ML20207D223
| ML20207D223 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/08/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207D214 | List: |
| References | |
| NUDOCS 8808150293 | |
| Download: ML20207D223 (2) | |
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SAFETYEVALUATIONBYTHEOFFICEOFNUCLERREACTORREGULATION SUPPORTING AMENDMENT NOS. 87 AN9 60 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated July 24, 1957 Public Service Electric & Gas Company requested an amendment to Facility Operating License Nos. OPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos.1 and 2.
The proposed amendments would change the plants Technical Specifications resulting from the elimination of the coincident logic (one-out-of-four) for the reactor coolant pump breaker position reactor trip above P-8, 2.0 EVALUATION Tiie staff reviewed the design modification and the preposed changes to
'the Technical Specifications with respect to the following justification:
(1) By the elimination of a reactor trip based on one-out-of-four logic, the potential for spurious reactor trips due to single component failures is removed with an accompanying reduction in challenges to reactor protection systems.
(2) The modification results in a design for loss-of-flow protection which is similar to recent Westinghouse plants (e.g. Catawba, Beaver Valley 2. Vogtle) licensed by the staff.
(3) Although the existing reactor coolant pump breaker position reactor trip coincident logic (one-out-of-four) provides an additional measure of safety as a back-up trip for the reactor trip on low flow in a single reactor coolant loop, it has been classified as an anticipatery trip for which no credit is taken in the plants' safety analyses and it is not required to meet staff requirements.
Based upon these justifications, the staff concludes that the amendment request is acceptable.
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. In addition, typographical errors were corrected that were made in the licensee's submittal.
3.0 ENy_IRONMENTALCONSIDERATION These amendments involve 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 amendments involve 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 amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendments meet the eli categorical exclusion set forth in 10 CFR 51.22(c)gibility criteria for (9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be preparad in connection with the issuance of the amendments.
4.0 CONCLUSION
The Comission made a proposed detennination that the amendments involve no significant hazards consideration which was published in the Federal Register (52 FR 37553) on Octooer 7, 1987 and consulted with the' State of New Jersey.
No public coments were received and the State of New Jersey did not have any coments.
The staff 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, and (2) such activities will be conducted in compliance with tne Comission's regulations and the issuance of the amendments will not be inimical to the comon defense and security nor to the health and safety of the public.
Principal Contributor:
F. Burrows Dated: August 8, 1988