ML20214J596

Amend 97 to License DPR-36,deleting Requirement for Emergency Diesel Generator Testing in Event That Any Component of One Train of ECCS Becomes Inoperable

ML20214J596
Person / Time
Site:	Maine Yankee
Issue date:	05/20/1987
From:	Nerses V Office of Nuclear Reactor Regulation
To:
Shared Package
ML20214J581	List: ML20214J577 ML20214J596 ML20214J600
References
NUDOCS 8705280120
Download: ML20214J596 (4)

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+ . ,o, UNITED STATES 8 ,. ' ,g NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LTCENSE Amendment No.97 License No. OPR-36

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

A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated October 16, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and reoulations set forth in 10 CFR Chapter I; R. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance li) that-the activities authorized C.

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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph ?.8(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:

l (bl Technical Specifications l The Technical Specifications contained in Appendix A, i as revised through Amendment No. 97 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, i

3. This license amendment is effective as of the date of its issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION

,4 4 l Victor Nerses, Acting Director Project Directorate I-3 Division of Reactor Pro.jects I-II l

Attachment:

Chances to the Technical Specifications Date of Issuance: May 20, 1987 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 97 i

FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 I .

. Revise Appendix _A as follows:

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Remove Pages insert Pages 3.6-2 3.6-2 i

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B. Whenever the reactor coolant system baron concentration is less than that required for a Hot Shutdown Condition (Condition 5), two high pressure safety injection pump subsystems shall be operable.

Remedial Action: If any of the component subsystems specified in B aoove becomes inoperable, the operable component subsystem performing the same function in the other train shall be tested within two hours and the inoperable system must be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the discovery of the nonconforming condition.

C. The following equipment must be operable whenever the reactor is in a Power Operation Condition (Condition 7):

1. Three safety injection tanks set for automatic initiation and subject to the conditions specified in A.1 above.

2. Two operable and redundant ECCS trains, each train consisting of the subsystems specified in A.2 above.

3. Station service power in accordance with Technical Specification 3.12.B.

4 The refueling water storage tank and the spray chemical addition tank filled and available in accordance with Technical Specification 3.7. -

5. The fill header motor, operated root valves to three non-isolated loops. -

Exceptions:

1. Ore safety injection tank may be isolated for a ceriod not to l exceed one hour. .

l Remedial Actions:

1. If any of the comonent subsystems specified in C.2 above becomes inoperable, the operable component subsystem performing the same function in the other train shall be tested,within l two hours and the inoperable system must be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the discovery of the nonconforming condition.

2. If any of the fill header motor operated root valves become inoperable both of the other root valves shall be tested operable within two hours and the inoperable valves snall be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the discovery of the nonconforming condition.

3. If one of the safety injection tanks is found not to be within specifications it shall be restored to specifibation within four hours.

Amendment No. 17, (1, (1, 97 3.G2