ML20247K671: Difference between revisions
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_t | _t l10 CFR-50.36 South C:rolina Electric & G*s Comp:ny ollie S. Brrdh"m s | ||
South C:rolina Electric & G*s Comp:ny | e ki vi SC 20065 ' | ||
u le r per tIons SCE&C a.ca n July 24, 1989 jg Document Control Desk | |||
.U. S. Nuclear Regulatory Commission Washington, DC 20555 | |||
==Subject:== | ==Subject:== | ||
Virgil C. Summer Nuclear Station Docket No. 50/395 | Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specification Change Steam Generator F* Criterion Gentlemen: | ||
. South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the~ Virgil C.. Summer Nuclear Station (VCSNS). Specifically, the proposed change revises the surveillance requirements of Technical Specification 3/4.4.5.." Steam Generators," to | |||
-extend the application of the F* tube plugging criterion for the life of the Lsteam generators. Administrative 1y, the definition of an F* tube was clarified by grammatically restructuring the phrase without altering the technical content. | |||
: Attachments 1, 2,'and 3 constitute the licensing submittal for the requested Technical-Specification change. Attachment 1 contains the marked-up Technical Specification pages Attachment 2 contains the safety analysis and supporting technical justification for the change, and Attachment 3 is the | : Attachments 1, 2,'and 3 constitute the licensing submittal for the requested Technical-Specification change. Attachment 1 contains the marked-up Technical Specification pages Attachment 2 contains the safety analysis and supporting technical justification for the change, and Attachment 3 is the | ||
-significant hazards evaluation pursuant to 10CFR50.91. | |||
This proposed Technical Specification change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. | This proposed Technical Specification change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. | ||
I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information and belief. | I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information and belief. | ||
Should you have any questions, please call at your convenience. | Should you have any questions, please call at your convenience. | ||
Very truly yours, | Very truly yours, | ||
: 0. S. Bradham AMM/OSB: led Attachments | : 0. S. Bradham | ||
c: | [I AMM/OSB: led Attachments f | ||
\\ | |||
c: | |||
See Page 2 8908010024 890724 PDR ADOCK 05000393 P. | |||
PDC | |||
m.. | m.. | ||
i g-l . | i g-l.. | ||
Document Control Desk July 24, 1989 Page 2 c: | Document Control Desk July 24, 1989 Page 2 c: | ||
i' | D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr. | ||
i' E. C. Roberts W. A. Williams, Jr. | |||
S. D. Ebneter J. J. Hayes, Jr. | S. D. Ebneter J. J. Hayes, Jr. | ||
General Managers | General Managers C. A. Price /R. M. Campbell, Jr. | ||
R. B. Clary K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte J. B. Knotts, Jr. | |||
R. B. Clary K. E. Nodland | |||
H. G. Shealy NSRC NPCF RTS (TSP 880027) | H. G. Shealy NSRC NPCF RTS (TSP 880027) | ||
File (813.20) | File (813.20) | ||
.}} | .}} | ||
Latest revision as of 20:05, 1 December 2024
| ML20247K671 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/24/1989 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247K675 | List: |
| References | |
| NUDOCS 8908010024 | |
| Download: ML20247K671 (2) | |
Text
_
_t l10 CFR-50.36 South C:rolina Electric & G*s Comp:ny ollie S. Brrdh"m s
e ki vi SC 20065 '
u le r per tIons SCE&C a.ca n July 24, 1989 jg Document Control Desk
.U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specification Change Steam Generator F* Criterion Gentlemen:
. South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the~ Virgil C.. Summer Nuclear Station (VCSNS). Specifically, the proposed change revises the surveillance requirements of Technical Specification 3/4.4.5.." Steam Generators," to
-extend the application of the F* tube plugging criterion for the life of the Lsteam generators. Administrative 1y, the definition of an F* tube was clarified by grammatically restructuring the phrase without altering the technical content.
- Attachments 1, 2,'and 3 constitute the licensing submittal for the requested Technical-Specification change. Attachment 1 contains the marked-up Technical Specification pages Attachment 2 contains the safety analysis and supporting technical justification for the change, and Attachment 3 is the
-significant hazards evaluation pursuant to 10CFR50.91.
This proposed Technical Specification change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee.
I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information and belief.
Should you have any questions, please call at your convenience.
Very truly yours,
- 0. S. Bradham
[I AMM/OSB: led Attachments f
\\
c:
See Page 2 8908010024 890724 PDR ADOCK 05000393 P.
m..
i g-l..
Document Control Desk July 24, 1989 Page 2 c:
D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.
i' E. C. Roberts W. A. Williams, Jr.
S. D. Ebneter J. J. Hayes, Jr.
General Managers C. A. Price /R. M. Campbell, Jr.
R. B. Clary K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte J. B. Knotts, Jr.
H. G. Shealy NSRC NPCF RTS (TSP 880027)
File (813.20)
.