ML20154H105
| ML20154H105 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/16/1988 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20154H109 | List: |
| References | |
| NUDOCS 8805250227 | |
| Download: ML20154H105 (4) | |
Text
_.
So th Car lina Electric & Gas Company Dan A. Nauman Jenkinsville. SC 29065 Nuclear Operations SCE&G (8 3) 3'"
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May 16, 1988 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/396 Operating License No. NPF-12 Technical Specification Change Steam Generator Sleeving Gentlemen:
Sour.h Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station.
Specifically, this proposed change revises surveillance requirement 4.4..i.4.a.10 of Technical Specification 3/4.4.5, "Steam Generators," to allow the use of various steam generator weld sleeve processes contingent upon prior Nuclear Regulatory Commission approval.
Currently, the Licensee is restricted by Technical Specifications to use the Combustion Engineering weld sleeve process per report CEN-337-P. This Technical Specification change is being submitted as an administrative change since SCE&G is not requesting a weld siteve process different from the Combustion Engineering process currently used. and 2 constitute the licensing submittal for this Technical Specification change. Attachment 1 provides the marked-up copy of the affected page. Attachment 2 provides the significant hazards evaluation pursuant to 10CFR50.92.
This proposed Technical Specification amendment has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. The application fee of $150 is enclosed.
Should you have any questions concerning this Technical Specifications amendment request, please call at your convenience.
Very truly yours, Y
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- 0. A. Nauman MOB /0AN: led Attachment pc: See Page 2 l
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Document Control Desk May 16, 1988 Page 2 pc:
J. G. Connelly, Jr./0. W. Dixon,-Jr./T. C. Nichols,'r.
J E. C. Roberts W. A. Williams, Jr.
J. N. Grace J. J. Hayes, Jr.
General Managers C. A. Price R. 8. Clary W. R. Higgins R. M. Campbell, Jr.
K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte J. B. Knotts, Jr.
H. G. Shealy M. D. Blue NSRC RTS (TSP 880010)
NPCF File (813.20) n.-
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ATTACHMENT 1 PROPOSED AMENDMENT MARKED-UP PAGES Page Technical Specification 3/4 4-14a 3/4.4.5, "Steam Generators"
ATTACHMENT 2 SIGNIFICANT HAZARDS EVALUATION FOR VIRGIL C. SUMMER NUCLEAR STATION STEAM GENERATOR SLEEVING Description of amendment request:
The proposed amendment revises surveillance requirement 4.4.5.4.a.10 of Technical Specification 3/4.4.5, "Steam Cenerators," to allow the use of various steam generator weld sleeve processes contingent upon prior Nuclear Regulatory Commission (NRC) approval.
Currently, the Licensee is restricted by this surveillance requirement to use the Combustion Engineering weld sleeve process per report CEN-337-P.
The proposed amendment would allow use of the Combustion Engineering weld sleeve process as well as other previously approved designs.
Basis forproposed no significan t hazards consideration determination:
This proposed amendment is administrative in nature in that the Licensee is not seeking technical approval of other weld sleeve processes but is simply amending the Technical Specification for future use of various weld sleeve processes.
The use of a weld sleeve process different from that of the Combustion Engineering weld sleeve process per report CEN-337-P would be formally submitted to the (NRC) for review and approval.
The Ccanission has provided certain examples (51 FR 7744) of actions likely to involve no significant hazards considerations.
The request involved in this case matches example (i), a purely administrative change to Technical Specifications.
Further, the Licensee has reviewed the proposed amendment and determined that should this request be implemented, it will not (1) involve a significant increase in the probability or consequences of an accident previousiy evaluated because this change is administrative in nature i
and does not change plant equipment or procedures, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated because no plant equipment or procedure changes are involved and only an NRC approved weld sleeving process would be used should sleeving te required. Also, it will not (3) involve a significant reduction in the margin of safety because this change is administrative in nature and any process used would require NRC prior approval.
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