ML20094F989
| ML20094F989 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/25/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20094F983 | List: |
| References | |
| NUDOCS 9202280093 | |
| Download: ML20094F989 (3) | |
Text
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SAJETY EVALUATION BY THE OFFICE OF NVCLFAR REACTOR REGULATION RELATED TO AMENEENT NO.162 TO FAClllTY OPERATING llCENSE NO. DPR-66 DUOVESNE llGHT COMPANY 9H10 EDIS0N COMPANY PENNSYLVANIA POWER COMPANY BEAVER VALLEY POWER STATION. Ul{lT NO. 1 DOCKET NO. 50-334
1.0 INTRODUCTION
By letter dated February 28, 1991, the Duquesne Light Company (DLC) submitted a request for changes to the Beaver Valley Power Station, Unit No.-l Technical Specifications (TS). The requested changes would rev4se the Appendix A Technical Specification Surveillance Requirement 4.7.1.5 by deleting the requirement for periodic part-stroke testing of each main steam isolation valve (MSIV) and by deleting reference to specific testing requirements.
The surveillance req.uirement would be replaced by the requirement to verify the full closure of each MSIV within 5 seconds when tested in accordance with the requirements of Specification 4.0.5 (which references Section Al of the ASME Code). The modified surveillance requirement would be in accordance with the Standard Technical Specifications for Westinghouse pressurized water reactors.
i 2.0 EVALUATION Surveillance Requirement 4.7.1.5 currently requires that each MSIV be demonstrated operable by (1) part-stroke exercising the valves at least once per 92 days, and (2) verifying full closure within 5 seconds on any closure actuation signal while in hot standby with T(avg) greater than or equal to 515 degrees during each reactor shutdown (need not be determined more often than once per 92 days). The proposed change to Surveillance Requirement 4.7.1.5 would demonstrate that each MSIV is operable by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
Specification 4.0.5 requires testing applicable components in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.
The ASME Code,Section XI, Article IWV-3412(a) states:
" Valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during 9202280093 920225 PDR ADOCK 05000334 p
I
, plant operation and full-stroke exercised during cold shutdowns.
Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns.
Full-stroke exercising during cold shutdowns for all s alves not full-stroke exercised during plant operation shall be on a frequency determined by the intervals between shutdowns as follows: for intervals of 3 months or longer, exercise during each shutdown; for intervals of less than 3 months, full-stroke exercise is not required anless 3 months have passed since last shutdown exercise."
Past reactor trip history at Beaver Valley Unit l' Indicates that there have been several plant shutdowns caused by the inadvertant closing of the MSIVs during-partial-stroke testing. Therefore, in order to eliminate unnecessary plant shutdowns, DLC has proposed that-the testing be done in accordance with Specification 4.0.5.
This deletes the requirement to part-stroke test the MSIVs during plant operation if it leads-to unnecessary plant trips.
The MSIVs will continue to be operated in the same manner and the revised surveillance requirements provide consistency with the 1983 edition of ASME Section XI. This will eliminate the need for future Technical Specification changes to reflect changes to ASME Section XI.
The proposed change to Surveillance Requirement 4.7.1.5 would also make it consistent with the Westinghouse Standard Technical Specifications, which require testing to be conducted in accordance with Specification 4.0.5.
The NRC staff has concluded, based on the above discussion, that the proposed change to the surveillance requirements is acceptable and will not affect the operation or function of the plant.
~
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 = ~1 ment changes a surveillance requirement. 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 an individual or cumulative 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 (56 FR 20034).
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: James Andersen Date:
February 25, 1992 e