ML20040C092
| ML20040C092 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/07/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040C089 | List: |
| References | |
| NUDOCS 8201270257 | |
| Download: ML20040C092 (5) | |
Text
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UN:T:D STATES f y s. # gf i NUCLEAR REGULATORY COMMISSION
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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION
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AMENDMENT TO FACILITY OPERATING LICENSE AmendmentNo.60 License No. OPR-36 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated December 24, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and.regula: ions of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amencment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comnission'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 apolicable requirements have been satisfied.
8201270257 820107 PDR ADOCK 05000309 P
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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 2.B(6)(b) of Facility Operating License No. OPR-36 is hereby amended to read as follows:
(b) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amencment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective on December 24, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief
's Operating Reactors Branch #3 Division of Licensing Attachments:
Changes to the Technical Specifications Date of Issuance: January 7, 1982 i
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ATTACHMErlT TO LICEt1SE AMEtlDMEtlT P10. 60 TO FACILITY OPERATItJG LICEt1SE fl0. OPR-36 DCCKET t10. 50-309 Revise Appendix A as follows:
Remove Pace Insert Pace 3.6-2 3.6-2 b
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B.
Whenever the reactor coolant system boron concentration is less than that required for hot shutdown condition, two high pressure safety injection.
pump subsystems shall be operable.
C.
The following equipment must be operable whenever the reactor is in a power operation condition.
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.
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 loops.
Exceptions:
1.
If any of the component subsystems specified 'in B and C.2 above becomes inoperable continued power operations is permitted for a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the component subsystem performing the same function in the other train are operable.
In this situation the operable sub-system and its diesel' generator shall be tested within two hours af ter discovery of the outage.
2.
If any of the fill header motor operated root valves becomes inoperable-continued power operation is permitted for a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided both of the remaining root valves are tested operable within two hours after discovery of the outage.
3.
One safety injection tank may be isolated for a period not to exceed one hour.
4.
If one of the safety injection tanks is found not to be within specifica-tiens it shall be restored to specification within four hours.
5.
Isolation of the minimum flow recirculation line for safeguards pumps is permitted for a period of not more than six hours on December 24, 1981,. o'nly, to accomplish repairs on leaking isolation valve SLA-59.
Remedial Action:
Restore required limiting condition within grace period specified or place the plant in a Hot Shutdown condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in a Cold Shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Basie:
Adequate core cooling and containment spray is provided for the entire break spectrum up to and including the design basis accider.t.
This protection covers all modes of operation from shutdown to full power.
At full power minimum required safety injection includes three (3) oper tble safety injection tanks, and'two complete ECCS trains consisting of the equip-ment specified in A.2, A.3 and A.4 above. The accident analysis considers that only 2/3 of the capacity of the operable equipment is effective for core cooling.
Amendment No. 59, 60 3.6-2 M
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