ML20006A139
| ML20006A139 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/17/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006A138 | List: |
| References | |
| NUDOCS 9001250274 | |
| Download: ML20006A139 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS.107 AND P4 TO FACILITY OPERATING LICENSE tms. OPR-70 AND DPR 75 PUBLIC SERVICE ELFCTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DElt1ARVA POWEP AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM GENERAT!NG, STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-?72 AND 50-311
1.0 INTRODUCTION
Ey letter dated September 28, 1989, Public Service Electric & Gas Company requested an amendment to facility Operating License Nos. OPR-70 and DPR 75 for the Salem Generating Station, Unit Nos. I and 2.
The proposed amendrents would change Surveillance Pequirement 4,5.2.1 for Salem 1 and 2 to require testing the Residual Heat Removal (RHR) system open permisthe interlock at a pressure of 375 psig or greater. The current requirement is to test the open permissive interlock at 580 psig or greater.
2.0 EVALUATION Current Technical Specifications (TS) require the RHP interlocks to be tested, within 7 days of use, by simulating a reactor coolant system (RCS) pressure of 580 psig or greater and verifying that RHR isolation valves, PHR1 and RiiR2, cannot be opened. The 580 psig was based on the setpoint of the automatic closure-interlock (ACl) which has been removed from Salem Unit I and will be removed from Salem Unit 2 during the upcoming refueling outage.
The open permissive interlock (OPI) prevents npening valves RHR1 and RHR2 until the RCS pressure is reduced below the RHR system design pressure (600 psig). The OPl setpoint is 375 psig. This change will allow testing of the OPl at a pressure that corresponds more closely to the setpoint.
The staff concludes that the proposed change is acceptable.
Also, the staff, with the knowledge and concurrence of the licensee, made 4
some administrative changes (i.e. page number and editorial) to the revised technical specification pages.
9001250274 900117 PDR ADOCK 05000272 1
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3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change to a requirement with respect to the installation or use of a facility camponent located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements.
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 The Commission has previously issued a proposed finding that exposure.
the amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendments meet the elicibility criteria for categorical exclusion set forth in 10 CFR51.22(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 amendments.
4.0 CONCLUSION
The Comission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Recister (54 FR 51262) on December 13, 1989 and consulted with the State of New Jersey.
No public comments were received and the State of New Jersey did not have any comments.
The staff has concluded, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of that:
the public will tot 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 the amendments will not be inimical to the common defense and security nor to the health and safety of the public, principal Contributcc: Jim Stone Dated:
January 17, 1990 w