ML20141G630

Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing

ML20141G630
Person / Time
Site:	Maine Yankee
Issue date:	05/19/1997
From:	Milano P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141G624	List: ML20141G620 ML20141G630 ML20141G651
References
NUDOCS 9705220436
Download: ML20141G630 (5)

Text

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p  % UNITED STATES g

e j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30666 4001

%...../

MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION ,

AMENDMENT 10 FACILITY OPERATING LICENSE Amendment No. 158 License No. DPR-36

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated September 13, 1996, as supplemented by letter dated January 15, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's r?les and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:

9705220436 970519 PDR ADOCK 05000309 P PDR

.. . = - . . - - - -- ._ - . . .

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.158, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

. 3. This license amendment is effective as of its date of issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION r

d3A _

Patrick D. Milano, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of Issuance: May 19, 1997 j

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4 ATTACHMENT TO LICENSE AMENDMENT NO.158 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 ,

s Replace the following pages of the Appendix A, Technical Specifications, with

. the' attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. -

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- Remove Insert  :

. 4.4-1 4.4-1  ;

4.4-2 4.4-2  ;

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4.4 CONTAINMENT _ TESTING Anolicability: Applies to containment leakage testing.

Obiective: To' verify that containment leakage conforms to specified limits.

- Specification:

1. Tvoe A Intearated Containment Leakace Rate Tests

1. All Type A ::ontainment tests will be performed in accordance with the provisions of 10 CFR 50.54(o),10 CFR 50, Appendix J, Option B, '

as modified by approved exemptions, and Regulatory Guide 1.163,

" Performance-Based Containment Leak-Test Program," dated September 1995. .

2. Testing will be performed using the absolute method of calculating the mass of air within the containment and its rate of loss with time.

3. The following terms appearing in 10 CFR 50, Appendix J, Option B, l are applicable for this specification:

a. (psig) - the calculated peak containment internal pressure P, lated to the design basis loss-of-coolant accident, 50 psig.

re (P, will be conservatively assumed to be equal to the ,

containment design pressure (55 psig) for the purposes of l containment testing in accordance with this Technical  !

Specification.) '

b. L, (percent /24 hours) - the maximum allowable leakage rate at pressure P,, 0.10 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

II. Tvoes B and C Containment Leakaae Rate Tests

1. Type B containment leakage rate tests will be performed in 4

accordance with the provisions of 10 CFR 50.54(o), 10 CFR 50, Appendix J. Option B, as modified by approved exemptions, and Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995, i

I 4.4-1 Amendment No. 38,B3,158 1

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2. Type C containment leakage rate tests will be performed in '

accordance with the provisions of 10 CFR 50.54(o),10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

3. The Type B air lock tests will be performed in accordance with the provisions of 10 CFR 50.54(o),10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and Regulatory Guide 1.163,

" Performance-Based Containment Leak-Test Program," dated September 1995, at a test pressure of not less than 55 psig. The allowable leak rate for the air lock test is 0.05 L,.

4. Containment purge supply, exhaust and bypass valve testing requirements for on-line purging are as follows:

a. ~The containment purge supply, exhaust and bypass valves will be leak tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the termination of on-line purge, except when the valves are being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

b. The containment purge supply, exhaust and bypass valves will be  ;

leak tested at six-month intervals.

l Halli i A leakage rate value of 0.10 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will, under the most adverse design basis accident conditions, maintain public exposure well below 10 CFR 100 values in the event of the hypothetical accident.

The air lock leak test is a measure of the operability of the air lock, however, the air lock is still considered to be operable in the event of -

exceeding air lock leak test acceptance criteria as long as one hatch is determined to be properly closed and sealed in accordance with Technical Specification 3.11 and total containment leakage from all penetrations and isolation valves (including the air lock) has been evaluated to be within 0.6 L,. l The seal is determined to be operable by an appropriate pressure test.

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i 4.4-2 Amendment No. 30,72,82,91,158 i l

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