ML20078Q498
| ML20078Q498 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/31/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078Q502 | List: |
| References | |
| TAC-49082, NUDOCS 8311110284 | |
| Download: ML20078Q498 (4) | |
Text
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION wasWNGTON. D. C. 20555 l
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ALABAPA POWER COWANY DOCKET NO. 50-348 JOSEPH li. FARLEY NUCLEAR PLANT, UNIT NO.1 AMENDENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-2 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power. Company (the licensee) dated June 17, 1983, supplemented,on July 8, 1983, complies with the standards and* requirements of tne Atomic Energy Act of 1954, as. amended (the Act) and the Commission's rules and regulations set, forth in 10 CFR Chapter I; 8.
The facility will operate in confonnity with the application, the provisions of the Act, and the r'JTes and regulations of the Connission;
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C.
There is reasonable assurance (1) that the activities authorized-by this amendment can be conducted without endangering the health and safety c* the public, and (ii) that such activities will be conducted in ecmpliance with the Commission's regulations; l
D.
The issuant:e of this amendment will not be inimical to the common
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defense and security or to the health and safety of the public; l
and l
E.
The issuance of this amerriment is in accordance with 10 CFR Part 51 of the Commission's regelations and all applicable requirements have been satisfied.
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8311110284 D31031 PDR ADOCK 05000348 i
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A 2.
Accordingly, the license is amended hy 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-2 is hereby amended to read as follows:
l (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised througn Amendment No. 35, are
.herehy incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as tyf the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
tev A.' ar, Chief Operating Rea rs Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 31, 1983 S
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s ATTACHENT TO LICENSE AENDENT AENDENT NO. 35 TO FACILITY OPL <ATING LICENSE NO. NPF-__2 DOCKET NO. 50-348 Revise Appendix A as follows:
Remove Page
Insert Page 3/4 7-2O 3/4 7-20
- Note: This revised page is applicable on a one-time basis only and should be removed at the end of the fifth refueling outage (about March 1984) at the latest. At that time the page removed by this amendment should be reinserted.
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4 PLANI SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERdTION
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3.7.9 All snubbers listed in* Tables 3.7-4a and.3.7-4b snail be OPERABLE.
APPLICA8ILITY: MODES 1., 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
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 /> repl' ace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluatior per Specification 4.7.9.c on the supported component or declare the supported system ir.9perab12 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 require,ments 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 i 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual,
per Inspection Period Inspection Period
- 0 18 months 1 25%
1 12 months 1 25%
2 6 months 25%**
l 3,4 124 days 25%
S,6,7 62 days t 25%
8 or more 31 days 25%
The snubbers may be categorized into two groups:
Those accessible and those inaccessible du ing reactor operation.
Each group may be inspected independently in accordance with the above schedule.
Theinspectionir$tervalshallnotbelengthenedmorethanonest'epatatime.
The provisions of Specification 4.0.2 are not applicable.
- Period is extended on a one-time basis for about three months or until the next shutdown of sufficient duration, but no later then tr.e fifth refueling outage.
Jarley - Unit 1 3/4 7-20 Amendment No. 35
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