ML20084C975

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Amend 34 to License DPR-77,changing Tech Specs to Modify Surveillance Requirements for Testing Containment Penetration Protective Fuses
ML20084C975
Person / Time
Site: Sequoyah 
Issue date: 04/12/1984
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20084C978 List:
References
NUDOCS 8405010108
Download: ML20084C975 (4)


Text

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-77 1.

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

A.

The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated December 29, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 hereby amended by page changes tn the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, are hereby_ incorporated into the license.

8405010108 840412 DR ADOCK 05000327 p

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. 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 COMISSION wm Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Change Date of Issuance: April 12, 1984

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ATTACHMENT TO LICENSE AMENOMENT NO. 34 i

i FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and 4

contains vertical lines indicating the areas of change.

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Amended Page 3/4 8-16 i

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representalve sample of at least 1 of the curcuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for functional testing shall be selected on a rotating basis. The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

3.

By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.

Each representative sample of fuses shall include at least 10% of all fuses of that type.

The functional test shall consist of a non-destructive resistance measure-ment test which demonstrates that the fuse meets its manufacturer's design criteria.

Fuses found inoperable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.

For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.*

b.

At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

" Surveillance requirement 4.8.3.1.a.3 may be suspended until the completion of the NRC generic study, provided the following surveillance requirement is implemented:

A fuse inspection and maintenance program will be maintained to ensure that:

1.

The proper size and type of fuse is installed, 2.

The fuse shows no sign of deterioration, and 3.

The fuse connections are tight and clean.

i SEQUOYAH - UNIT 1 3/4 8-16 Amendment No. 34

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