ML17264B097
| ML17264B097 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/10/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264B096 | List: |
| References | |
| NUDOCS 9711180221 | |
| Download: ML17264B097 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20~1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO 69 TO FACILITY OPERATING LICENSE NO DPR 18 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
- 1. 0 INTRODUCTION By letter dated August 19,
- 1997, as supplemented September 17, 1997, the Rochester Gas and Electric Corporation (the licensee) submitted a request for changes to the R.
E.
Ginna Nuclear Power Plant Improved Technical Specifications (ITSs).
The requested changes would revise the Ginna Station ITSs to correct an error in the required accumulator borated water volume specified in Surveillance Requirement (SR) 3.5. 1.2.
The September 17,
- 1997, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
- 2. 0 EVALUATION On February 13, 1996, the NRC issued Amendment No.
61 to the Ginna Technical Specifications (TSs).
This amendment replaced the existing TSs in their entirety with the ITSs.
Included within the ITS (SR 3.5. 1.2) was the addition of specified accumulator borated water volumes to match with the existing specified accumulator percent level values.
That is, the previous TSs already required an accumulator inventory based on percent values of instrumentation range.
The limits were between 50X and 82X of the instrumentation range.
The indicated level of 50X corresponded to 1108 cubic feet of water in the accumulator and the indicated level of 82X corresponded to 1134 cubic feet.
However, in SR 3.5. 1.2 the indicated level of 50X is currently shown to correspond to 1126 cubic feet and the indicated level of 82X is currently shown to correspond to 1154 cubic feet.
In arriving at these volume values, the licensee has subsequently discovered a calculation error in their determination.
The correct values, taking into account the correct wall thickness of the accumulator tank, are 1111 cubic feet for the 50X indication and 1139 cubic feet for the 82X indication.
The licensee has since re-evaluated the affected accident analyses (e.g.,
small-and large-break loss-of-coolant accidents and steam line breaks) using the correct cubic feet values with respect to the 50X and 82X levels as specified in the proposed change to-SR 3.5. 1.2 and determined a negligible change results.
The NRC staff has reviewed the licensee's request and has determined that, since the corrected accumulator water volumes result in negligible change such that all requirements with respect to the emergency core cooling system remain met, the proposed change to SR 3.5. 1.2 is acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR
'art 20 and changes surveillance requirements.
The NRC staff has 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 in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 52587).
Accordingly, the amendment meets the eligibilitycriteria 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;
- 5. 0 CONCLUSION The Commission has 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; (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
G. Vissing Date:
November 10,1997