ML17279A925

SER Accepting Util Submittals on Plant post-accident Monitoring Instrumentation,Per Generic Ltr 82-33. Instrumentation Meets Guidelines of Reg Guide 1.97

ML17279A925
Person / Time
Site:	Columbia
Issue date:	03/23/1988
From:	NRC
To:
Shared Package
ML17279A924	List: ML17279A923 ML17279A925
References
RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, TAC-59516, NUDOCS 8803310189
Download: ML17279A925 (4)

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i UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT WASHINGTON PUBLIC POMER SUPPLY SYSTEM NUCLEAR PROJECT N0.2 DOCKET NO. 50-397 CONFORMANCE TO REGULATORY GUIDE 1.97

1. 0 INTRODUCTION The Washington Public Power Supply System was requested by Generic Letter 82-33 to provide a report to the NRC describing how the post-accident monitoring instrumentation meets the guidelines of Regulatory Guide 1.97 as applied to emergency response facilities.

The licensee's response to Regulatory Guide (R.G.) 1.97 was provided in the FSAR and by letters dated April 15, 1983, October 8, 1985, and January 23, 1986.

A detailed review and technical evaluation of the licensee's submittals was performed by EG8IG Idaho, Inc., under contract to the NRC, with general supervision by the NRC staff.

This work was reported by the EGSG in the Technical Evaluation Report (TER), "Conformance to Regulatory Guide 1.97, Washington Public Power Supply System, Nuclear Project No. 2," dated February 1986 (copy attached).

2. 0 EVALUATION CRITERIA Subsequent to the issuance of the generic letter, the NRC held regional meetings in February and March 1983 to answer licensee and applicant questions and concerns regarding the NRC policy on R.G. 1.97.

At these meetings, it was established that the NRC review would only address exceptiqns taken to the guidance of R.G. 1.97.

Further, where licensees or applicants explicitly state that instrument systems conform to the provisions of the regulatory guide, no staff review would be necessary for those items.

Therefore, the review performed and reported by EGLG only addresses exceptions to the guidance of R.G. 1.97.

This Safety Evaluation addresses the licensee's submittals based on the review policy described in the NRC regional meetings and the conclusions of the review as reported by EG8G.

3. 0 EVALUATION Me have reviewed the evaluation performed by EGKG TER and concur with its bases and findings.

The licensee either conforms to, or has acceptably justified deviations from the guidance of R.G. 1.97 for each post-accident monitoring variable except for the variable neutron flux.

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4.0 CONCLUSION

Based on the staff's review of the licensee's submittals and of the EG8G

report, we find that the llashington Public Power Supply System, Nuclear Project No. 2, design is acceptable with respect to conformance to R.G. 1.97, Revision 2 except for neutron flux instrumentation.

It is the staff's position that the licensee install and have operational monitoring instrumentation for the neutron flux variable which fully conforms to the recommendations of R.G, 1.97, Revision 2.

This requirement is included in the WNP-2 operating license as License Condition 16, Attachment 2, Item 3b.

Since this issue is being handled separately, our review of conformance to R,G.1.97 can be considered closed.

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