ML20215G017

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SER Re Util 830202,1216,840113 & 850528 Responses to Generic Ltr 82-33 Re Conformance to Reg Guide 1.97,Rev 2,as Applied to Emergency Response Facilities.Design Acceptable.Salp Input Encl
ML20215G017
Person / Time
Site: Millstone, 05000000
Issue date: 10/29/1985
From:
NRC
To:
Shared Package
ML20213F414 List:
References
FOIA-87-213, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8706230094
Download: ML20215G017 (4)
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  • SAFETY EVALUATION REPORT MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 CONFORMANCE TO REGULATORY GUIDE 1.97 i INTRODUCTION AND

SUMMARY

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i Northeast Nuclear Energy Company (NNECO) was requested by Generic Letter 82-33  ;

to provide a report to the NRC describing how the post-accident monitoring in- )

strumentation meets the guidance of Regulatory Guide 1.97 as applied to emer-gency response facilities. The applicant responded to Section 6 of the generic letter by letter dated February 2, 1983. Additional information was provided by ]

letters dated December 16, 1983, January 13, 1984 and May 28, 1985.

i l

A detailed review and technical evaluation of the applicant's submittals was performed by EG&G Idaho, Inc., under contract to the NRC, with general super-vision by the NRC staff. This work is reported by EG&G in their Technical Evaluation Report (TER), "Conformance to Regulatory Guide 1.97, Millstone Nuclear Power Station, Unit No. 3," dated July 1985 (attached). We have re-viewed this report and concur with the conclusion that the applicant either l conforms to, or is justified in deviating from, the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable except for the contain-ment sump water temperature.

I EVALUATION CRITERIA Subsequent to the issuance of the generic letter, the NRC held regional meet-ings in February and March 1983, to answer licensee and applicant questions and concerns regarding the NRC policy on Regulatory Guide 1.97. At these meetings, it was noted that the NRC review would only address exceptions taken 8706230094 870618 PDR FOIA CONNDRB7-213 PDR

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. to Regulatory Guide 1.97. Further, where licensees or applicants explicitly state that instrument systems conform to the regulatory guide, it was noted that no further staff review would be necessary. Therefore, the review per-formed and reported by EG&G only addresses exceptions to Regulatory Guide 1.97.

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

EVALUATION We have reviewed the evaluation performed by our consultant contained in the enclosed TER and concur with its bases and findings. The applicant either conforms to, or has provided an acceptable justification for deviations from the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable except for Containment Sump Water Temperature.

Regulatory Guide 1.97 recommends that instrumentation be provided to monitor containment sump water temperature. The applicant has not provided this in-strumentation on the basis that containment sump water temperature indication is not used by the operator to take any type of corrective action, and because available net positive suction head (NPSH) was calculated using a saturated sumpmodel(seeSERSection6.2.2),therebyassuringadequateNPSHregardlessof sump temperature. While the staff agrees with the applicant that emergency operating procedures do not rely upon measured values of sump water temperature, we believe that this instrumentation should be provided to permit monitoring of i

the containment heat removal system operation and effectiveness. In this i

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regard, we find the applicant's proposed exemption to the guidelines of Regulatory Guide 1.97 to be unacceptable. ]

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CONCLUSION , j Based on'the staff's review of'the enclosed Technical Evaluation Report,-and the applicant's submittals, we find.that the Millstone Nuclear Power Station, i Unit No. 3. design is acceptable with respect to conformance to the guidelines-of Regulatory Guide 1.97, Rev. 2. .

.j It is the staff's position that NNECO shall install and have' operational Con-tainment Sump Water Temperature instrumentation at the first scheduled outage of sufficient duration, but no later than startup following the first refueling i

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