ML20080K728

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Proposed Tech Specs,Revising TS Section 3/4.6.1.2 & Bases 3/4.6.1.2 for Containment Leakage Type a Test Schedule
ML20080K728
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/21/1995
From:
NORTHEAST UTILITIES
To:
Shared Package
ML20080K724 List:
References
NUDOCS 9503010239
Download: ML20080K728 (4)


Text

-,

e g-Docket No. 50-336 B15102 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Marked-up Page February 1995 J

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9503010239 950221 PDR ADOCK 05000336 P

PDR

(April 8,19

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CONTAINMENT SYSTEMS 1

CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be lialted to:

a.

An overall integrated leakage rate of s L, 0.50 percent by weight of the containment air per 24 hourl at P,, 54 psig.

b.

A combined leakage rate of 5 0.60 L for all penetrations and valves subject to Type !! and C testl when pressurized to P,.

c.

A combined leakage rate of 5 0.017 L for all penetrations identified in Table 3.6-1 as secondafy containment bypass leakage paths when pressurized to P,.

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 0.75 L,v,alves subject to Types B and C tests exceeding 0.60 L, or penetrations and (c) with the combined bypass leakage rate exceeding 0.017 L, restore t$e leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEltlANCE REOUIREMENTS 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.

7.g d ly c Three Type A tests (Oy ra 1 Int _egrated Containment Leakage Rate) a.

e shall be conducted at

_ F-monE)intervaltJ* during shutdown at P l

8 (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.

[

khe 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 Il refueling outage. This exbnsion expires upon completion of Cycle Il refueling outage.

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]LjsTONE-UNIT 2 3/4 6-2 AmendmentNo.JJ/h o %2.

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i Docket No. 50-336 l

B15102 i

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Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications containment Leakage Type A Test Schedule Retyped Page l

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February 1995 1

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C0KMIMENT SYSTEMS CONTAIMENT LEAKAGE LIMITING COMITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of s L, 0.50 percent by weight of the containment air per 24 hours2.777778e-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 valves subject to Type B and C tests when pressurtzed to P..

c.

A combined leakage rate of 10.017 L, for all penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L., or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, or (c) with the combined bypass leakage rate exceeding 0.017 L., restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 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 approximately equal intervals during shutdown at P.

(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.

MILLSTONE - UNIT 2 3/4 6-2 Amendment No. J77 J)J, om