ML20133E882
| ML20133E882 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/30/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20132D191 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8508080052 | |
| Download: ML20133E882 (2) | |
Text
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SAFETY EVALUATION REPORT EDWIN I. HATCH huCLEAR PLANT, UNIT NOS. 1 & 2 DOCKET N05. 50-321/366 CONFORMANCE TO REGULATORY GUIDE 1.97 INTRODUCTION AND
SUMMARY
Georgia Power Company was requested by Generic Letter 82-33 to provide a report to the NRC describing how the post-accident monitoring instrumentation meets Regulatory Guide 1.97 as applied to emergency response facilities.
The licensee responded to the generic letter by letter dated February 21, 1984.
Additional information.was provided by letter dated April 29, 1985.
A detailed review and technical evaluation of the licensee's submittals was 4
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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, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 & 2," d'ated June 1985 (attached). We have reviewed this report and concur with the conclusion that the licensee either conforms to, or is justified in deviating from, the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable.
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 8508000052 850730 PDR ADOCK 05000321 F
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- 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 to the guidance of Regulatory Guide 1.97.
Further, where licensees or appli-cants explicitly state that instrument systems conform to the provisions of the guide, it was noted that no further staff review would be necessary. There-fore, the review performed and reported by EG&G only addresses exceptions to Regulatory Guide 1.973-This Safety Evaluation addresses the licensee's sub-mittals 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 licensee 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.
CONCLUSION j
Based on the staff's review of the enclosed Technical Evaluation Report, and the licensee's submittals, we find that the Edwin I. Hatch Nuclear Plant.
Unit Nos.1 and 2, design, lis acceptable with respect to conformance to Regulatory Guide, 1.97, Revision 2.
i Principal Reviewer:
J. Jayce
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