ML20128K198

Safety Evaluation Supporting Amend 50 to License DPR-73

ML20128K198
Person / Time
Site:	Three Mile Island
Issue date:	10/08/1996
From:	NRC (Affiliation Not Assigned)
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Shared Package
ML20128K178	List: ML20128K174 ML20128K183 ML20128K198
References
NUDOCS 9610100299
Download: ML20128K198 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 50 TO POSSESSION-ONLY LICENSE NO. DPR-73 GPU NUCLEAR. INC.

THREE MILE ISLAND NUCLEAR STATION. UNIT N0. 2 DOCKET N0. 50-320

1.0 INTRODUCTION

By letter dated January 16, 1995, GPU Nuclear, Inc. then known as GPU Nuclear Corporation, (GPUN, or licensee) submitted a request for changes to the Technical Specifications (TS) for Three Mile Island Nuclear Station,  !

Unit No. 2. The proposed changes would delete the requirement for certain unreviewed safety question (USQ) determinations in the licensee's internal review and approval matrix. The proposed change is consistent with the Standard Technical Specifications for Babcock and Wilcox Plants (NUREG 1430).

2.0 EVALUATION The proposed amendment would revise Section 6.5.1.7 of the administrative controls section of the technical specifications (TS). The change would delete the requirement for personnel in the licensee's internal review and .

approval matrix to render an USQ determination regarding 1) proposed changes I to unit technical specifications and 2) investigations of violations of ,

technical specifications. Technical specification changes involve docketed  !

correspondence in which an USQ determination is made and justified to the NRC staff. Any unreviewed safety questions would be reviewed, analyzed, and resolved by the staff during the review process. Violations of technical specifications and the licensee's analysis and corrective actions are also documented in docketed correspondence with the NRC staff and receive NRC staff review. This obviates the need for internal documentation of the licensee's reviews.

The proposed change is consistent with the Standard Technical Specifications for Babcock and Wilcox Plants and, based on the above, is acceptable to the NRC staff.

3.0 STATE CONSULTATION

In accordance with the regulations of the Commission, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.

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4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes administrative requirements only. The Commission has

previously issued a proposed finding that the amendment involves no i significant hazards consideration, and there has been no public comment on l such finding (60 FR 65679). 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 i 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 regulations of the Commission, and (3) the issuance of the amendment will not be inimical to the common defense and security er to the health and safety of the public.

t Principal Contributor: Lee H. Thonus Date: October 8, 1996

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