ML20080F244
| ML20080F244 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/27/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080F247 | List: |
| References | |
| NUDOCS 8402100405 | |
| Download: ML20080F244 (4) | |
Text
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I,ostari,h'i UNITED STATES
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT C0flPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEf1 NUCLEAR GErlERATING STATION, UNIT NO. 2 Af1ENDMENT TO FACILITY OPERATING LICENSE Amendment flo. 23 License flo. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadephia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 7,1982, as supplemented September 9,1983, complies with the standards and requirements of th'e Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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: (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 tne Commission'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 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.
2.
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 Op'erating License No. DPR-75 is hereby amended to read as follows:
8402100405 840127 PDR ADOCK 05000311 P
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i 2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 23 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
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(,VL d(L O
even Varga,, Chief
. Operating Reactort Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 27, 1984 t
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_ ATTACHMENT TO LICENSE AMENDMENT fl0. 23 FACILITY OPERATING LICENSE N0. DPR-75 DOCKET N0. 50-311 Revised Appendix A as follows:
Remove Insert 3/4 7-23 3/4 7-23
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PLANT SYSTEMS
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3/4.7.9 SNUBBERS i
LIMITING CONDITION FOR'6PERATION 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-46 shall be OPERA 8LE.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snuccers located on systems required OPERABLE in those MODES).
ACTION,:
With one or more snutbers 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 snumber(s) to CPERABLE status and perform an engineering evaluation per Specification 4.7.9c on the supported component or declare tne supported system incperacle and follow appropriate ACU ON statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the folicwing augmented inservice inspection program and the requirements of Specification 4.0.5.
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a.
Visual Inspection An inservice visual inspection of all snubbers listed in Tables 3.7 da and 3.7-4b shall be performe~d in accordance with the following schedule for each separate Table.
No. Inoperable Snubbers in Subsequent inspection Period a Table per Inspection Period for each Table *#
0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days & 75%
5,6,7 62 days + 25%
8 or more 31 days + 25%
Within each Table, the snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group within a Table 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.
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3ALEM - UNIT 1 3/4 7-23 Amendment No.23 I