ML20247K923
| ML20247K923 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/21/1989 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247K929 | List: |
| References | |
| NUDOCS 8908010099 | |
| Download: ML20247K923 (2) | |
Text
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Eg O. Box 88 Prhs den
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JInMnwilla, SC 29065
. Nuclear Op3 rations (803) 345-4040 SCE&G a r.aw,,
k July 21, 1989 h4 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 s
Technical Specifications Change Request'- RHR Autoclosure Interlock Removal Gentlemen:
South Carolina Electric &~ Gas Company (SCE&G) hereby requests an amendment to Technical Specifications Section 3/4.5.2, " Emergency Core Cooling Systems,"
in support of the removal of the Residual Heat Removal (RHR) system autoclosure interlock (ACI).
'Specifically, this proposed amendment deletes the surveillance requirement associated with the ACI to test the autoclosure capability every 18 months.
Removal.of the RHR ACI addresses utility and Commission concerns regarding the potential for failure of the ACI circuitry to cause inadvertent RHR isolation with the resulting loss of RHR capability during cold shutdown and refueling operations. A Westinghouse analysis has demonstrated that removal of the RHR ACI improves the availability of the RHR system during short-term cooldown (within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of shutdown) and long-term cooldown (after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following shutdown) by 24 and 38 percent, respective;y.
Further, the frequency of an interfacing loss-of-coolant accident is reduced by 33 percent.
The marked-up page for the proposed amendment to 3/4.5.2 is provided in.
The proposed no significant hazards evlauation is provided as.
Also provided as Attachments 3 and 4 respectively, are Westinghouse WCAP-11736 (Westinghouse Owners Group generic analysis) and WCAP-11835 (V. C.
Summer Nuclear Station plant specific analysis).
This request has been reviewed and approved by both the Plant Safety Review
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Committee and the Nuclear Safety Review Committee.
f glr *ASSEES$8k!5 hfy i
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Document Control. Desk
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' July 21, 1989 Page 2 J;
. I declare that'the statements and. matters set forth herein are true and S
correct to'the best.of my knowledge, information and belief.
- Should'you have any questions,7please call at-your convenience.
uly yours, 634t&p
- 0. S. Bradham
' MDB/OSBiled
- Attachments c:
D. A'.lNauman/0..'W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A." Williams, Jr..
S. D. Ebneter
'J.'J.. Hayes, Jr..
General I4anagers C. A. Price /R. M. Campbell, Jr.
R. B.'Clary 4
K. E. Nodland J.'C. Snelson
- G. 0.'Percival R. L. Prevatte
- J. B;;Knotts, Jr.
- H. G. Shealy M. D. Blue
, NSRC-RTS '(TSP 890008)
' ilPCF File (813.20) l l
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