ML20147E863

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Amend 127 to License NPF-15,deferring Implementation of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation, for 30 Subgroup Relays Until Next SONGS Unit 3 Shutdown
ML20147E863
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/17/1997
From: Fields M
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20147E867 List:
References
NUDOCS 9703190258
Download: ML20147E863 (4)


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UNITED STATES p

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j NUCLEAR REGULATORY COMMISSION 2

j WASHINGTON, D.C. enana anni j.

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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY l

THE CITY OF RIVERSIDE. CALIFORNIA j

THE CITY OF ANAHEIM. CALIFORNIA j

DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT N0. 3 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 127 License No. NPF-15 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated February 18, 1997, as supplemented by letter dated February 21, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in l.

10 CFR Chapter I; 3

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l

Comission; 3

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health a

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 amendment will not be inimical to the comon i

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 1

Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 127, are hereby incorporated in the license.

Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION fff

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Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 17, 1997 i

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ATTACHMENT TO LICENSE AMENDMENT i

l AMENDMENT NO. 127 TO FACILITY OPERATING LICENSE NO. NPF-15 l

DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.

1 REMOVE INSERT 3.3-25 3.3-25 9

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ESFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.3.5.2 Perform a CHANNEL FUNCTIONAL TEST of each 30 days on a ESFAS channel.

STAGGERED TEST BASIS SR 3.3.5.3 Perform a CHANNEL FUNCTIONAL TEST of each 120 days ESFAS channel bypass removal function.

SR 3.3.5.4 Perform a CHANNEL CALIBRATION of Function 18 months 5, Recirculation Actuation Signal, including bypass removal functions.

SR 3.3.5.5 Perform a CHANNEL CALIBRATION of each ESFAS 24 months channel, with the exception of Function 5, including bypass removal functions.

SR 3.3.5.6 Verify ESF RESPONSE TIME is within limits.*

24 months on a l

STAGGERED TEST BASIS SR 3.3.5.7 Perform a CHANNEL FUNCTIONAL TEST on each Once within 4

automatic bypass removal channel.

120 days prior to each reactor startup

  • Verification of the RESPONSE TIME of the 30 subgroup relays identified in the February 18, 1997 Edison letter is not applicable until return to Mode 4 from the Unit 3 Cycle 9 refueling outage, with the additional commitments made in the February 18, 1997 letter. The safety justification for not performing this testing is also included in the February 18, 1997 letter.

SAN ONOFRE--UNIT 3 3.3'-25 Amendment No. 115,122,127 i

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