ML20078D704

Safety Evaluation Supporting Amend 202 to License DPR-49

ML20078D704
Person / Time
Site:	Duane Arnold
Issue date:	11/02/1994
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078D701	List: ML20078D698 ML20078D704
References
NUDOCS 9411070345
Download: ML20078D704 (2)

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WASHINGTON, D.C. 20555-0001 SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGVLATION HELATED TO AMENDMENT N0. 20'2 TO FACillTY OPERATING LICENSE NO. DPR-49 IES UTILITIES INC.

CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DUANE ARNOLD ENERGY CENTER DOCKET N0. 50-331

1.0 INTRODUCTION

By application dated June 30, 1994, IES Vtilities Inc., requested changes to the Duane Arnold Energy Center (DAEC) Technical 3pecifications (TS).

The requested change is to modify Technical Specifications 6.5.2.8 which discusses audits of facility activities that are under the cognizance of the Safety Committee. The proposed change would remove the requirement for Safety Committee involvement in audits for the emergency and security plans from the TS that duplicate the provisions in Parts 50 and 73 of Title 10 of the Code of federal Regulations (10 CFR). The NRC issued guidance to all holders of operating licenses for nuclear power reactors on the proposed change by Generic Letter (GL) 93-07, " Modification of Technical Specification Administrative Control Requirements for Emergency and Security Plans" dated December 28, 1993.

The requested changes to the DAEC Technical Specifications also clarify tne Safety Committee Audit requirements and add a provision for the plant Superintendent-Nuclear designation of signature authority for approval of plant procedures.

2.0 EVALVATION The licensee proposed modifying TS 6.5.2.8 by removing items e. and f., which reference the emergency and security plans, respectively, and their implementing procedures under the audit responsibilities of the Safety Committee, which are to be performed at least once every 12 months.

This proposed TS change eliminates TS provisions that duplicate the requirements in 10 CFR Parts 50 and 73 and is consistent with the NRC guidance set forth in GL 93-07. The staff has concluded that relocation of audit responsibilities of the Safety Committee is acceptable because (1) their inclusion in Technical Specifications is not specifically required by 10 CFR 50.36 or other regulations, (2) the audit responsibilities of the Safety Committee are not required to avert an immediate threat to the public health and safety, and (3) changes that are deemed to involve a decrease in effectiveness of security or emergency plans will require prior NRC approval, in accordance with 10 CFR 50.54.

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The licensee also proposed changes in TS 6.8.2 and 6.8.3 to allow the Plant I

Superintendent-Nuclear to designate signatory authority for procedure approval.

The proposed allowance for designation of authority for procedural approval will relieve the Plant Superintendent-Nuclear of the burden of approving all plant procedural changes.

In addition, the licensee proposed changes to paragraph 6.5.2.8.a, b, c, and d, to clarify these requirements and make them consistent with Regulatory Guide 1.33.

The proposed change to capitalize the term OPERATING CYCLE in paragraph 6.8.1.11 is editorial, and is consistent with the BWR/4 Draft Improved Technical Specification, NUREG-1433.

Therefore, the staff finds that these proposed TS changes for DAEC are acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Iowa State official was notified of the proposed issuance of the amendment. The State official had no I

comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment relates to changes in recordkeeping, reporting, or administra-tive procedures or requirements. Accordingly, the amendment meets the elig-ibility 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 amendment.

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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: Thomas G. Dunning Joseph M. Sebrosky Date: November 2, 1994 1

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