ML20235G083
| ML20235G083 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/06/1987 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20235G085 | List: |
| References | |
| NUDOCS 8707140094 | |
| Download: ML20235G083 (4) | |
Text
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gth,otgna Electric & Gas Company nA n
gumgag29218 Nuclear Operations A $CNagA Corngapy July 6, 1987 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 Specifications Deletion of Organization Charts and Revision of Training Requirement' Gentlemen:
South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station.
The
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proposed changes delete the organization charts from the Technical Specifications and revise the retraining and replacement training program.
The NRC has previously approved a similar change to delete the organizational charts for the McGuire Nuclear Station, Units 1 and 2, on March 16, 1986.
The -proposal to delete the charts has been endorsed by the Westinghouse Owners' Group as a lead plant item.
Please refer to the marked-up copy of Sections 6.2 and 6.4 (Attachment III).
Previously, organization changes have resulted in SCE&G processing and NRC review of license amendment requests.
Consistent with the NRC and industry commitment to improve Technical Specifications, SCE&G proposes to delete the organization charts from the Technical Specifications, thereby eliminating needless expenditure of both NRC and utility resources.
As in the past, the NRC will continue to be informed of organizational changes through other required submittals.
For example, Chapter 13 of the Final Safety Analysis Report provides a description of the organization as well as detailed organization charts.
As required by 10CFR50.71(e), SCE&G submits annual updates to the FSAR.
10CFR50.54(a)(3) and 10CFR 50, Appendix B.
govern changes to the organization described in the Quality Assurance Program; some of these organizational changes require prior NRC approval.
The NRC resident inspector will also be made aware of any changes in the organization.
The proposed change to the training section revises the retraining and replacement training program to meet or exceed the requirements of amended 10 CFR 55 effective May 26, 1987. The Final Safety Analysis Report is being revised, as shown in Attachment IV, to reflect this change.
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Document Control Desk July 6. 1987 Page 2
..J Attachments I and II provide the Safety Hazards Considerations pursuant to 10CFR50.91(a)(1). These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety Review Committee.
Two checks in the amount of one hundred fifty dollars ($150.00) each are enclosed for processing these changes.
I declare 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 contact us at your convenience.
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Attachments c:
- 0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts
- 0. S. Bradham J. G. Connelly, Jr.
D. R. Moore W. A. Williams, Jr.
J.-N. Grace Group Managers W. R. Baehr C. A. Price C. L. Ligon (NSRC)
R. M. Campbell K. E. Nodland J. C. Snelson G. O. Percival J. B. Knotts, Jr.
R. L. Prevatte H. G. Shealy NPCF File
I Attachment I to Document Control Desk July 6, 1987 Page 1 of 1 SAFETY HAZARDS CONSIDERATION Deletion of Organization Charts Section 6.2 The Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazards consideration exists.
A proposed amendment to an operating license for a facility involves a significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because deletion of the organization charts does not affect plant operation in any manner.
2.
The proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated because the proposed change is administrative in nature and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.
3.
The proposed amendment does not involve a significant reduction in a margin of safety.
Through SCE&G's Quality Assurance programs and efforts to maintain only the most qualified personnel in positions of responsibility, it is assured that safety functions performed by the on-site and the corporate organizations will continue to be performed at a high level of competence.
Based on the above reasoning, SCE&G has determined that the proposed amendment does not involve a significant hazards consideration.
Attachment II to Document Control Desk July 6, 1987 Page 1 of 1 SAFETY HAZARDS CONSIDERATION Revision of Training Requirements Section 6.4 The Commission-has provided standards in 10CFR50.92(c) for determining whether a significant hazards consideration exists.
A proposed amendment to an operating license for a facility involves a significant hazards consideration if operation of the facility in accordance with the proposed amendment.would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
1.
The proposed amendment does not involve a significant increase in the probability or. consequences of an accident previously evaluated because the proposed Technical Specifications change only revises the administrative section to incorporate the new -10 CFR 55 requirements which improve the operator licensing process and examination content.
2.
The proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated because the proposed change is administrative in nature and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.
3.
The proposed amendment does not involve a significant reduction in a margin of safety.
The revised 10 CFR 55 improves the safety of the nuclear power plant by improving the operator licensing process and examination content.
]
Based on the above reasoning, SCE&G has determined that the proposed amendment does not involve a significant hazards consideration.
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