ML20151D217
| ML20151D217 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/06/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151D220 | List: |
| References | |
| NUDOCS 8804140050 | |
| Download: ML20151D217 (4) | |
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NUCLEAR REGUi 'riY COMMISSION 5
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ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. NPF-6 1.
The Nuclear Regulatory Conaission (the Comission) has found that:
A.
The application for amendment by Arkansas Pcwer and Light Company (the licensee) dated November 30, 1987 and supplemented on March 7, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment car 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 Comission's regulations and all applicable requirements have been satisfied.
8804140050 880406 DR ADOCK 050 O
~ 2.
Accordingly, the licerse is amended by changes to the Technical Specifi-cations as indicated in tne attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as followr:
(2) Technical Specifications and Environmental Protection Plan The Technical Specification contained in Appendices A and B, as revised thrcugh Amendment No. 83, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its dete of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l,,~< ' g,
l< low Jose A. Calvo, Director Project Directorate - IV Division of Reactor Pro,iects - III, IV, Y and Specic1 Projects Office of Nuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications Date of Issuance: April 6,1988 i
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ATTACHMENT TO LICENSE AMENDPENT NO. 83 FACILITY OPERATING LICENSE NO. NPF-6
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DOCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Specifications with 2
the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
REMOVE INSERT 3/4 7-1 3/4 7-1
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3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE
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SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 3.7-5.
ARLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Linear Pow::r Level-High trip setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With one reactor coolant loop and associated steam generatur in operation and with one or more riain steam line code safety valves associated with the operating steam generator inoperable, operation in MODES 1, 2 and 3 may proceed provided:
1.
That at least 2 main steam line code safety valves on the non-operating steam generator are OPERABLE, and 2.
That within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Linear Power Level-High trip setpoint is reduced per Table 3.7-2; otherwise be in at least HOT STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.7.1.1 No additicial Surveillance Requirements other than those required by Specification 4.0.5.
- Except that during hydrostatic testing in Mode 3, eight of the main steam line code safety valves may be gagged and two (one on each header) may be reset for the duration of the test to allow the required pressure for the test to be attained.
The Reactor Trip Breakers shall be open for the duration of the test.
ARKANSAS - UNIT 2 3/4 7-1 Amendment No. 83
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