ML20086H954

Amend 170 to License DPR-46,revising Surveillance Requirement 4.7.A.2.f.1 to Allow one-time Extension for Performance of Type B Local Leak Rate Testing of Drywell Head & Manport

ML20086H954
Person / Time
Site:	Cooper
Issue date:	07/11/1995
From:	Hall J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20086H958	List: ML20086H954 ML20086H976
References
NUDOCS 9507180341
Download: ML20086H954 (4)

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- UNITED STATES S

NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 2056fM201

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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License No. DPR-46 1.

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

A.

The application for amendment by Nebraska Public Power District 1

(the licensee) dated May 2, 1995, complies with the standards and requirements of the 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 the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

9507180341 950711 PDR ADOCK 05000298 P

PDR

.. 2.

Accordingly, the license is amended by changes to the Technical'Specifi-

. cations as indicated in the attachment.to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.170, are hereby incorporated _in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION hll f

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t J mes R. Hall, Senior Project Manager

'l Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 11 1995 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 170 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

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REMOVE PAGE INSERT PAGE 162 162 l

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N Lin'tITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.7.A.(Cont'd)'

4.7.A.2.e (cont'd) repeated provided locally measu' red-

-l leakage reductions,- achieved. by

'i repairs, reduce --the ' containment's overall ' measured.

leakage rate sufficiently to meet the acceptance

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-criteria.

'i f.

Imcal Imak Rate Tests 1.

With the exceptions specified below,-

loca11eak rate tests (LIAT's) shall.

be performed on the primary contain-ment. testable penetrations. and isolation valves at a. pressure of 58 psig during each reactor shutdown for refueling,' or other convenient--

i intervals, but in no case at inter-vals greater than two years *. The'l test duration of all - valves and' penetrations shall be of-sufficient length to determine repeatable results. The total acceptable leak- -

o age for.all valves and penetrations-other than the MSIV's is 0.60 La.

2.

Bolte'd double-gasketi seals shall be-i tested after each opening and during each reactor shutdown for refueling, or other convenient intervals but in ',

no casa at intervals greater than two years.

.i 3.

Tee main steam isolatiore ' valves (h1IV's). shall~ be tested at a pressure of 29 psig.

If a total leakage rate of 11.5 scf/hr for any; one MSIV is exceeded, repairs and retest shall be performed to correct the condition. This is an exemption to Appendix J of 10CFR50.

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• .The two year interval requirement-for -Penetrations DWH~ and X-4 (Drywell Head and Manport) may be i

extended until completion of.

Refueling Outage No. 16-(RE-16).

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Amendment No. 25.4':,80,S2,157,170

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