ML20028D445
| ML20028D445 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/12/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028D443 | List: |
| References | |
| NUDOCS 8301190130 | |
| Download: ML20028D445 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATI0ff L
RELATED TO AMEN 0 MENT N0. 8 TO FACILITY OPERATING LICENSE NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY
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, INTRODUCTION By telecopied letter dated December 28, 1982, the South Carolina Electric & Gas Company (SCEf.6) requested a change to th.e Technical Specifications.
The change would add a footnote (3) to Table 3.6-1 for valves 9398A-SS, 93988-SS, and 9398C-SS to read:
The provisions of Specification 3.0.4 are not applicable from December 28, 1982, until July 1,1983.
HACKGROUND l
Containment isolation valves 9398A-SS and 93988-SS, sampling line from steam gener-ator A and B respectively, were recently declared inoperable because they were not able to close within the 40 seconds allowed by Technical Specification Table 3.6-1.
Action statement 3.6.4.c states that plant operation may continue with one or more containment isolation valves inoperable provided that each affected penetration is isolated by at least one manual closed valve.
The licensee complied with the action statement and continued plant operation.
On Dece.nber 28, 1982, the Summer plant tripped due to a personnel error.
According to Specification 3.0.4, plant startup may not take place because the plant is rely-ing on provisions contained in the action statement.
Repair of the isolation valve was the critical path for plant startup. Only one of the two rep 1;cemeat valves was onsite.
This condition posed an economic concern for SCE&G and the South Carolina Public Service Authority (SCPSA).
Because SCE8G's gen-erating configuration allowed several fossil units to be shut down, the licensee was required to purchase 300 M'le from neighboring utilities and operate a pumped storage facility to replace the Virgil C. Survner Nuclear Station's output.
Those sources of energy were limited.
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On Occenber 28, 1982, the licensee requested a Technical Specification change to allow plant startup with these two containment isolation valves inoperable.
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. l EVAUIATION The licensce's proposed basis for requesting an exemption to Specification 3.0.4 is as follo.es:
1.
the sample lines involved are small (3/8") high pressure secondary system lines that are exempt from 10 CFR 50 Appendix J. Type C testing requirements.
2.
these valves are currently in their containment isolation position (closed).
3.
these lines are equipped with manual isolation valves down-stream which have also been closed.
4.
continuous operation is allowed within the action statement indicating that the safety concern is that the valves are isolated in their safety position not that they are immedi-ately restored in operation.
5.
alternate nethods for sampling exist which provide represen-tative samples and do not increase operator dose rates, namely via the Steam Generator Blowdown Syten through valves 550-A-BD and 5500-BD or 10512-BD and 10513-80 for steam gen-erator A and 5508-B0 and a50E-BD or 1054-80 and 10515-BD for stema generator G and 550C-80 and 550F-BD or 10516-B0 and 10517-BD for steen generator C.
Although only two of the three steam generator sample line isolation valves are inoperable, the licensee has requested that the change be applicable for all three isolation valves as a precautionary measure.
We concur with the licensee that restart Of the Virgil C. Summer fluelear Station is i
the most feasible means of supplying the power needs.
The proposed fechnical Speci-fication change states that this one-time only exemptien will only last torough July 1,1983.
It is our understanding that the licensee plans to shutdown in late March 1983 or early April 1983 to perform steam generator modifications.
The licensee states that this is wheL the valve replacement will take place.
We agree that safe opeiation nay be conducted with these valves in the closed posi-I tion. Also, as stated above, steam generator sempling will not be interrupted as a l
resuit of this change.
Therefore, we feel the proposed change to be acceptable.
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. i ENVIRONMENTAL CONSIDERATION He have detenained that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any signif-icant environmental impact.
Having made this deternination, we have further con-cluded that the enendment involves an action which is insignificant fran the stand-point of environnental inpact and, pursuant to 10 CFR 951.5(d)(4), that an environ-mer tal impact statement or negative declaration and environnental impact appraisal reed not be prepared in connection with the issuance of this acendment.
CONCLUSION We have concluded, based on the considerations discussed above, that: (1)because the anendment does not involve a significant increase in the probability or con-sequences of accidents previously considered, does not create the possibility l
of an accident of a type different from any evaluated previously, and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health l
and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regu-
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lations and the issuance of this ataendrnent will not be inimical to the common defense and security or to the aealth and safety of the public.
Date: January 12, 1983 Principal Contributors: Jon Hopkins, Licensing Branch No. 4, DL Douglas Pickett, Operating Reactors Assessment Branch, DL i
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