ML20155D313

Safety Evaluation Supporting Amend 100 to License DPR-54

ML20155D313
Person / Time
Site:	Rancho Seco
Issue date:	09/28/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20155D302	List: ML20155D300 ML20155D305 ML20155D313
References
NUDOCS 8810110216
Download: ML20155D313 (3)

Text

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UNITED 8TATES 8

NUCLEAR REGULATORY COMMISSION e

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,I w ash WO TON. D. C. 20H1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 100 TO FACILITY OPERATING 1

LICENSE NO. DPR-54 RANCHO SECO NUCLEAR GENERATING _ STATION DOCKET NO. 50-312 i

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1.0 INTRODUCTION

l By letters dated July 1 1988 and September 8, 1988, the Sacramento Municipal Utility District (SMUD) requested an amandment to the Technical Specifications (TS) appended to Facility Operating License No OpR-54 for the Rancho Seco Nuclear Generating Station.

The proposed amendment would change the TS by revising TS Section 6.0, Administrative Controls, to remove organizational charts as depicted by Figures 6.2-1 and 6.2-2.

General regulatory requirements related to the plant organization were I

added to the TS to ensure that organizational features important t0 safe plant operations are raintained.

Per the recorrrnendations contained in l

Generic Letter (GL) 88-06, organizational charts were transferred from the TS to the Updated Safety Analysis Report.

l 2.0 EVALUATION The ERC staff has evaluated the proposed changes ard has concluded that they are acceptable. The staff's evaluation is given below, i

1 A.

Removal of Licensee Organization Charts from the TS 4

The content required in the Administrative Controls Section of the l

TechnicalSpecificationsisspecifiedin10CFR50.0Sc(5).

That pro-vision requires that the technical specifications contain provisions relating to organization and management procedures, recordkeeping, review and audit, and reporting that a e necessary to assure operation l

of the facility.n a safe manner.

It does not specifically require inclusion of organizational charts in the technical specifications.

l In (GL) 88-06, "Rencval of Organizational Charts from Technical Speci-fication Administrative Control Requirerents", dated March 22, 1988, the NRC has provided guidance for the removal of organizational charts from the TS. GL 88-M concludes that the removal of organization charts from the technical specifications will provide greater flexibility for licensees to implement changes in both the onsite and offsite organiza-tional structure, q

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A review of the existing Rancho Seco Administrative Controls TS and the changes proposed by this amendment indicates that the reconnendations included in GL 88-06 are applicable to the Rancho Seco TS and that the changes proposed by the licensee follow the guidance contained in the Generic Letter.

As in the past, the NRC will continue to be informed of organizational changes and management personnel titles through other required controls.

For example,10 CFR Part 50.34(b)(6)(1) requires that the applicant's organizational structure be includsd in the USAR. As required by 10 CFR 50.71(e), the licensee submits annual revisions to the FSAR Update.

The removal of the organization charts represent no reduction in the current safety requirements, because the following conditions are included in the technical specifications by these amendments, per the reconnendations of GL 88-06:

(1) A raquirement that lines of authority, responsibility, and connunica tic.) shall be established and defined from the highest manactment levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, a: appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or equivalent fonns of documentation.

(2) Designation of an executive position that has corporate responsibility for overall plant nuclear safety and authority ts take such measures as may be needed to ensure acceptable performance of staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

(3) Designation of a management position in the ensite organization that is responsible for overall unit operation and has control over those onsite activities necessary for safe operation and maintenance of the plant.

(4) Designation of those positions in the onsite organization that require a senior reactor operator (SRO) or reactor operator license.

(5)

Provistuns of sufficient organizational freedom to be independent of operational pressures to those individuals who perform the functions of health physics, quality assurance, and training of operating staff.

As discussed above, because removal of licensee organization charts from the TS meets the requircinents of 10 CFR 50.36, and because these amendments meet the guidelines of GL 88-06, the NRC staff finds them acceptable.

3.0 CONTACT WITil STATE OFFICIAL The NRC staff has advised the Chief of the Radiological Health Branch, State Department of Health Service, State of California, of the proposed determination of no significant hazards consideration. No coments were received.

4.0 ENVIRONMENTALCON30SION These amendments involve changes in administrative procedures and require-categorical exclusion set forth in 10 CFR Si.22(c)gibility criteria for ments.

Accordingly, these amendments meet the eli (10).

Pursuant to 10 CFR51.22(b),noenvironmentalimpactstatmentorenvironmentalassessment need be prepared in connection with the issuance of these amendments.

5.0 CONCLUSION

Wehaveconcluded,basedontheconsiderationsdiscussedabove,that(1) there is reasonable assurance that the health and safety of the p(ublic2)such will not be endangered by operation in the proposed manner, ion's regulations, and activities will be conducted in compliance witn the Comiss and (3) the issuance of the amendment will not be inimical to comon defense and security or to the health and safety of the public.

Principal Contributor: Gcorge Kalman Dated: September 28, 1988

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