ML20214M166
| ML20214M166 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/20/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214M162 | List: |
| References | |
| TAC-60718, TAC-60719, NUDOCS 8609100562 | |
| Download: ML20214M166 (3) | |
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4 UNITED STATES 4-
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1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 53 TO NPF-10 AND AMENDMENT NO.42 TO NPF-15 SOUTHERN CALIFORNIA EDISON COMPANY, UNITS 2 & 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
Southern California Edison Company (SCE), on behalf of itself and the other licenses, San Diego Gas and Electric Company, The City of Riverside California, and The City of Anaheim, California, has submitted several applications for license amendments for San Onofre Nuclear Generating Station, Units 2 and 3.
One such request, designated Proposed Change Number (PCN) 198 is evaluated herein.
2.0 EVALUATION OF CHANGES By letter dated February 7, 1986, SCE requested that isolation valve
- 10-068 be deleted from the surveillance requirements of Technical Specification (TS)3/4.5.2,"ECCSSub-System,T greater than or equal to 350*F."
ThisTScurrentlyrequires,aMRgotherthings,that the licensee verify at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that yalve #10-068 is in a locked open position. This valve is located in a pipe (#080-6"-D-LLO) which connects the mini-flow lines of the engineered safety feature (ESF) pumps with the refueling water storage tank (see the Final Safety Analysis Report:
Figures 6.2-46,6.3-5and9.1-10). The ESF pumps are provided with a minimum flow protection to prevent damage to the pumps which could result from operating the pumps with a closed discharge. The purpose of the surveillance requirement in TS 4.5.2.a is to assure that the ESF
.t pumps have at least a minimum flow protection.
In SCE's submittal dated February 7,1986, SCE stated that the internals of valve #10-068 will be removed, and thus surveillance of the valve is no longer necessary.
By removing the internals of valve #10-068, the valve will be effectively in a locked open position.
It should.be noted that the shutdown cooling system may still be isolated from the refueling water storage tank during long-term recirculation cooling following a loss-of-coolant accident.
Isolation is provided by two valves in series in each of the mini-flow lines (i.e., valves #HV 9307, HV 9308, HV 9347, and HV 9348). Based on the above, the staff finds the removal of the valve internals to be j
acceptable, as well as the proposed TS change, l
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In summary, the staff has reviewed the proposed changes to Technical Specifications 3/4.5.2 for San Onofre Units 2 and 3.
The proposed changes would delete the isolation valve for the refueling water storage tank from a surveillance requirement. As discussed in the proceeding paragraph, the staff finds that the proposed changes meet the applicable regulatory guidance and requirements and are, therefore, acceptable.
3.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Chief of the Radiological Health Branch, State Department of Health Services, State of California, of the proposed determination of no significant hazards consideration. No comments were i
received.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in the installation or use of facility components located within the restricted area. The staff has determined that the amendments involve no significant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual or cummulative occupation radiation exposure. The Commission has previously issued proposed findings that the amendments involve no significant hazards consideration, and there has been no public comment on such findings. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR Sec. 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environ-mental assessment need to be prepared in connection with'the issuance of these amendments.
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5.0 CONCLUSION
The Staff has concluded, based on the considerations discussed above, l
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 the Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. We, therefore, conclude that the proposed changes are acceptable, and are hereby incorporated into the San Onofre 2 and 3 i
Technical Specifications.
Dated: August 20, 1986 4
i ISSUANCE OF AMENDMENT NO. 53TO FACILITY OPERATING LICENSE NPF-10 AND AMENDMENT NO. 42 TO FACILITY OPERATING LICENSE NPF-15 SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DISTRIBUTION et File 50-361/362 NRC PDR Local PDR PRC System NSIC PBD7 Reading JLee(8)
HRood OELD LHarmon EJordan -
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