ML20216G560

Safety Evaluation Supporting Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively

ML20216G560
Person / Time
Site:	Peach Bottom
Issue date:	09/04/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216G528	List: ML20216G523 ML20216G532 ML20216G560
References
NUDOCS 9709150227
Download: ML20216G560 (3)

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\* UNITED STATES NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 2006H001

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 220 AND 223 TO FAtiLITY OPERATING LICENSE NOS. DPR-44 and DPR-56 PECO ENERGY COMPANY P_@ilt SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT NOS. 2 AND 3 DOCKET NOS. 50-277 AND 50-278

1.0 INTRODUCTION

By letter dated May 9, 1997, as supplemented by letter dated July 14, 1997, PECO Energy Company (PEC0, the licensee) submitted a request for changes to the Peach Bottom Atomic Power Station (PBAPS), Unit Nos. 2 and 3, Technical Specifications (TSs). The requested changes would revise TS surveillance renuirement 3.6.1.3.16, which requires replacement of the inflatable T-ring

' seal for each 6-inch and 18-inch primary containment purge valve and each 18-inch primary containment exhaust valve every 48 months, to increase the replacement frequency to 96 months. The supplemental letter provided clarifying information that did not change the original no significant hazards consideration determination.

t 2.0 EVALUATION Surveillance Requirement 3.6.1.3.16 was incorporated into the PBAPS, Units 2 and 3 TSs in Amendment Nos. 144 and 146, dated May 8, 1989. The T-ring seal replacement frequency was changed to every second refueling outage in Amendment Nos. 179 and 182, dated August 2, 1993. The requirement was subsequently transferred to the Improved Technical Specifications as a deviation from NUREG-1433, " Standard Technical Specifications, General Electric Plants, BWR/4," dated September 1992, in Amendment Nos. 210 and 214, dated August 30, 1995.

The licensee stated that no significant wear or degradation of the old seals was identified during replacement at 48-month intervals, and that visual examination of seals by engineering and maintenance indicated no noticeable wear or loss or resilience. The licensee indicated that T-ring seal performance reviews since 1986 indicate that documented seal failures were not due to material condition, but were mainly a result of improper installation.

The licensee has reviewed the purge and exhaust valve performance history and the valve leakage test data and determined that the valves are relatively free of valve leakage problems. The results of the leakage test program were provided in a letter to the U.S. Nuclear Regulatory Commission, from G. A. Hunger, Jr., PECO, dated July 14, 1997.

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The licensee also indicated that the leakage test data for the torus to reactor building vacuum breaker isolation valves also supports the extension of the replacement frequency in Surveillance Requirement 3.6.1.3.16. The torus to reactor building vacuum breaker isolation valves are 20-inch air-operated butterfly valves of the same series and design as the primary containment purge and vent valves. These valvos use the same T-ring seat seal and have had no documented cases of valve leakage due to T-ring elastomer degradation.

The licensee is not proposing any change to the existing requirements contained in the TSs for the leak testing of the primary containment purge and vent valves per 10 CFR 50, Appendix J, which requires Type C tests to be

" performed during each reactor shutdown for refueling but in no case at intervals greater than 2 years."

The staff has reviewed the licensee's submittal, including the data provided in support of the revision of Surveillance Requirement 3.6.1.3.16, and finds the proposed change to be acceptable. Based upon the licensee's operational experience and the continuation of local leak rate testing of the primary containment purge and vent valves in accordance with 10 CFR Part 50,

' Appendix J, the staff finds that the revision of Surveillance Requirement 3.6.1.3.16 to require replacement of the purge and vent valve seat seals every 96 months instead of 48 months is acceptable.

3.0 STATE CONSULTATION

In accordance with the Comission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendments change a surveillance requirement. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (62 FR 35851). Accordingly, the amendments meet 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 amendments.

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 defense) andthe issuance security of the or to the amendments health and safety ofwill the not be inimical to the common public.

Principal Centributor: M. Hart Date: September 4, 199/

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