ML20091A781
| ML20091A781 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/23/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20091A787 | List: |
| References | |
| NUDOCS 8405300085 | |
| Download: ML20091A781 (2) | |
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SOUTH CAROLINA ELECTRIC 8: GAS COMPANY post ovvet vu Cowwem. Soum CApoLma 29218 c w cno% so.
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May 23, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Otanission Washington, D.C. 20555
Subject:
Virgil C. Sunner Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Installation of P-9 Interlock
Dear Mr. Denton:
South Carolina Electric and Gao Conpany (SCF4G) hereby requests a revision to the Virgil C. Summr Wclear Station Technical Soecifications to allow for the installation of an interlock to provent a dlrect reactor trip following a turbine trip at or below 50% reactor power.
Wis P-9 Interlock, designed by Westinghouse Corporation, will prevent needless challenges to the Reactor Protection System and the initiation of unnecessary transients to the Reactor Coolant Systen during startup of the reactor. Please find enclcsed ten (10) copies of the analysis that supports the preposed modification and the associated Technical Specification changes.
As shown in the attachal analysis, inplementation of the P-9 interlock modification is possible since the Virgil C. Smmer Mclear Station is designed for full load rejection with 85% steam dunp capability. We results of this analysis show that the Virgil C. Smner Nuclear Station design can acy Mate a turbine trip without an inmediate reactor trip and will not jeopardize the integrity of the reactor coolant system or the main steam system. %is analysis also demonstrates that the nodification is not expected to significantly increase the probability of a sosll break IDCA due to a stuck-open Power Operated Relief Valve.
SCFAG has termined that a finding of no significant hazards is justified based on t!he attached analysis and because pressure relieving devices incorporated in the Virgil C. Sunner Mclear Station main steam system are adequate to limit maxinun expected pressures to within the design limits.
to Technical Specification changes have been reviewed and approved by both the Plant Safety Review Comnittee (PSRC) and the Nuclear Safety Review (benittee (NSRC). A check in the amount of Four Wousand Dollars
($4000.00) is enclosed for processing the change.
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,7 Mr. Harold R. Denton Installation of P-9 Interlock May 23, 1984 Page 42 SCEEG's current plans project the installation of this modification during the first refueling outage scheduled for September 1984.
'Ib support this schedule, a high priority review by the NRC Staff and an expeditious response to any Staff questions by the Licensee is
. essential.
If there are any questions, please advise.
Very truly yours, s
O. W. D n, Jr.
NN OE/gj Enclosure cc V. C. Sumer C. A. Price T. C. Nichols, Jr./O. W. D12 eon, Jr.
C.'L. Li n (NSRC)
E. H. Crews, Jr.
K. E.
land E. C. Roberts R. A. Stmgh W. A. Williams, Jr.
G. Percival-D. A. Naman C. W. Hehl J. P. O'Reilly J. B. Knotts, Jr.
Group Managers H. G. Shealy O. S. Bralham NPCF File f