ML20044B016
| ML20044B016 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/11/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044B017 | List: |
| References | |
| NUDOCS 9007170206 | |
| Download: ML20044B016 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION j
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4 ALABAMA POWER COMPANY i
DOCKET NO. 50-364
[0SEPHM.FARLEYNUCLEARPLANT, UNIT 2
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AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 75
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License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the -
licensee), dated February 8,1990, complies with the standards and requirements of the Atomic Energy Act of 1954 asamended(the Act), and.the Comission's rules and regulations s,et 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 Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 Comission's regulations; D.
The issuance of this. license 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; andparagraph2.C.(2)ofFacilityOperatingLicenseNo.NPF-8ishereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.
75, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Clinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects. 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 11, 1990 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 75 4
FACILITY OPERATING LICENSE NO. NPF-8 DOCKET N0. 50-364 Replace the following pages of the Appendix A Technical Specifications j
with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 7-20 3/4 7-20 i
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I PLANT SYSTEMS 3/4.7.9' SNUBBERS i
LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or the failure of the system on which they are l
Installed would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES 1, 2. 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
Vith 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 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 I
The first inservice visual inspection of snubbars shall be performed after four months but within 10 months of POVER OPERATION and shall include all snubbers within the scope of Specification 3.7.9.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second i
inservice visual inspection shall be performed 12 months + 25% from the date of the first inspection.
Othervise, subsequent visual inspectin?t shall be performed in accordance with the following i
schedule: -*
No. of Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *#
0 18 months + 25%
l 1
12 months ! 25%
4 l
2 6 months ! 25%
3, 4 124 days
! 25%
5,6,7 62 days
- 25%
8 or more 31 days i25%
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be 1,
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 is a one-time Technical Specification change until startup from the seventh refueling outage.
Table 4.7-3 should be utilized during this interval to l
determine the subsequent visual inspection period.
FARLEY - UNIT 2 3/4 7-20 AMENDMENT NO. 75