ML20056F049
| ML20056F049 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/19/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056F048 | List: |
| References | |
| NUDOCS 9308250476 | |
| Download: ML20056F049 (2) | |
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 3
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 114 TO FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated May 25, 1993, as supplemented by letter dated June 16, 1993, and June 30, 1993, South Carolina Electric & Gas Company (the licensee), submitted a request for a change to the Virgil C. Summer Nuclear Station, Unit No. 1 (Summer Station) Technical Specifications (TS).
The proposed change would modify TS Surveillance Requirement 4.7.1.2 to allow testing of the steam driven emergency feedwater (EFW) pump to be conducted with secondary steam supply pressure greater than 865 psig.
The current requirement is that secondary steam supply pressure be greater than 900 psig.
2.0 EVALUATION Performing Surveillance Requirement 4.7.1.2 at greater than 865 psig will adequately test the design capability of the steam driven EFW pump.
A governor valve on the inlet to the turbine that drives the pump will throttle steam pressure down to the maximum steam ring pressure of 750 psig; thus, for any steam pressure greater than 750 psig at the inlet to the governor valve, the turbine will see the same 750 psig i'nlet pressure.
Calculations show that the pressure drop in the steam supply line to the turbine at full steam flow is 112 psig.
If this pressure drop is adopted as the maximum pressure loss, then the minimum steam generator pressure at which the des gn capability of the EFW pump could be tested i
fully is 862 psig.
The reduction of full power main steam pressure below 900 psig was a foreseen result of the increased tube plugging authorized by Amendment 111.
There are no compensatory measures needed to perform the Surveillance Requirement when secondary steam pressure is greater than 865 psig; the pump will be capable of developing its full brake horsepower, its required discharge pressure (1330 psig) and its required flow (97 gpm).
The requested change is, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations the South Carolina state official was notified of the proposed issuance of the amendment.
The state official had no comments.
9308250476 930819 PDR ADOCK 03000395 p
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR
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Part 20.
The staff has determined that the amendment involves no significant i
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 amendment involves no significant hazards consideration and there has been no public i
comment on such finding (58 FR 37975). Accordingly, the amendment meets 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 i
environmental assessment need be prepared in connection with the issuance of l
the amendment.
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5.0 CONCLUSION
i The Commission 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
i Principal Contributor G. Wunder Date: August 19, 1993 1
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