ML20247D936
| ML20247D936 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/23/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247D933 | List: |
| References | |
| NUDOCS 8903310256 | |
| Download: ML20247D936 (2) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION h
WAEMNGTON, D. C. 20505
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 52 70 :
FACILITY OPERATING LICENSE NO. NPF-38 LOUISIANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION, UNIT 3 D0CKET NO. 50-382
1.0 INTRODUCTION
By application dated December 23, 1988, Louisiana Power and Light Company LP8L or the licensee) requr<sted changes to the Technical Specifications Appendix A to Facility Operating License No. NPF-38) for Waterford Steam Electric Station, Unit 3.
The proposed changes would show a new location for one of the backup seismic monitors.
2.0. DISCUSSION The' backup seismic monitor (SM-IYR-6021) is located nearby the reactor coolant pump on the cold leg 2A. The monitor is a triaxial peak accelerograph (TPA) which, as a passive device, scratches information on coated metal plates. Repeated damage to the metal plates has resulted in the discovery of high system vibrations in the current location. Once damaged from these vibrations, the monitor is useless. To solve the problem.and still have the monitor available for recording seismic activity on the primary coolant system, the licensee proposes to relocate the monitor to a pipe less susceptible to vibration.
3.0 EVALUATION l
The new location of the monitor will provide the information required and without the likelihood of repeated damage. The new location at elevation L
23 feet versus 8 feet will also provide for easier accessibility for maintenance. We have reviewed the location and proposed Technical Specifications and find them acceptable. In installing the new monitor, i
we recommend that trained personnel handle the metal plates due to high incidence of inadvertent scratching during installation reported by the manufacturer of the instruments.
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4.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Administrator, Nuclear Energy Division, 3
Office of Environmental Affairs, State of Louisiana of the proposed J
determination of no significant hazards consideration. No comments were received.
5.0 ENVIRONMENTAL CONSIDERATION
l The amendment relates to changes in installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eli criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)gibility Pursuant to 10 CFR 51.22(b), no environmental impact statement or environ-mental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
Based upon its evaluation of the proposed changes to the Waterford 3 Technical Specifications, the staff has' concluded that: there is reason-able assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. The staff, therefore, cencludes that the proposed changes are acceptable, and are hereby incorporated into the Waterford 3 Technical Specifications.
Dated:
March 23, 1989 Principal Contributor:
G. Geise-Koch 1