ML20004B575
| ML20004B575 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/20/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004B572 | List: |
| References | |
| NUDOCS 8105290054 | |
| Download: ML20004B575 (4) | |
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NUCLEAR REGULATORY COMMISSION
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- - MAINE YANKEE ATOMIC POWER COMPANY E DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-36 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Maine Yankee Atomic Power Compariy (the licensee) dated May 5, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon-l defense and security or to the health and safety of the public; and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements l
have been satisfied.
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2 I Adcordingly, the license it. amended by changesito the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.B(6)(b)ofFacilityOperatingLicense No. OPR-36 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment was effective on May 5, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION ha.
i RobertA.klark, Chief Operating Reactors Branch #3 Division of Licensing Attachmente:
Changes to the Technical Specifications L
-m Date of Issuance: May20,198i
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A TACHMENT TO LICENSE AMENDMENT NO. 59
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,c-e' TO FACILITY OPERATING LICENSE NO. OPR-36
- - DOCKET NO. 50-309 Revise Appendix A as follows:
Remove Page Insert Page 3.19-1 3.19-1 e
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a 3.19 SAFETY INJECTION SYSTEM Applicability:
Applies to the condition of safety injection system.
Obiective:
To define the condition of the safety injection system 7,,
required during reactor, operation ;,
l a). None of the following valves may be closed unless ther.
Specification:
l reactor is suberitical:
1.
Any safety injection tank isolation valve I
(SIA-M-11, 21, 31) -
2.
Any safety injection header isolation valve (HSI-16, 26, 36) 3.
Any loop isolation valve (RC-M-11, 12, 21, 22, l
31, 32)
. b), The reactor shall not be critical unless th_e following conditions are met:
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- l.. The breakers shall be racked out and tagged open
- ch for the safety injection tank isolation valves, the power leads shall be removed from the breakers, i
l the bare metal terminal ends taped, and the breakers locked out.
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The breakers for the loop isolation valves:
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a) Shall be opened, and padlocked in the open 2.
...c Position.
b) The breaker thermal overload links shall be physically removed from the breakers.
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- 1 Excep' tion
- . Breakers for loop isolation valves
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. ;. RC-M-21 and RC-M-22 need not be opened and pad-locked and the thermal overload links for these valves need not be physically removed during the
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period between May 5, 1981 and May 9, 1981.
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j Basis:
The position restrictions on the loop isolation valves, safety injection header isolation valves, and the safety injection tank isolation valves are necessary to assure that plant operation is restricted to conditions considered in the loss-of-coolant accident analysis.
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The exception with respect to valves RC-M-21 and RC-M-22 ensures that loop two can be isolated rapidly following a postulated plant shutdown necessitated by degradation at the loop two reactor coolant pump seals.
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l Amendment No. 19, 29, 59 3.19-1 y-c
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