ML20092E870

Proposed TS 4.6.1.2.a Containment Leakage Surveillance Requirements Change to Allow Second Type a Test to Be Conducted in May 92 Cycle 11 Refueling Outage

ML20092E870
Person / Time
Site:	Millstone
Issue date:	02/07/1992
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20092E861	List: B14033, Application for Amend to License DPR-65,TS 4.6.1.2.a to Allow Second Type a Test to Be Conducted During May 1992 Outage & Add Surveillance Requirement 4.6.1.2.h Allowing Unit 2 TS Consistency W/Units 1 & 3 ML20092E870
References
NUDOCS 9202180302
Download: ML20092E870 (3)

Text

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i Docket No. 50-336 B14911 Attachment 1 Millstone Nuclear Power Station. Unit No. 2 Proposed Change to Technical Specification Containment Leakage ll b

February 1992 i

9202180302 920207 PDR ADOCK 05000336 l P PDR

e CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited tot

a. An overall integrated leakage rate of s L , 0.50 percent by weight of the containment air per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> $ at P,, 54 psig.

b. A combined leakage rate of s 0.60 L for all penetrations and valvessubjecttoTypeBandCtest!whenpressurizedtoP,.

c. A combined leakage rate of 5 0.017 L for all penetrations identifiedinTable3.6-1assecondaEycontainmentbypass leakage paths when pressurized to P3 .

APPLICABILITY: MODES 1, 2, 3 and 4. -

ACTION:

.With either (a) the measured overall integrated containment leakage rate or (b) with the measured combined leakage rate for all exceeding penetrations0.75 and L,v,alves-subject to lypes B and C tests exceeding 0.60 L , or (c) with the combined bypass leakage rate exceeding 0.017 L , restore tRe leakagerate(s)towithinthelimit(s)priortoincreasingtheReactorCoolant System temperature above 200'F.

SURVElltANCE RE0VIREMENTS 4.6.1.2 The containment leakage 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,

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40110 month intervals

• during shutdown at P 8 l (54 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.

• The test interval for conducting a Type A test shall be extended to allow the second Type A test, within the second ten-year service period, to be conducted during Cycle 11 refueling outage. This extension expires upon completion of Cycle 11 refueling outage.

L MILLSTONE - UNIT 2 3/4 6-2 Amendment No. J U 0054 l

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r 1 CONTAINMENT SYSTEMS SURVElllANCE L. J1REMENTS (Continued) 9 All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to j select an acceptable integrated leakage measurement system. j

h. The provisions of Specification 4.0.2 are not applicable. l l

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Hj(gSTONE. UNIT 2 3/4 6 4 Amendment No. ///

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