ML20136H017
| ML20136H017 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/23/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136H014 | List: |
| References | |
| TAC-59334, NUDOCS 8601090127 | |
| Download: ML20136H017 (2) | |
Text
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UMTED STATES g
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20066
....*p SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NO. DP GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-321
1.0 INTRODUCTION
In the Spring and Fall of 1976, the Nuclear Regulatory Commission sent guidance to power plant licensees regarding the implementation of 10 CFR 50.55a(g) - Inservice Inspection requirements.
That guidance directed licensees to submit proposed Technical Specification changes to incorporate standard language referencing 50.55a(g).
In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c), Georgia Power Company (GPC) submitted a request dated August 1, 1985, to amend the Edwin I. Hatch Nuclear Plant, Unit 1, Technical Specifications (Appendix A to Facility Operating License DPR-57) to update the inservice inspection requirements pursuant to 10 CFR 50.55a(g)(4)(ii). The proposed Technical Specification changes are needed, in part, to help support completion of the first ten-year inservice inspection interval during the Hatch Unit 1 maintenance /
refueling outage scheduled to begin November 30, 1985.
2.0 EVALUATION The August 1, 1985, submittal includes a request for changes to other surveillance requirements in addition to those directed at updating the inservice inspection requirements pursuant to 10 CFR 50.55a(g)(4)(ii).
This evaluation concerns only those portions of the submittal related to the 10 CFR 50.55a(g)(4)(ii) inservice inspection update. Specifically, we have reviewed the proposed changes on pages 3.6-10 through 3.6-14 and 3.6-23 through 3.6-30 of the Technical Specifications. The other changes requested by the August 1,1985, submittal are being handled j
separately.
The proposed changes replace current requirements which do not specify the Code requirements with new requirements that specifically state that inservice inspection of ASME Code Class 1, 2 and 3 (equivalent) components and inservice testing of ASME Code Class 1, 2 and 3 (equivalent) pump and valves shall be perfonned in accordance with i
Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda.
8601090127 851223 PDR ADOCK 05000321 P
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These proposed changes ensure that inservice inspection of components and piping will be performed in accordance with periodically updated editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code. The inspection and testing programs include ASME Code Class, 1, 2 and 3 components and piping (including supports) and will provide assurance that the structural integrity of these components and piping will be maintained at an acceptable level throughout the life of the plant.
Based upon the above evaluation, we conclude that the proposed changes represent an increase in the safety of the plant and therefore are acceptable.
3.
ENVIRONMENTAL CONSIDERATION An Environmental Assessment and Finding of No Significant Impact has been issued for this amendment.
4.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: December 23, 1985 Principal Contributor:
B. Turovlin fI~
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