ML19347B567
| ML19347B567 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/29/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347B566 | List: |
| References | |
| NUDOCS 8010150362 | |
| Download: ML19347B567 (2) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
.p WASHINGTON, D. C. 20556
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SAFETY EVALUATI0fl BY THE OFFICE OF NUCLEAR REACTOR REGULATION j
SUPPORTING AMENDf1ENT NO. 30 TO FACILITY LICENSE NO. DPR-71 CAROLINA POWER & LIGHT COMPANY a
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 i
DOCKET N0. 50-335 l
1.0 Introduction By letter dated September 15, 1980 Carolina Power & Light Company LP&L or licensee) requested an extension of the end date for temporary ietpoints in effect on 3 of the 11 BSEP-1 safety-relief valves (SRVs).
This change was necessitated by revisions to the BSEP outage schedule which drferred the T-quencher modification on BSEP-1 to an outage in spring 198C. The staff was advised of the Mark I Containment Program modificatic i schedule
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by CP&L letter dated September 2, 1980.
2.0 Discussion Amendment No. 29 to Facility Operating License No. DPR-71 authorized a 20 psi SRV setpoint differential pressure spread for each of the paired SRVs.
This change was made to provide added assurance that SRVs with paired discharge headers would not be likely to experience "a pipe organ" response in an overpressure transient, similar to the event that occurred following a BSEP-1 scram on November 20, 1979.
(Refer to LER l-79-107 dated December 20,1979).
The staff concluded that the setpoint spread was an adequate compensatory measure, pending installation of the l
T-quencher modification and removal of the paired discharge headers.
3.0 Evaluation The end date cf the original TS change was September 1980, as requested by the licensee.
Had the end date been keyed to the conpletion of the j
T-quencher modification, it would have been equally acceptable.
4.0 Finding l
The SRV setpoint sprera authorized by Amendment No. 29 to DPR-71 is an acceptable interin measure until such time as the SRV discharge headers are modified under the Long Tera liark I Program.
Therefore, the TS change proposed by the licensee is acceptable.
5.0 Environmental Consideration
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We have determined that the license amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will 8010150 3[p$
not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR Section 51.5(d)(4) that an environmental impact statement or negative declaration and environmental impact apprairal need not be prepared in connection with the issuance of this amendment.
6.0 Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendmerit does not involve a significant increase in the probability or consequences of accidents previously considered 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 and safety of the public will not be endangered by operation in the proposed manner, and (3) such activ-ities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical ta the common defense and security or to the health and safety of the public.
Dated: September 29, 1980 I
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