ML16138A724

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Safety Evaluation Supporting Amends 190,190 & 187 to Licenses DPR-38,DPR-47 & DPR-55,respectively
ML16138A724
Person / Time
Site: Oconee  
Issue date: 08/30/1991
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML16138A723 List:
References
NUDOCS 9109120253
Download: ML16138A724 (4)


Text

vtREGu UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. l90TO FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 190TO FACILITY OPERATING LICENSE DPR-47 AMENDMENT NO. 187TO 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 February 7, 1991, 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 delete the Organization charts from Section 6 of the TSs and the associated bases, and add new statements addressing particular administrative control requirements related to the licensee organization. These changes are based on NRC guidance provided in Generic Letter 88-06. Specifically, the licensee has proposed changes that would (1) expand Specification 6.1.1 to include a requirement for establishing onsite and offsite organizations for unit operation and corporate management; (2) provide a new requirement for establishing lines of authority, responsibility, and communication in Specification 6.1.1.1; (3) replace the current Specification 6.1.1.2 with a new Specification 6.1.1.2 to designate the station manager as the management position responsible for overall unit operation; (4) replace the current Specification 6.1.1.3 with new Specification 6.1.1.3 to designate an executive position that has corporate responsibility for overall plant safety; (5) change the title "General Manager, Nuclear Stations," to "Vice President, Nuclear Operations," in Specification 6.1.1.4 to reflect changes in corporate organization; (6) specify the minimum operating shift crew require ments in Specification 6.1.1.6; (7) delete Figures 6.1.1 and 6.1.2; and (8) make the required editorial changes to the numerical sequence of the specifica tions and figures. The organization charts currently in Chapter 13 of the Final Safety Analysis Report (FSAR) identifying the lines of authority will be updated routinely to reflect changes in the organizations.

2.0 EVALUATION Currently, for the Oconee Nuclear Station, onsite and offsite organizations are shown by organization charts included under Administrative Controls of the TSs.

This practice requires the processing of a license amendment to change an organization chart before implementing a change in organizational structure.

Generic Letter 88-06 provides guidance for deleting these organization charts from the TSs and requires the addition of general requirements that would capture the essential aspects of the organization charts being deleted. This regulatory change results from staff experience concluding that organization charts can be modified while maintaining adequate operational safety.

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-2 Generic Letter 88-06 identified that the only aspects of organization charts which are important to safety would include (1) lines of authority, responsibility, and communication to be established and updated in documents like the FSAR; (2) designation of the authority responsible for overall unit safe operation including onsite activities necessary for safe operation and maintenance of the plant; (3) designation of the executive having corporate responsibility for overall plant nuclear safety, including measures for acceptable performance of staff in operation, maintenance, and technical support to ensure nuclear safety; (4) establishment of the independence from operating pressures for individuals who train the operating staff and who carry out health physics and quality assurance functions even though they report to appropriate onsite managers; and (5) the designation of the positions requiring a Senior Reactor Operator and/or Reactor Operator license.

The changes proposed by the licensee are in accordance with the guidance provided by Generic Letter 88-06. The proposed changes to Section 6 of the Oconee Nuclear Station TSs follow the guidance and specific details provided in Enclosures 1 and 2 of Generic Letter 88-06. These changes are as follows:

1. Specification 6.1.1 includes a requirement for establishing onsite and offsite organizations for unit operation and corporate management consistent with the Generic Letter 88-06 guidance and the Standard Technical Specifications.
2. Specification 6.1.1.1 establishes a new requirement for establishment of lines of authority, responsibility, and communication.
3. The current TSs 6.1.1.2 and 6.1.1.3 are deleted. The proposed Specification 6.1.1.2 designates the station manager as the management position responsible for overall unit operation, while proposed Specification 6.1.1.3 is a new requirement which designates an executive position that has corporate responsibility for overall plant safety.
4. Organization charts in Figures 6.1.1 and 6.1.2 are deleted pursuant to Generic Letter 88-06 guidance. The existing organization charts in Chapter 13 of the FSAR depicting the lines of authority and responsibility will be updated as necessary for any future changes to these organizations. The List of Figures on page viii is revised to indicate the deletion of the Organizational Charts on pages 6.1.7 and 6.1.8.

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5. The minimum operating shift crew requirements included in the current TS 6.1.1.3 are now under the new proposed TS 6.1.1.6. The order of the current TSs 6.1.1.5, 6.1.1.6, and 6.1.1.7 is changed to 6.1.1.7, 6.1.1.8, and 6.1.1.9, respectively, for proper sequencing due to the addition of new specifications. The text of these specifications remain unchanged.

The change of title from General Manager, Nuclear Stations to Vice President, Nuclear Operations is an administrative change and is acceptable. The NRC staff has reviewed each specific change proposed by the licensee and finds them 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 Contributors: F. Rinaldi, PDII-3 L. Wiens, PDII-3 Date:

August 30, 1991

DATED:August 30, 1991 DATED:

AMENDMENT NO. 190 TO FACILITY OPERATING LICENSE DPR Oconee Nuclear Station, Unit 1 AMENDMENT NO. 190 TO FACILITY OPERATING LICENSE DPR Oconee Nuclear Station, Unit 2 AMENDMENT NO. 137 TO FACILITY OPERATING LICENSE DPR Oconee Nuclear Station, Unit 3 DISTRIBUTION:

Docket File NRC PDR Local PDR PD 11-3 R/F Oconee R/F S. Varga 14-E-4 G. Lainas 14-H-3 D. Matthews 14-H-25 L. Berry 14-H-25 L. Wiens 14-H-25 F. Rinaldi 14-H-25 OGC-WF 15-B-18 D. Hagan MNBB 4702 G. Hill (12)

P1-37 W. Jones MNBB 7103 J. Calvo 11-F-22 ACRS (10)

P-135 GPA/PA 17-F-2 OC/LFMB MNBB 4702