ML17278B093

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Safety Evaluation Supporting Amend 31 to License NPF-21
ML17278B093
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 11/06/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17278B091 List:
References
TAC-60050, NUDOCS 8611180192
Download: ML17278B093 (5)


Text

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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 SAFETY EVAlUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.

31 TO 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 3.0 By the letter dated October 28, 1985 the licensee requested a Technical Specification amendment to allow continued reactor operation with one of two containment isolation valves in series inoperable.

By letter dated February 24, 1986, and at. the suggestion of the staff, the licensee requested a modification to the specification wording to conform to the wording of the standard Technical Specifications.

The changes were not substantive and the amendment request was not renoticed.

EVALUATION The intent of Sections 3/4.6.3 (Primary Containment Isolation Valves) and 3/4.6.5.2 (Secondary Containment Automatic Isolation Valves) of the Tech-nical Specifications is to assure proper containment of radioactivity in the primary and secondary containments.

This assurance is obtained by requiring that all lines penetrating the containments be isolated in the event of an accident.

This change to the Technical Specifications allows continued reactor operation (i.e. allows reactor mode changes) with inoper-able automatic or manual isolation valves, provided that the inoperable valves are secured in the closed position.

Since the design function of the containments, to contain radioactivity, is maintained if inoperable isolation valves are closed, plant safety is not degraded and the changes are thus acceptable, ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation and use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that this amendment involves no significant in-crease in the amounts, and no significant change in the types, of any ef-fluents 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 consideration and there has been no public comment on such finding.

Accordingly, this amendment meets the eligibility criteria 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 amend-ment.

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4.0 CONCLUSION

The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (51 FR 1882) on January 15,

1986, and consulted with the state of Washington.

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

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

(3.) there is reasonable assurance that the health and safety o

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 regula-tions and 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 Contributor:

Frank J. Witt, NRR Dated November 6, 1986

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AMENDMENT NO. 3l TO FACILITY OPERATING LICENSE NO.

NPF<<21 WF'PSS NUCLEAR POJECT NO, 2

DISTRIBUTION:

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