ML20216F923

Safety Evaluation Supporting Amend 216 to License DPR-50

ML20216F923
Person / Time
Site:	Three Mile Island
Issue date:	09/22/1999
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216F920	List: ML20216F923
References
NUDOCS 9909270067
Download: ML20216F923 (3)

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.j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555-0001 o

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION j

RELATED TO AMENDMENT NO. 216TO FACILITY OPERATING LICENSE NO. DPR-50 l

METROPOLITAN EDISON COMPAN_Y JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR. INC.

THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 DOCKET NO. 50-289

1.0 INTRODUCTION

By letter dated October 19,1998, as supplemented August 19,1999, GPU Nuclear, Inc.

(licensee), submitted a request for changes to the Three Mile Island Nuclear Station, Unit 1 (TMI-1), technical specifications (TSs). The requested changes would add operability and surveillance requirements for a remote shutdown system which are similar to those in NUREG-1430, " Standard Technical Specifications - Babcock and Wilcox Plants," Section 3.3.18 entitled

" Remote Shutdown System." The staff requested additionalinformation from the licensee regarding this request by letter dated July 12,1999, to which the licensee responded by letter dated August 19,1999. The licensee's August 19,1999 response did not change the Nuclear Regulatory Commission (NRC) staff's proposed no significant hazards consideration determination and did not expand the scope of the application as noticed in the Federal Reaister. The staff's evaluation of the licensee's request is contained below.

2.0 EVALUATION The proposed revision to the TMI 1 TSs adds operability and surveillance requirements to the TSs for the remote shutdown system functions similar to those in NUREG 1430. The remote shutdown system meets the NRC Policy Statement as a risk significant item for retention in the TSs. The proposed TS Section 3.5.7, " Remote Shutdown System," incorporates the applicability requirements, limiting conditions for operation, operability requirements, required actions and completion times, and associated Bases. Proposed TS Section 4.1.4 incorporates the remote shutdown system surveillance requirements.

The staff has evaluated the proposed TSs against the standard TSs (STSs) for Babcock and Wilcox plants as defined in NUREG-1430 and has determined that the proposed TSs are consistent with the NUREG-1430 guidelines for a remote shutdown system. The staff has further compared the list of functions contained in proposed TS Table 3.5-4 with those in the

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Updated Final Safety Analysis Report (UFSAR) Table 7.4-1 for consistency. Minor differences 9909270067 990922

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2-between the licensee's proposed TSs and the STSs and differences between the functions in proposed TS Table 3.5-4 and UFSAR Table 7.4-1 are explained in the licensee's August 19, 1999, letter. The staff has determined that the functions in proposed TS Table 3.5-4 are consistent with those required for safe shutdown of the TMI-1 facility as described in UFSAR Table 7.4-1 and also with those contained in NUREG-1430, Table 3.3.18-1. The staff has further determined that the operability and surveillance requirements contained in the proposed TS are consistent with those in NUREG-1430, Section 3.3.18. Based on the information above, the staff has determined that the proposed TSs will provide adequate operability and surveillance requirements for the remote shutdown system and, therefore, the staff finds the licensee's proposed TSs acceptable.

3.0 STATE CONSULTATION

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

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 64118). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) 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 Contributor: Timothy G. Colburn Date: September 22, 1999 m

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DATED: September 22, 1999 AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. DPR-50 THREE MILE ISLAND DISTRIBUTION:

Docket File -

PUBLIC PDIRF J. Zwolinski/S. Black E. Adensam (E-mail)

S. Bajwa T. Colburn M. O'Brien L. Berry OGC G. Hill, IRM (2)

W. Beckner S. West ACRS R. Scholl (E-mail SE)

M. Oprendek, RI l

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