ML17279A251

Safety Evaluation Supporting Amend 41 to License NPF-21

ML17279A251
Person / Time
Site:	Columbia
Issue date:	04/29/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML17279A249	List: ML17279A248 ML17279A250 ML17279A251
References
TAC-60740, NUDOCS 8705060128
Download: ML17279A251 (4)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVA UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 41TO FACILITY OPERATING LICENSE NO. NPF-21 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.

2 DOCKET NO. 50-397

1.0 INTRODUCTION

2.0 By letter dated January 31, 1986, the Washington Public Power Power Supply

System, the licensee for WNP-2, requested exemptions from the requirements of 10 CFR 50, Appendix J, regarding local leak rate test schedules and proposed Technical Specifications (TS) changes to reflect these exemptions.

The exemption requests concern the requirements contained in Paragraphs III.D.2(a) and III.D.3 of Appendix J.

Specifically, these paragraphs contain requirements that Type C leakage tests be performed on specified containment barriers during each reactor shutdown for refueling, but in no case shall Type B or C testing be done at intervals greater than two years.

In lieu of these requirements, the li'censee proposed to divide the components requiring Type B or C testing into two roughly equivalent groups to receive less frequent testing.

Only one of the two groups would be tested during any given refueling outage, alternating the group to be tested so that all barriers would be 'tested at least within two refueling cycles.

Additionally, the licensee requested a three-month allowance on the maximum interval between tests.

The maximum interval would thereby become 27 months, rather than the 24 months required currently.

The licensee also indicated that a program would be in place to identify barriers that leak excessively.

When so identified, these barriers would be leak tested every refueling outage until the measured "as found" leakage is restored to an acceptable value.

EVALUATION

. The safety evaluation is contained in Section III of the Exemption document which is enclosed.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change in the installation of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendment involves no significant increase in the

amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that this amendment involves no significant hazards consider ation and there has been no public comments on such finding.

87050b0128 870429 PDR ADOCK 05000397 P

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I i' Accordingly, this amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendm6At.

4.0 CONCLUSION

The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Re ister on February 26, 1987 (52 FR 5871) and consulted with the State of as ington.

No public comments were received, and the State of Washington did not have any comments.

We have concluded, based on the considerations discussed above and in the Exemption, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner and (2) such activities will be conducted in compliance with the Commission's regulations and (3) the issuance of this amendment will not be inimical to the common defense and security or to the 'health and safety of the public.

Principal Contributors:

G.

Gwo, NRR Dated.. 2 9 APR 1987

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