ML20245F227
| ML20245F227 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245F225 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8908140211 | |
| Download: ML20245F227 (3) | |
Text
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g NUCLEAR REGULATORY COMMISSION n
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 99 AND 76 T'O FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM GENERATING STATION, UNIT NOS. 1 AND 2 000 ET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated July 15, 1988 and supplemented by letters dated April 25 1989 and May 24, 1989, Public Service 21ectric & Gas Company requested an amendment to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Generating Station,. Unit Nos. I and 2.
The April 25, 1989 letter revised the original submittal to provide the title of the senior corporate official responsible for nuclear safety. The May 24, 1989 letter provided revised Technical Specification pages. The proposed a.nendments would delete the organization charts, Figures 6.2-1 and 6.2-2 from the Technical Specifications and replace them with a more generalized organizational requirement.
2.0 EVALUATION The Technical Specifications currently have organization charts included.
The'NRC staff experience has shown that organization charts can be modified in many ways while maintaining adequate operational safety.
The staff has issued Generic Letter 88-06, Removal of Organization Charts from Technical Specification Administrative Control Requirements, to l
provide guidance to the utilities in removing the organization charts.
The proposed amendments make two types of changes to the Administrative Controls, Section 6.0, of the Salem Generating Station Technical Specifications, Units 1 and 2.
The first change involves the deletion of the offsite and onsite organization charts, Figures 6.2-1 and 6.2-2, and replaces them with more general requirements which capture the essential aspects of the organizational structure. Technical Specifications (TSs) 6.1.1 and 6.1.2 have been supplemented with the necessary general requirements specified ir, Generic Letter 88-06, dated March 22, '.988.
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The second change replaces the reference to the Vice President - Nuclear, contained in TS 6.1.2, with the title Vice President and Chief Nuclear Officer.
For consistency, TSs 6.2.1, 6.5.1.~6, 6.5.1.8, 6.5.1.9, 6.5.2.4.2, 6.5.2.6, 6.5.2.7, 6.6.1, and 6.7.1, have also had the title, Vice Prerident - Nuclear, replaced with the title, Vice President and Chief Nuclear Officer. This change is necessary because the title, Vice President - Nuclear, has been changed to, Vice President and Chief Nuclear Officer, and the Technical Specifications as currentl3 structured should reflect this change.
The NRC staff will continue to be informed of organizational changes through other required controls. The Code of Federal Regulations, Title 10, Part 50.34(b)(6)(1) requires that the applicants organizational structure be included in the Final Safety Analysis Report. Chapter 13 of the Salem Generating Station Updated Safety Analysis Report (UFSAR) provides a description of the organization and detailed organization charts. This chapter of the UFSAR already contains the minimum information specified in Generic Letter 88-06.
In accordance with 10 CFR 50.71(e), PSE8G submits annual updates to the UFSAR and has committed to continue this practice.
In addition, changes ~to the organization described in.the Quality Assurance P Appendix B and by 10 CFR 50.54(a)(3)rogram are governed by 10 CFR 50, Any changes to the organizational structure which have the potential to decrease the effectiveness of the Quality Assurance Program require prior NRC approval.
Furthermore, it has been~PSE&G's practice to inform the NRC of major organizational changes affecting the nuclear facilities prior to implementation. They have restated their intention to continue this practice for such future changes in organizational structure.
The Index is also being revised to bring it into agreement with the aforementioned changes and to update it to reflect the actual location of the sections.
The licensee's proposal is in conformance with the guidance provided in Generic Letter 88-06 and is therefore acceptable.
In addition, administrative clarifications and typographical corrections were made to the licensee's incoming technical specification pages and bars were added to those pages to show the changes.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change to administrative requirements. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public connent on such finding. 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 raed be prepared in connection with the issuance of the amendments.
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8 4.0 CONCLUSICW The Commission made a proposed determinatforf that the amendments involve no significant hazards consideration which was published in the Federal Register (54 FR 23322) on May 31, 1989 and consulted with the State of New Jersey. No public comments were received and the State of New Jersey did not have any comments.
The staff 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor: Jim Stone Dated:
July 31,.1989 e
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