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{{#Wiki_filter:n 10CFR50.36 | {{#Wiki_filter:n 10CFR50.36 gi(c.gogina aeetric a ou company | ||
: s. nradjam j | |||
Nucisar Operabons geng<gSC 2900$ | |||
-SCE&G | |||
- ~.m December 11, 1989 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. | |||
20555 | |||
==Subject:== | ==Subject:== | ||
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating Licanse No. NPF-12 | Virgil C. Summer Nuclear Station Docket No. 50/395 Operating Licanse No. NPF-12 Technical Specification Change Request for Steam Generator Sleeving Gentlemen: | ||
Technical Specification Change Request for Steam Generator Sleeving Gentlemen: | t-South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station (VCSNS). The proposed change revises the surveillance requirements of Technical Specification 3/4.4.5, " Steam Generators," to allow the option of using the Babcock & Wilcox (B&W) kinetic sleeving process for steam generator 6 | ||
t-South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station (VCSNS). The proposed change revises the surveillance requirements of Technical Specification 3/4.4.5, " Steam Generators," to allow the option of | tube repair. This change will provide SCE&G with another alternative for handling degraded tubes. This letter reformats the previous submittal dated September 19, 1989, to comply with new guidance received from Mr. Jack Hayes, NRC Project Manager. | ||
using the Babcock & Wilcox (B&W) kinetic sleeving process for steam generator tube repair. This change will provide SCE&G with another alternative for handling degraded tubes. This letter reformats the previous submittal dated September 19, 1989, to comply with new guidance received from Mr. Jack Hayes, NRC Project Manager. | The change request is contained in the following attachments: | ||
The change request is contained in the following attachments: | . The Technical Specification pages with the requested changes indicated. -- A description of the amendment request and supporting safety evaluation. - A description of the amendment request and associated no significant hazards evaluation. | ||
SCE&G would like to utilize the B&W sleeving process at the next refueling outage..It is therefore requested that NRC review and approve this change by February 1, 1990 in order to support outage olanning activities. | |||
SCE&G would like to utilize the B&W sleeving process at the next refueling outage. .It is therefore requested that NRC review and approve this change by February 1, 1990 in order to support outage olanning activities. | |||
This proposed Technical Specification change has been reviewed and approved by the Plant Safety Review Committee and Nuclear Safety Review Committee. | This proposed Technical Specification change has been reviewed and approved by the Plant Safety Review Committee and Nuclear Safety Review Committee. | ||
4 Please note that a previous Technical Specification change request, Steam Generator L* Criteria, submitted on August 1, 1988 provided a corrected numbering scheme for Section 4.4.5.4. An additional editorial numbering / title revision is being submitted as part of this request. | 4 Please note that a previous Technical Specification change request, Steam Generator L* Criteria, submitted on August 1, 1988 provided a corrected numbering scheme for Section 4.4.5.4. | ||
An additional editorial numbering / title revision is being submitted as part of this request. | |||
A00I | A00I | ||
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0912200201 891211 | 0912200201 891211 | ||
.gDR ADOCK 0500 5 | |||
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7, | |||
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Document Control Desk December 11, 1989 Page 2 of 2 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, ise | Very truly yours, ise | ||
: 0. S. Bradham g | ,/ | ||
E. C. Roberts W. A. Williams,'Jr. | : 0. S. Bradham g | ||
ARR/OSB: led Attachments c:- | |||
D. A..Nauman/0. W. Dixon,'Jr./T. C. Nichols, Jr. | |||
E. C. Roberts W. A. Williams,'Jr. | |||
S. D. Ebneter J._J. Hayes, Jr. | S. D. Ebneter J._J. Hayes, Jr. | ||
General Managers C. A. Price R. B. Clary | General Managers C. A. Price R. B. Clary | ||
'K. E. Nodland J. C. Snelson R. L. Prevatte-J. B. Knotts, Jr. | |||
