ML17263A978

Proposed Tech Specs to Revise TS 4.4.2.4.a,replacing Specific Leakage Testing Frequencies for Containment Isolation Valves

ML17263A978
Person / Time
Site:	Ginna
Issue date:	03/13/1995
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A976	List: ML17263A975 ML17263A977 ML17263A978
References
NUDOCS 9503160210
Download: ML17263A978 (6)

Text

ATTACHMENT B Marked Up Copy of R.E. Ginna Nuclear Power Plant Technical Specifications Included pages:

4.4-7

.9503160210 950313 PDR ADOCK 05000244 PDR

b. If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not, demonstrated within 48 hours, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion.

Ce If it is determined 'hat the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and ,.plans for corrective action developed.

4 4.2.4 Test Fre uenc ae Except as specified in b. and c. below, individual in a.~o4o.viCa penetrations and containment isolation valves shall fQ 0 A pp~CLi&

~ + be teste each reactor shutdown r

~~P~vQ g refueling, or other conv tervals, but in no

~~Ha~

ntervals greater than two years.

b. The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.

Amendment No. ZS 4.4-7

ATTACHMENT C Proposed Revised R.E. Ginna Nuclear Power Plant Technical Specifications Revise the pages as follows:

Remove Insert 4.4-7 4.4-7

b. If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not demonstrated within 48 hours, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion.

c ~ If it is determined that the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and plans for corrective action developed.

4.4.2.4 Test Fre uenc a~ Except as specified in b. and c. below, individual penetrations and containment isolation valves shall be tested in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

b. The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.

Amendment No. 4.4-7 Proposed

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