ML20065G121
| ML20065G121 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/22/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065G124 | List: |
| References | |
| NUDOCS 8210040039 | |
| Download: ML20065G121 (4) | |
Text
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UNITED STATES
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- t, NUCLEAR REGULATORY COMMISSION I*
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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 17
- License No. NPF-8 1.
He Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated August 2,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regu-lations 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 (.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 witn the Comission'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 2;
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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8210040039 820922 PDR ADOCK 05000364 P
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Accordingly, the license is amended by changes to the Technical 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 Saecifications The Technical Specifications contained in Appendices A and B, as revised througn Amendment No. 17, are hereby incorporated in the license. The licensee shall 6
operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
i FpR THE NUCLEAR REGULATORY COMMISSION I
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Operating Reactors $ a
- 1 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance: Septenber 22, 1982 W
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u ATTACHMENT TO LICENSE AMEN 0 MENT AMENDMENT NO.17 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revise Appendix A as follows:
Remove Page Insert Page 3/4 7-20 3/4 7-20 1
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2.
.... x PLANT SYSTEMS 3/4.7.9 SNUBBERS j
hj LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
i ACTION:
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With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation 2
per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
Subsequent Visual No. Inoperable Snubbers Inspection Period *g per Inspection Period 0
18 months 1 25%
1 12 months 25%
2 6 months i 25%**
3,4 124 days 25%
5,6,7 62 days i 25%
8 or more 31 days 25%
The snubbers may be categorized into two groups:
Those accessible
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and those inaccessible during reactor operation.
Each group may.:be inspected independently in accordance with the above schedule.
The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
- This period is extended on a one-time basis until the first refueling outage scheduled to begin October 22, 1982, for inacces,sible snubbers.
FARLEY-UNIT 2 3/4 7-20 Amendment No.17 I
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