ML20151Y463
| ML20151Y463 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/29/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151Y419 | List: |
| References | |
| TAC-57309, NUDOCS 8602120710 | |
| Download: ML20151Y463 (2) | |
Text
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UNITED STATES o
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.122 TO FACILITY OPERATING LICENSE NO. DPR-57 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 1 DOCKET NO. 50-321
1.0 INTRODUCTION
By letter dated August 23, 1985, Georgia Power Company requested changes to the Technical Specifications for Hatch Nuclear Plant Unit 1 to account for planned logic modifications to the Automatic Depressurization System (ADS).
2.0 EVALUATION These modifications were made to satisfy TMI Action Plan Item II.K.3.18 which requires that the ADS operation be extended to transient events and LOCAs which do not result in steam release to the drywell, but could result in a need to depressurize the reactor coolant system to maintain adequate core cooling. To meet this requirement, the ADS logic is modified by providing bypass timers such that the high drywell pressure permissive logic is i
bypassed after sustained reactor vessel low water level (level 1). The setting of the bypass timers is described in the General Electric Company report " Bypass Timer Calculation for the ADS Modification for Hatch Units 1 i
and 2."
GPC is reconsidering installation of a manual switch to prevent automatic operation of ADS during an anticipated transient without scram j
(ATWS).
l The proposed changes to the Technical Specifications for Hatch Unit 1 are similar to those already approved for Hatch Unit 2 by Amendment No. 52 dated August 27, 1985. We find the proposed changes acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements.
We have determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase The Commission in individual or cumulative occupational radiation exposure.
has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment Accordingly, the amendment meets the eligibility on such finding.
criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
I We have concluded, based on the considerations 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 amerdment will not be inimical to the common-defense and security or to the health and safety of the public.
Principal Contributor:
C. Graves Dated: January 29, 1986 4
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