ML20154Q633
| ML20154Q633 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/17/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20154Q636 | List: |
| References | |
| NUDOCS 8603210210 | |
| Download: ML20154Q633 (2) | |
Text
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South Carolina Electric a Ga3 Company Dan A. N:uman P.O. Box 761 Vice President Columbia. SC 29218 Nuclear Operations (803) 748-3513 SCE&G March 17, 1986
' =am ' -
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Administrative Technical Specification Changes
Dear Mr. Denton:
Enclosed are Attachments 1 and 2, administrative changes to the Virgil C. Summer Nuclear Station Technical Specifications.
A discussion of each of these proposed changes follows.
As shown on Attachment 1, South Carolina Electric and Cas Company (SCE6G) requests that the wording for the review of individual overtime by the Director, Nuclear Plant Operations or his designee be clarified for applicability during extended shutdown periods. This request is in accordance with a letter from Elinor G. Adensam of your Staf f to 0. W. Dixon, Jr. dated June 27, 1985.
As shown on Attachment 2, item d. of the required Emergency Care Cooling System (ECCS) Subsystems during Mode 4 is clarified to reflect the actual ECCS alignment changes that would be required for ECCS operation in Mode 4.
Technical Specification 3.5.3, " Emergency Core Cooling Systems," as currently written is not clear in its intent to allow the Residual Heat Removal (RHR)
System to be aligned to the Reactor Coolant System (RCS) during Mode 4 and to utilize manual alignment to the Refueling Water Storage Tank (RWST) upon initiation of a Safety Injection signal. The preceeding alignment, based upon Westinghouse Standard Technical Specifications, is consistent with Technical Specification 3.4.9.3, " Overpressure Protection Systems," which requires that both trains of RHR be aligned to the RCS during Mode 4.
A finding of no significant hazards is appropriate for these changes because the changes are clarifying and administrative in nature.
This request has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. A check in the amount of one hundred fif ty dollars ($150.00) is enclosed to initiate the processing of this request.
If you have any questions, please advise.
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Mr. Harold R. Denton Page Two March 17, 1986 MDB: DAN:tdh Attachments c:
V. C. Summer O. W. Dixon, Jr./T. C. Nichols, Jr.
E. H. Crews, Jr.
E. C. Roberts W. A. Williams, Jr.
J. G. Connelly, Jr.
J. N. Grace Group Managers
- 0. S. Bradham D. R. Moore C. A. Price R. M. Campbell C. L. Ligon (NSRC)
K. E. Nodland R. A. Stough G. Percival R. L. Prevatte J. B. Knotts, Jr.
H. G. Shealy NPCF File 1
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