ML20246F792
| ML20246F792 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/02/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246F788 | List: |
| References | |
| NUDOCS 8905150100 | |
| Download: ML20246F792 (4) | |
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[*g UNITED STATES r
NUCLEAR REGULATORY COMMISSION r.
j WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORT NG AMENDMENT HOS. 95 AND 71 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 GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET N05. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated December 20, 1988 and supplemented on March 3, 1989 (Refs.1 & 2), Public Service Electric & Gas Company requested an amendment to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Generating Station, Unit Nos. I and 2.
The proposed amendments would delete the Autoclosure Interlock (ACI) function of the Residual Heat Removal System (RHR). The staff review of this issue has focused on assuring that the changes proposed for Salem 1 and 2 meet the staff position on the removal of the autoclosure interlock as set forth in the staff's safety evaluation for Diablo Canyon (Ref. 3). The information supplied in the March 3, 1989 supplement provided clarification of the original submittal.
2.0 EVALUATION The staff )osition taken on removal ACI at Diablo Canyon consisted of f
hardware c1anges and procedural / enhancements which the staff believes will produce a net safety benefit compared to the current plant arrangement. The hardware changes consist of the addition of an alarm to each RHR suction valve. The alarm actuates if the valve is open and the pressure is greater than the open permissive setpoint and less than the RHR design pressure minus the RHR pump head pressure. The open permissive which prevents these valves from being opened must be left ir, i
l place and 7iot be disabled by the addition of the alarm and the removal of l
the ACI circuitry. The valve position indicator to the alarm must not be affected by power lockout of the valves and a method, independent of the alarm, for determining valve position should be available in the control room following power lockout of the RHR suction valves. The procedural modifications required are as follows:
8905150100 890502 PDR ADOCK 05000272 P
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The alarm response procedure used during plant startup should be modified to reflect alarm recognition responses for the added j
alarm. The procedure should be revised to direct the operator to take the necessary actions to close the open RHR suction valvels),
if they are not closed following alarm actuation.. If this is not' possible, the operator should be instructed to not pressurize further and to return to the safe shutdown mode of operation.
2.
A Surveillance procedure for the RHR suction valve alarms is added to ensure these alarms remain operable.
3.
A ' method, independent of the alarm, should be used to ensure that these valves are closed when the power to these valves is locked out.. For example, the valves could be leak-checked after power lockout.
Beside the hardware and procedural changes described above, Diablo Canyon and Salem were requested to review the sizing of the valve operators on the RHR suction valves to ensure that it would be unlikely taat these valves could be epened against full system pressure. This provides still another level of protection to ensure the integrity of the high/ low pressure system interface.
The staff has reviewed the Salem submittal (Refs.1 & 2) and has found that their proposed changes meet the hardware and procedural modifications described above which have been previously approved by the staff for Diablo Canyon and are therefore acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
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 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 1
exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public cosmient on such finding. Accordingly, the amendments meet the eligibility criteria 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 amendments.
4.0 CONCLUSION
The Consnission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (54 FR 6206) on February 8,1989 and consulted with the state of New Jersey, No public comments were received and the State of New Jersey did not have any comments.
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. 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, 4
and (2) such activities will be conducted in compliance with the Commission'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 Contributor:
G. Schwenk Dated: May 2, 1989 i
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5.0 REFERENCES
1.
Letter, Steven E. Miltenberger (Public Service Electric & Gas) to USNRC, dated December 20, 1988.
2.
Letter,StevenE.Miltenberger(PublicServiceElectric& Gas)toUSNRC, dated March 3, 1989.
3.
Letter, Harry Rood (NRC) to J. D. Shiffer (Pacific Gas & Electric), dated February 17, 1988.
4.
NUREG-1269, " Loss of Residual Heat Removal at Diablo Canyon, Unit 2."
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