ML20127D488
| ML20127D488 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/11/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127D473 | List: |
| References | |
| NUDOCS 9301150243 | |
| Download: ML20127D488 (4) | |
Text
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g NUCLEAR REGULATORY COMMISSION 5
l W ASHINGToN, D, C. 2055$
a g...H..f MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. OPR-36 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Maine Yankee Atomic Power Company (the licensee) dated October 19, 1992, 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 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 set forth in 10 CFR-Chapter I; 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 Specifica-tions as indicated in the attachment to this license amendment, and i
paragraph 2.B.6.(b) of Facility Operating License No. OPR-36 is hereby amended to read as follows:
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9301150243 930111 PDR ADOCK 05000309 2
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..7 Technical Specifications The Technical Specifications contained in Appendix A_, as revised through Amendment No.136, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate 1-3 Divis' ion of Reactor Projects - 1/II Office of-Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 11, 1993 j.
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4 n 4 ATTACHMENT TO LICENSE AMENDMENT NO.136 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 3.6-2 3.6-2 1
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B.
Whenever the reactor coolant system boron 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 above becomes inoperable, the inoperable system must be restored to I
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 I
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 tne 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.
Exceotions:
1.
One safety injection tank may be isolated for a period not to exceed one hour.
Remedial Action:
1.
If any of the component subsystems specified in C.2 above i
I becomes inoperable, 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.
)
If any of the fill header motor operated root valves become 2.
inoperable, the inoperable valves shall be restored to operable l
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 specification within four hours.
l Amendment No. M, M. E, 97,136 3.6-2
.