ML20087J283

Safety Evaluation Supporting Amend 180 to License DPR-16

ML20087J283
Person / Time
Site:	Oyster Creek
Issue date:	05/01/1995
From:	Office of Nuclear Reactor Regulation
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ML20087J277	List: ML20087J274 ML20087J283
References
NUDOCS 9505080177
Download: ML20087J283 (2)

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.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219

1.0 INTRODUCTION

By letter dated February 28, 1995, the GPU Nuclear Corporation (the licensee)n-submitter a request for changes to the Oyster Creek Nuclear Generating Statio (OCNGS) itchnical Specifications (TSs). The requested changes would revise TS Section 6.5.1.12 to delete the requirement to render determinations in writing with regard to whether or not activities listed in TS Sections 6.5.1.2 and 6.5.1.5 constitute an unreviewed safety question. These activities are proposed changes to Appendix A TS (6.5.1.2) and investigations of all violations of the TS (6.5.1.5).

This change is consistent with NUREG-1433 Standard Technical Specifications General Electric Plants, BWR/4 Revision 0, dated September 28, 1992.

2.0 EVALUATION The proposed TS change removes the requirement to render determinations in writing with regard to whether or not proposed changes to the TSs and investigations of violations of the TSs constitute an unreviewed safety question. Both of these activities involve submittals to the NRC.

Proposed changes to the TSs cannot be implemented until approved by the NRC.

Investigations of violations of TSs require a docketed response to the identified violation and are subject to NRC review and acceptance. Therefore, the requirement to determine whether or not either of these activities constitute an unreviewed safety question, in terms of 10 CFR 50.59 criteria, is not relevant to the activity. The existing OCNGS TS Section 6.5.1 and 6.5.2 requirements to perform Technical Reviews and Independent Safety Reviews of these activities are not affected by this change. Therefore, the level of assurance that these activities do not adversely affect nuclear safety or safe plant operations is maintained.

The proposed change is also consistent with the Revised Standard Technical Specifications (NUREG-1433) Administrative Controls for Review and Audit (STS 5.5.1.1.c).

9505080177 950501 DR ADOCK 050 29

.* Based on the above, the staff has concluded that the proposed change is acceptable.

3.0 STATE CONSULTATION

In accordance with the Comission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment.

By letter dated April 5,1995, Mr. Kent W. Tosch, of the State of New Jersey Department of Environmental Protection comented that they concur with GPU Nuclear's rationale that these unreviewed safety question reviews serve no value since these activities specifically require NRC review and approval. The State official had no other coments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets 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 amendment.

5.0 CONCLUSION

The Comission has s' ncluded, 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 Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributor.

A. Dromerick Date:

May 1, 1905

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