ML20134P287
| ML20134P287 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/27/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134P270 | List: |
| References | |
| TAC-56983, TAC-56984, NUDOCS 8509060229 | |
| Download: ML20134P287 (2) | |
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NUCLEAR REGULATORY COMMISSION i3 t -
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WASHINGTON. D. C. 20555 Id
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'd SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION y
' ' ~i SUPPORTING AMENDMENTS NOS.113 AND 53 TO e :.
j FACILITY OPERATING LICENSES NOS. OPR-57 AND NPF-5 is GEORGIA POWER COMPANY a
,1 OGLETHORPE POWER CORPORATION 4
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA l
EDWIN I. HATCH NUCLEAR PLANT, URITS NOS. 1 AND 2 DOCKETS NOS. 50-321 AND 50-366
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1.0 INTRODUCTION AND BACKGROUND
4 By letter dated February 15, 1985, Georgia Power Company (licensee) proposed change to the Technical Specifications for the Edwin I. Hatch Nuclear Power Plant, Units Nos.1&2. The affected Sections of the Technical Specifications are Table 3.1-1 Item 5 for Unit 1 and Table j.
3.3.1-1, Note G for Unit 2.
Originally, these provisions of the Technical Specifications allowed the operators to bypass the high drywell (pressure) scram signal for the purpose of rapid inerting. This would be accomplished by allowing cycles of drywell pressurization with nitrogen followed by purging, until oxygen levels were reduced to within Technical Specification limits.
Subsequently, a torus shell structural analysis was perforined as part of the Mark I containment long-term program. As a result of this analysis, g
it was determined that potentially high torus stress levels may result
-l from a postulated small line break occurring with drywell pressure at or if slightly above the 2 psig setpoint. Consequently, the licensee has M
proposed a change to the Technical Specifications which would delete the i
provision, originally in effect, which allowed the "high drywell pressure"
'l scram signal to be bypassed when the inert /deinert process took place.
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2.0 EVALUATION The staff has evaluated this proposed Technical Specification change. We u
find the proposed change results in a more restrictive and consequently more conservative Technical Specification than that currently in effect.
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Therefore, the margin of safety will increase by this proposed change.
!N In light of these considerations, we find the proposed changes to Tables L:
3.1-1 Item 5 and 3.3.1-1 Note G, of Hatch, Unit 182, respectively, y
acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
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The amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part
- 20. We have determined that the amendments involve no significant 8
increase in the amounts, and no significant change in the types, of any
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effluents that may be released offsite, and that there is no significant 4
increase in individual or cumulative occupational radiation exposure.
i The Commission has previously issued a proposed finding that the amendments involve no significant hazards _ consideration and there has i
been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 1
CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environment impact
.i statement or environmental assessment need be prepared in connection
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with the issuance of the amendments.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the healtt. 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 s
Commission's regulations, and the issuance of the amenaments will not be inimical to the common defense and security or to the health and safety of the public.
I Dated:
August 27, 1985 Principal Contributorr J. Lane O
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