ML20086H690

Proposed Tech Specs 4.6.1.2.a & 4.6.1.2.d Re Integrated Containment Leak Rate Intervals

ML20086H690
Person / Time
Site:	Hope Creek
Issue date:	11/29/1991
From:	Public Service Enterprise Group
To:
Shared Package
ML20086H689	List: ML20086H687 ML20086H690
References
NUDOCS 9112090297
Download: ML20086H690 (5)

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ATTACHMENT 2

. REQUEST : FOR LICENSE - AMENDMENT ONE-TIME EXTENSION- OF CONTAINMENT- LEAK RATE TEST INTERVAL -

FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION

-DOCKET NO. 50-354-i ..

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HOPE CREEK LCR 91-09

, NLR-N91106 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specification for ' Facility operating License No. NPF-57 are effected by this license' amendment request:

Technical Snecification Page

'4.6.1'.2.a 3/4 6-3 4.6.1.2.d 3/4 6-4 ATTACHMENT 2

CONTAINMiNT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

b. The combined leakage rate for all penetrations 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 1:nes, end other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B &nd C tests to less than or equal to 0.60 L,, and c.

The leakage rate to less than or equal to 46.0 scfh combined through all four main steam lines, and d.

The combined leakage. rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 to less than or equal to 10 gpa, and

e. The combined leakage rate for all other penetrations and containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment co less than or equal to 10 gpe, prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leau je rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the.msthods and provisions of ANSI N45.4 - 1972: u

a. Three Type A Overall Integrated Contai nt Leakage Rate tests shail be conducted at 40 + 10 month interval during shutdown at P '

a 48,1 psig, during each 10 year service period. The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection. -

b.-

If any periodic Type A test fails,to meet 0.75 L,, the test schedule for subseco nt Type A tests stall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 L,, a Type A test shall be performed at ! east every 18 months until two consecutive Ty;e A tests meet 0.75 Lg , at which time the above test schedule may be resumed.

c. The accuracy of each Type A test shall *- vceified by a supplementC test which:

1. Confirms the accuracy of the test by verifying that the. difference between the supplemental data and the Type A test data is within 0.25 L,.

2. Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

r /g 3. Requires the quantity of gas injected fato the contr.inment or

• b y bled from the containment during the supplemental test to be pg sw between 0.75 La and 1.25 La*

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

HOPE CREEK 3/4 6-3 Gaendment No. 32

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. HOPE CREEK LCR 91-09' NLR-N91156 1

-Insert A-for TS Dacro 3/4 6-3

-** The. test interval for conducting a Type A test shall be l extended to allow the second Type A test,'within the first ten year service period, to bo. conducted during the fifth refuel outage. This extension expires upon completion ~of the fifth refuel outage.

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CONTAlHMEh; SYSTEMS

, SURVE!LLANCE REQUIREMENTS (Continued)

The formula to be used is: [L, + L ,- 0.25 L,] $ Lc 1 El o * 'm

• 0.25 L,) where L, a supplement test result; L, a superimposed leakage; ind L as measured Type A leakage,

d. Type B and C tests shall be conducted with gas at P,, 4J 1 psig*,

at intervals no greater than 24 monthsh except for tests involving:

1. Air locks, a

2. Main steam line isolation valvet, I 3. Valves pressurized with fluid from a seal system,

4. All containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, and

5. Purge supply and exhaust isolation valves with resilient material seals. '

e. Air locks shall be tested and demonstrated OPERABLE per Surveil'ence Requirement 4.6.1.3.  !

f.

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

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

h. All containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment shall be leak tested at least once per'Irmonths, i.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6.1.8.2.

J. The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a. 4.6.1.2.b, 4.6.1.2.c, 4.6.1.2.d, and 4.6.1.2.e.

-. "Unless6 a hydrostatic test is required per Table 3.6.3-1. ('h Y **X type C test,Anterval pktension/to the first refTellngf outage is f /

/ permissible for primacy containment isolat' ion valves 1,fsted in Tab)e 3.6.3-1, f

v[ :7 / wil ch are 'r NoidentifiedAn Public' Service Electric & Gas' Company's Jftter to the jdC(lettd . NLR 'N87047)/ dated Apcil 3,1987, af needing aflant outage to test.

,/ not apflica' ale./For this / on'e time / te'st interval, / the requi/ements

/ of

/;- Section 4.0.2 ar,e HOPE CREEK 3/4 6-A Amendment No. 32-

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