ML20235F730
| ML20235F730 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/23/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F676 | List: |
| References | |
| NUDOCS 8709290296 | |
| Download: ML20235F730 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMFNDMENT NO.82 TO FACILITY OPERATING LICENSE NO. DPR-70 1
PUBLIC SERVICE ELECTRIC A GAS COMPANY l
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272
1.0 INTRODUCTION
By letter dated October 3, 1986, Public Service Electric & Gas Company requested an amendment to Facility Operating License No. DPR-70 for the Salen Nuclear Generating Stetion, Unit No. 1.
The proposed amendment would replace the numerical Fxy limits in TS 4.2.2.2.e with statements referring to the Radial Peaking Factnr Limit Report in which the Fxy limits are provided as needed at the beginning of or during each operating cycle.
2.0 EVALUATION The purpose of Fxy limits in the Technical Specifications is to ensure that this initial condition assumed for the LOCA analysis is not exceeded in normal operation (including load following maneuvers) of the i
power plant. Calculation of the Fxy limits is performed by approved methods contained in WCAP-8385-P-A, " Power Distribution Control and Load Following Procedures" and WCAP.9272-P-A " Westinghouse Reload Safety Evaluation Methodology".
The Radial Peaking Factor Limit Report is the subject of a separate Technicel Specification change involving the whole of Section 6.
However, the language of the section (6.9.1.9) was reviewed for the i
present change and is acceptable. Technical Specification 6.9.1.9 and the changes to Fxy proposed for this action were previously approved for Unit 2 in Amendment 19, dated May 5, 1983.
Because the proposed change involves a quantity which is calculated by approved methods, makes the Unit 1 Specification identical to that of Unit 2, and brings it into conformance with the Westinghouse Standard Technical Specification l
(NUREG-045?, Revision 4), we find it acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The 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 thcre is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that this amendment involves no significant l
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hazards consideration and there has been no public coment on such finding. Accordingly, this amendment meets the eligibility criteria for Pursuant to 10 categorical exclusion set forth in 10 CFR 51.22(c)(9).
CFR 51.?2(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The Comission made a proposed deterninstion that the amendment involves no significant hazards consideration which was published in the Federal Register (52 FR 24558) on July 1,1987 and consulted with the State of No public coments were received and the State of New Jersey New Jersey.
did not have any coments.
The staff has concluded, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of thet:
the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security nor to the health and safety of the public.
Principal Contributor:
M. Dunenfeld Dated:
Septaber 23, 1987 l
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