ML20063G961
| ML20063G961 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/17/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063G964 | List: |
| References | |
| NUDOCS 8209010254 | |
| Download: ML20063G961 (4) | |
Text
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h NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20$55 g
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2 ALABAMA POWER COMPANY DOCKET NO. 50-364 1
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.15 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The request for amendment by Alabama Power Company (the licensee) dated April 28, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended,
(the Act) and the Comissi' iles and regulations set forth in 10 CFR Chapter I s
B.
The facility will operate in $cnformity with the application, thes provisions of the Act, and the rules and regulations of the Commission; e
L C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complian'ce with the Commission's regulations; D.
Theissuanceofthisamendmentwillnotbeinimica$tothecommon r
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.
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2.
Accordingly, the license is amended by changes to the Technicaly,,
Specifications as indicated in the attachment to this license' amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications containe'd in Appendices A and B, as revised through Amendment No.15, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Techn.fcal Specifications.
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3.
This license amendment is effective on April 28, 1982 for one. time i only.
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F STHE NUC AR) GULATORY COMMISSION
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, Operating. Reactors a h No. 1 Division of Licensing
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Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.15 TO FACILITY OPERATING [ICENSE NO. NPF-8 j
DOCKET NO. 50-364 Revise Appendix A as follows:
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t REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVA8LE CONTROL ASSEMBLIES
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GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step counter demand position.
APPLICABILITY: MODES 1* and 2*.
ACTION.
With one or more full length rods inoperable due to being immovable I'
as a result of excessive friction or mechanical interference or a.
known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod inoperable or misaligned from the group step counter demand position by# nore than i 12 steps (indicated i
position), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With one full length rod inoperable due to causes other than addressed c.
by ACTION a, above, or misaligned from its group step counter demand height by more than 12 steps (indicated position), POWER OPERATION may continue provided that within one hour either:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod within one hour while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operatior, or 3.
The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.
^5ee Special Test Exceptions 3.10.2 and 3.10.3.
- 0ne-time only exception allowing time for being in HOT STANDBY to be extended l
from 6 to 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> for completion of surveillance testing on April 28, 1982.
FARLEY-UNIT 2 3/4 1-14 AMENDMENT N0.15 l
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