ML20203M615
| ML20203M615 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/22/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203M608 | List: |
| References | |
| TAC-60559, NUDOCS 8605010610 | |
| Download: ML20203M615 (2) | |
Text
g[%A UNITED STATES NUCLEAR REGULATORY COMMISSION y
,h WASHINGTON, D. C. 20555 e
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 1 TO OPERATING LICENSE NO. NPF-42 KANSAS GAS & ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE, INC.
WOLF CREEK GENERATING STATION DOCKET N0. 50-482 INTRODUCTION By letter dated January 20, 1986, the Kansas Gas & Electric Company (KG&E) pro-posed a license amendment to revise the Technical Specifications for Wolf Creek Generating Station, Unit 1, after 8000 MWD /MTU burnup in Cycle 1.
These changes would implement a Westinghouse developed Power Distribution Control methodology called Relaxed Axial Offset Control (RA0C).
EVALUATION Westinghouse reactors have for a number of years operated under a power distri-bution control system called Constant Axial Offset Control (CAOC), which ensures peaking factors will remain below values assumed as input for accident analyses during normal operation of the power plant. Basically CA0C achieves its result by requiring plant operation within a 5% flux difference (4 I) around a measured target value. By controlling the axial power distribution, the possible skew-ing of the axial xenon distribution is limited, thus minimizing xenon oscillations and their effects on the power distribution, i
Plants have varying degrees of margin to the peaking factor limits which can be supported by CAOC. Westinghouse developed RA0C to directly determine the allow-ed band of 4 I operation required to support any plant specific peaking factor limit. We approved RA0C for referencing in licensing actions in a letter to E. P. Rahe (W) from C. Thomas (NRC), " Acceptance for Referencing of Licensing Topical Report WCAP-10216(P)(NS-EPR-2649)," dated February 28, 1983.
The affected sections of the Technical Specifications are: 3/4.2.1, Figure i
3.2-1, Table 2.2-1, and Bases Section 3/4.2.1 and Figure B 3/4.2.1. The changes have all been made in accordance with those outlined in WCAP-10216PA.
The pro-cedure outlined in WCAP-10216PA was used for the analysis performed by Westinghouse for Cycle 1 of the Wolf Creek Generating Station Unit 1.
The analysis is applicable only after the unit reaches 8000 MWD /MTU burnup in Cycle 1 and thereafter until the end of Cycle 1.
Cycle specific evaluations are made 1
8605010610 860422 PDR ADOCK 05000482 p
, ]
by Westinghouse to determine if the allowableo I band curve remains valid or requires revision (by Technical Specification change).
We have reviewed the submittal for the RAOC technical specification change for Wolf Creek; the methcdology used has previously been reviewed and approved by the staff. The propo!ed technical specification changes are those outlined in the topical (WCAP-102L6PA). Therefore, the proposed technical specification changes are acceptable.
ENVIRONMENTAL CONSIDERAT M This amendment involves a change in the installation or use of facility compon-ent located within the restricted area as defined in 10 CFR Part 20.
The staff has detennined 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 Comission has previously is-sued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, this 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 this amendment.
CONCLUSION The Commission made a proposed detennination that the amendment involves no significant hazards consideration which was published in the Federal Register (51 FR9728) on March 20, 1986
, and consulted with the state of Kansas. No public comments were received, and the state of Kansas did not have any comments.
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 Commission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributors:
P. O'Connor, PWR#4 M. Chatterton, PARS Dated:
April 22, 1986