H. G. Shealy A. M. Monroe A. R. Rice NSRC NPCF RTS l(TSP 890014) | H. G. Shealy A. M. Monroe A. R. Rice NSRC NPCF RTS l(TSP 890014) | ||
File (813.20) i-o l | File (813.20) i-o l | ||
| Line 57: | Line 60: | ||
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-4 ATTACHMENT 1 L | |||
Marked Up Technical Specification Pages Pace Specification Chance Description | |||
- 3/4 4-14~ | |||
4.4.5.4.a.6 Revises th'e title for 4.4.5.4.a.6 and-adds item 4.4.5.4.a.7 to more clearly delineate tube versus sleeve plugging or repair limits. | |||
- 3/4 4-14a 4.4.5.4.a.7 - 4.4.5.4.a.10-Renumbers the Technical | |||
4.4.5.4.a.10 | . Specification as 4.4.5.4.a.8-4.4.5.4.a.11 based on.the addition of item 4.4.5.4.a.7. | ||
4.4.5.4.a.10 Adds a second. steam generator tube sleeving option and references report BAW-2045P. | |||
v-- | ' 3/4 4-15 4.4.5.4.a.9 - 4.4.5.4.a.11 Renumbers the Technical Specification as 4.4.5.4.a.12-4.4.5.4.a.14 to correct a numbering error and reflect the addition of item 4.4.5.4.a.7. | ||
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Latest revision as of 17:52, 25 December 2024
| ML19332G134 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/11/1989 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19332G135 | List: |
| References | |
| NUDOCS 8912200201 | |
| Download: ML19332G134 (3) | |
Text
n 10CFR50.36 gi(c.gogina aeetric a ou company
- s. nradjam j
Nucisar Operabons geng<gSC 2900$
-SCE&G
- ~.m December 11, 1989 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating Licanse No. NPF-12 Technical Specification Change Request for Steam Generator Sleeving Gentlemen:
t-South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station (VCSNS). The proposed change revises the surveillance requirements of Technical Specification 3/4.4.5, " Steam Generators," to allow the option of using the Babcock & Wilcox (B&W) kinetic sleeving process for steam generator 6
tube repair. This change will provide SCE&G with another alternative for handling degraded tubes. This letter reformats the previous submittal dated September 19, 1989, to comply with new guidance received from Mr. Jack Hayes, NRC Project Manager.
The change request is contained in the following attachments:
. The Technical Specification pages with the requested changes indicated. -- A description of the amendment request and supporting safety evaluation. - A description of the amendment request and associated no significant hazards evaluation.
SCE&G would like to utilize the B&W sleeving process at the next refueling outage..It is therefore requested that NRC review and approve this change by February 1, 1990 in order to support outage olanning activities.
This proposed Technical Specification change has been reviewed and approved by the Plant Safety Review Committee and Nuclear Safety Review Committee.
4 Please note that a previous Technical Specification change request, Steam Generator L* Criteria, submitted on August 1, 1988 provided a corrected numbering scheme for Section 4.4.5.4.
An additional editorial numbering / title revision is being submitted as part of this request.
A00I
\\
0912200201 891211
.gDR ADOCK 0500 5
i:
7,
'E l
Document Control Desk December 11, 1989 Page 2 of 2 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, ise
,/
- 0. S. Bradham g
ARR/OSB: led Attachments c:-
D. A..Nauman/0. W. Dixon,'Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams,'Jr.
S. D. Ebneter J._J. Hayes, Jr.
General Managers C. A. Price R. B. Clary
'K. E. Nodland J. C. Snelson R. L. Prevatte-J. B. Knotts, Jr.
H. G. Shealy A. M. Monroe A. R. Rice NSRC NPCF RTS l(TSP 890014)
File (813.20) i-o l
l-
n i
-4 ATTACHMENT 1 L
Marked Up Technical Specification Pages Pace Specification Chance Description
- 3/4 4-14~
4.4.5.4.a.6 Revises th'e title for 4.4.5.4.a.6 and-adds item 4.4.5.4.a.7 to more clearly delineate tube versus sleeve plugging or repair limits.
- 3/4 4-14a 4.4.5.4.a.7 - 4.4.5.4.a.10-Renumbers the Technical
. Specification as 4.4.5.4.a.8-4.4.5.4.a.11 based on.the addition of item 4.4.5.4.a.7.
4.4.5.4.a.10 Adds a second. steam generator tube sleeving option and references report BAW-2045P.
' 3/4 4-15 4.4.5.4.a.9 - 4.4.5.4.a.11 Renumbers the Technical Specification as 4.4.5.4.a.12-4.4.5.4.a.14 to correct a numbering error and reflect the addition of item 4.4.5.4.a.7.
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