ML16138A733
| ML16138A733 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/01/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A732 | List: |
| References | |
| NUDOCS 9205200334 | |
| Download: ML16138A733 (3) | |
Text
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.193TO FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO.193 TO FACILITY OPERATING LICENSE DPR-47 AMENDMENT NO.190 TO FACILITY OPERATING LICENSE DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
By letter dated January 2, 1992, as supplemented February 14, 1992, the Duke Power Company (the licensee) submitted a request for changes to the Oconee Nuclear Station, Units 1, 2, and 3 Technical Specifications (TS). The requested changes would revise the Administrative Controls section to reflect a reorganization of the Duke Power Company (DPC). The reorganization essentially decentralizes the corporate management of nuclear activities to each of DPC's three nuclear site facilities, including the Oconee Site. The revisions to the TS also reflect and are complementary to revisions to the DPC Quality Assurance Topical Report. The review of this report, based upon the guidance of Standard Review Plan 17.3 as issued in August 1990, is being addressed as a separate action from the revision of the TS.
2.0 EVALUATION 2.1 Administrative Controls
- a. Section 6.1.1 - Organization - The designation "facility" has been changed to "plant", and the designation "health physics" has been changed to "radiation protection". The Vice President, Oconee Nuclear Site, now has responsibility for overall plant nuclear safety and the Senior Vice President, Nuclear Generation, will have responsibility for overall nuclear safety. In addition, the titles of Station Health Physicist, Superinten dent of Operations, Operating Engineer, and System Health Physicist have been changed to Radiation Protection Manager, Operations Superintendent, Shift Operations Manager, and Nuclear Technical Services Manager, respec tively. The position of Shift Manager has been created that subsumes the function of the Shift Technical Advisor (STA). This change in title has also been made in Table 6.1.1.
The NRC staff finds these changes acceptable as they reflect the revised organization and reassignment of responsibilities, and the function of the STA has been retained in the position of Shift Manager.
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- b. Section 6.1.2 - Technical Review and Control - The approval authority for proposed modifications to unit nuclear safety-related structures, systems, and components, and proposed tests and experiments which affect nuclear safety have been revised to conform to the revised organization. Other titles have been changed throughout this section to reflect the revised organization and the reassignment of responsibilities, and the designation "station" has been changed to "site".
- c. Section 6.1.3 - Nuclear Safety Review Board (NSRB) - The titles of Vice President, Nuclear Production Department; Nuclear Production Department; Quality Assurance Department; and Executive Vice President, Nuclear Production Department have been replaced to reflect the revised organization, and the designation "station" has been changed to "site".
In Subsection 6.1.3.2, the qualification requirements for NSRB members has been revised to allow, in special cases, an individual with ten years experience in a specific technical area. In Subsection 6.1.3.4, Audits, the licensee has relocated the audit frequency from the audits required by this subsection.
Audit frequency requirements are now addressed in the Duke Quality Assurance Topical Report and are performance-based on the safety significance and extent of the activities except those for the Emergency and Security Plans as discussed below.
The NRC staff finds these changes acceptable as they reflect the revised organization and reassignment of responsibilities, the appropriate acceptance criteria of Section 13.4 of NUREG-0800, the Standard Review Plan, and the commitment to performance-based audits in DPC's revised Duke Quality Assurance Topical Report, a document controlled in accordance with 50.54(a).
- d. Section 6.2 - Action To Be Taken in the Event Of A Reportable Occurrence The titles in this section have been revised to reflect the revised organization.
The NRC staff finds these changes acceptable as they reflect the revised organization.
- e. Section 6.3 - Action To Be Taken In The Event A Safety Limit Is Exceeded The titles in this section have been revised to reflect the revised organization.
The NRC staff finds these changes acceptable as they reflect the revised organization.
We find the above changes to the Administrative Controls Section of the Technical Specifications for the Oconee Nuclear Station, as described in the letters dated January 2, 1992, and February 14, 1992, acceptable.
-3 2.2 Security and Emergency Plan The requirements in TS 6.1.2.1.h for review of the security program and implementing procedures and in TS 6.1.2.1.i for review of the station emergency plan and implementing procedures are removed from the TS and are relocated to the respective security and emergency plans. Once they are included in the respective plans, further changes in these review requirements must be made in accordance with 10 CFR 50.54(P) for the security plan and with 10 CFR 50.54(q) for the emergency plan. The NRC staff concludes that, in conjunction with this change to the plans, the extensive requirements for emergency planning in 10 CFR 50.47 and 50.54 and for security in 10 CFR 50.54 and 73.55 for drills, exercises, testing and the maintenance of the programs provides adequate assurance that the objective of the previous TS 6.1.2.1.h and TS 6.1.2.1.i for a periodic review of the programs and changes to the programs will be met. Therefore, this change is acceptable.
The requirements of TS 6.1.3.4.e and.f for an audit on a twelve month frequency by the corporate Nuclear Safety Review Board (NSRB) of the emergency and security plans and implementing procedures is modified by deleting the specification of the twelve month frequency. This results in no change in this regulatory requirement since the frequency of such independently conducted reviews is also specified in 10 CFR 50.54(t) for the emergency plan, in 10 CFR 50.54(P)(3) for the safeguards contingency plan and in 10 CFR 73.55(g)(4) for the security program. This change is acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: F. Allenspach, LPEB Date:
May 1, 1992