ML20153F994

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Safety Evaluation Supporting Amend 153 to License DPR-57
ML20153F994
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/02/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20153F973 List:
References
TAC-66895, NUDOCS 8805110111
Download: ML20153F994 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENOMENT NO.153 TO FACILITY OPERATING LICENSE OPR-57 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITv 0F GEORGIA CITY OF DALT0th GEORGIA EDWIN 1. HATCH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-321

1.0 INTRODUCTION

By submittal dated December 21, 1987, Georgia Power Company (the licensee) proposed a change to the Technical Specifications (TS) for the Edwin I. Hatch Nuclear Plant, Unit 1, that effectively would require surveillance testing of the main steam isolation valves (MSIVs) in accordance with Section XI of the ASME Boiler and Pressure Yessel Code. Specifically, the change would alter the wording of TS 4.7.0.1 to reouire MSIV testing in accordance with TS 4.6.K.,

which requires in-service surveillance testing of ASME Code Class 1, 2 and 3 valves in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

2.0 EVALUATION Existing TS 4.7,0.1 for Unit I requires that the MSIVs be tested quarterly by the MSIVs c reducing powertotoverify (one at a time) less valve than 75% of rated closure time. The power TSand then2tripping (TS 4.0.5),

for Unit which are patterned after the Standard Technical Specifications, require testing of the MSIVs in accordance with Section XI of the ASME Code. The change reouested by the licensee would require that the Unit 1 MSIVs also be tested in accordance with Section XI of the ASME Code. By making th? change, the Unit 1 TS would be made similar to the Unit 2 TS in regard to MSly testing.

The proposed change is administrative in nature and would have no effect on MSIY operation. Surveillance requirements would be unchanged, since Section XI of the Code requires MSIV testing on a quarterly basi; as is now required by the existing TS 4.7,0.1 for Unit 1. Since the effective surveillance requirements remain unchanged, and since the proposed change would have no effect on valve operation, the NRC staff finds the proposed change acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a surveillance requirement. The staff has determined that the amendment involses no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite; and that there should be no significent increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment invovies no significant hazards consider-ation 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 nor environmental assessment need be prepared in connection with the issuance of this anendment.

4.0 CONCLUSION

The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register on March 9,1988 (53 FR 7.12 ), and consulted with the state of Georgia.

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

We have concluded, based on the consideration discussed above, 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 the issuance of the amendnent will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Lawrence P. Crocker, P0ll-3/DRP1/II Dated: May 2, 1988 l

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