ML20206N075
| ML20206N075 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/17/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206N064 | List: |
| References | |
| GL-83-28, TAC-53186, TAC-53187, NUDOCS 8607010367 | |
| Download: ML20206N075 (3) | |
Text
-
'a nu
[o UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
D j
WASHINGTON, D. C. 20555
\\*...+/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 100 AND 103 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-266 AND 50-301 INTRODUCTION Generic Letter 83-28 was issued by NRC on July 8, 1983, indicating actions to I,
be taken by licensees based on the generic implication of the Salem ATWS events.
Item 4.3 of the generic letter requires that modifications be made to improve the reliability of the reactor trip system by implementation of an automatic actuation of the shunt attachment on the reactor trip breakers.
By letter dated June 1, 1984, Wisconsin Electric Power Company (licensee) responded to Generic Letter 83-28.
The staff issued a safety evaluation (SE) on September 26, 1984 indicating the acceptable and unacceptable aspects of the design and requested the licensee to resubmit it for staff's approval.
By letters dated February 28, and August 8, 1985, the licensee resubmitted the proposed design for the incorporation of the automatic actuation of the shunt trip attachments for the reactor trip breakers, and also requested Technical Specification (TS) changes which would add new surveillance requirements for the reactor trip breakers.
The shunt trip modifications including the main control board bypass breaker position indication for Unit I were completed during the Spring 1985 outage.
The shunt trip modifications for Unit 2 were completed during the Fall 1984 outage.
EVALUATION The licensee proposed a revision to the TS surveillance requirements of fable 15.4.1-2, page 3 of 3 which was responsive to the surveillance parameters noted in the staff's safety evaluation of September 26, 1984. The staff has found that the proposed TS address independent testing of the undervoltage and shunt trip attachments during power operation for reactor trip breakers and independent testing of the control room manual switch contacts during each refueling outage.
Further, the proposed technical specifications address testing to verify the operability of the undervoltage trip function of the bypass breakers prior to use for surveillance tests for reactor trip breakers and testing to verify operability of the shunt trip function of 860'010367 86061' PDR ADOCK 05000E66 PDR
, l the bypass breakers during each refueling outage. The proposed c'hange to the TS addresses itens 10 and 13 of the September 26, 1984 SE and are in accordance with the guidelines provided in NRC Generic Letter 85-09 of May 23, 1985, and are, therefore, acceptable.
The staff has also reviewed the licensee's proposed Technical Specification changes of:
(1) adding a reference to maintenance of sampling and analysis equipment as part of their Post-Accident Sampling Program; and (2) correction of two typographical errors.
The staff has determined that these changes are purely administrative in nature and acceptable.
ENVIRONMENTAL CONSIDERATION These amendments involve a change in the 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 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 published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
These amendments also involve changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, the amendments meet 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 environ.mantal assessment need be prepared in connection with the issuance of these amendments.
CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
T. Colburn N. Trehan Date:
June 17, 1986.
+
Distrbution Coates:__
~
,techetFiles.9kN6/301.ZTl NRC PDR Local PDR
-PAD #1 r/f PAD #1 p/f TNovak, Actg Div Dir Glear TColburn PShuttleworth NTHompson, DHFT ELD LHarmon EJordan BGrimes JPartlow TBarnhart(4)
WJones EButcher F0B Tech Branch that had input in package ACRS(10)
OPA LFMB