,~a,n,+ si,

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- bc equivalent to at least 25 percent of the tota' mcace ed i n.s b. ~e n n.s+....

r-a --

L'

-- nein D

A. O. nein n e' D 9R 3

r-J'

.r (Po.qe. 3/%.3A has been deleted.)

A one tio on from the accelerated testing recujr.ementrcT Specification 4.6...

en granted nit 2 Type A test i

i will be performed during the a e after which two consecutive T e ures are require e the accelerated tes BRUNSWICK UNIT 2 3/4 6 3 Amendment No. 198

CONTAINKENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) r d.

Type B and C tests shall be conducted with gas at P,, 49 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

pg 4

Main steam Line isolation valves.

3/4 4 3 Air locks shall be tested and demonstrated OPEFABLE per Surveillance e.

Requirement 4. 6.1. 3.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

g.

All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement

system, h.

The provisions of Specification 4.0.2 are not

.d ';01 'O wuch-surveillance intervals.

applicable to 24 month u

T E.LETE PAGE 3/4 6-3 BRUNSWICK - UNIT 2 3/4 6-3A Ame ndmen t No. 91

ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS CONTAINMENT INTEGRATED LEAKAGE RATE TESTING TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1

, CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) c.

The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212 F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated in accordance with the schedule and criteria specified in 10 CFR 50. Appendix J, as modified by approved exemptions. The provisions of Technical Specification 4.0.2 are not applicable to the test intervals specified in 10 CFR 50, Appendix J.

a.

Deleted.

b.

Deleted.

c.

Deleted.

d.

Type B and C tests shall be conducted with gas at P., 49 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks.

2.

Main steam line isolation valves, e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

I g.

All test leakage rates shall be calculated using observed data converted to absolute values.

Error analyses shall be performed to select a balanced integrated leakage measurement system, h.

The provisions of Specification 4.0,2 are not applicable to 24 month surveillance intervals.

I (Pages 3/4 6-3A and 3/4 6-3B have been deleted.)

BRUNSWICK - UNIT 1 3/4 6 Amendment No.

4 ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS CONTAINMENT INTEGRATED LEAKAGE RATE TESTING TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2 I

i CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

~

ACTION (Continued) c.

The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212 F.

SURVEILLANCE REQUIREMENTS 4 6.1.2 The primary containment leakage rates shall be demonstrated in accordance with the schedule and criteria specified in 10 CFR 50, Appendix J, as modified by approved exemptions. The provisions of Technical Specification 4.0.2 are not applicable to the test intervals specified in 10 CFR 50.

Appendix J.

a.

Deleted.

b.

Deleted.

c.

Deleted.

d.

Type B and C tests shall be conducted with gas at P, 49 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

Main steam line isolation valves, e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

g.

All test leakage rates shall be calculated using observed data converted to absolute values.

Error analyses shall be performed i

to select a balanced integrated leakage measurement system.

h.

The provisions of Specification 4.0.2 are not applicable to 24 month surveillance intervals.

l l

(Page 3/4 6-3A has been deleted.)

j BRUNSWICK - UNIT 2 3/4 6-3 Amendment No.

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