ML20137S063
| ML20137S063 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/06/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137S069 | List: |
| References | |
| NUDOCS 8602130567 | |
| Download: ML20137S063 (5) | |
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PHILADELPHIA ELECTRIC COMPANY DOCKET N0. 50-352 LIMERICK GENERATING STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE A,mendment ho. 1 License No. NPF-39 1.
The Nucleer Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Philadelphie Electric Company dated December 18, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Corriission; 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 license amendment will not be inimical to the comon defense and security or to the health and safety of the public;
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have.
bee'n satisfied.
i 2.
Accordinoly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this amendment and Paragraph j
2.C(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-F mental Protection Plan contained in Appendix B, as revised through l
Amendment No. 1, are hereby incorporated in the license.
PECo shall operate the facility in accordance with the Technical Specifications i
and the Environmental Protection Plan.
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This amendment is effective immediately and is to be full'y implemented within 30 days of the date of issuance.
FOR THE' NUCLEAR REGULATORY COMMISSION
. halter R. Butler, Director Project Directorate No. 4-Utvision of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: ~ FEB 0 61986 e
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ATTACHl1ENT TO LICENSE-AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-354 Replace the following pages of.the Appendix A Technical Specifications with the enclosed pages, The revised pages are identified by Amendment nutber and contain vertical lines indicating the area of change. Also to be replaced are
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the folicwing cycrieaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4'6-18 3/4-6-17
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CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMlllNG CONDlil0N 10R OPERA 110N 3.6.3 lhe primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one or more of the primary containment isolation valves shown in a.
Table 3.6.3-1 inoperable, maintain at least one isolation valve OPERA 6LC in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1.
Festore the inoperable valve (s) to OPERABLE status, or 2.
Isolate each affected penetration by use of at least one de-activated automatic valve secured in the isolated position,* or 3.
Isolate each af fected penetration by use of at least one closed manual valve or blind. flange.*
The provisions of Specification 3.0.4 are not applicable provided 4.
- t. hat within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the affected penetration is isolated in accordance with ACTION a.2. or a.3. above, and provided that the associated system, if applicable, is declared inoperable and the appropriate ACTION statements for that system are performed.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With one or more of the reactor instrumentation line excess flow che.ck valves shown in Table 3.6.3-1 inoperable, operation may continue and the provisions of Specifications 3.0.3 and 3.0.4 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1.
The inoperable valve is returned to OPERABLE status, or 2.
The instrument line is isolated and the associated instrument is declared inoperable.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative control.
LIMERICK - UNIT 1 3/4 6-17