ML20236L256
| ML20236L256 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/02/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236L237 | List: |
| References | |
| NUDOCS 8711100235 | |
| Download: ML20236L256 (2) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION -
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SAFETY EVALUATION BY'THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.11 TO FACILITY OPERATING LICENSE NO. NPF-C KANSAS GAS & ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COMPANY XANSAS ELECTRIC POWER COOPERATIVE, INC.
1 WOLF CREEK GENERATING STATION j
'0OCKET N0. 50-482 INTRODUCTION By letter dated June 19, 1987, the Wolf Creek Nuclear Operating Corporation, the licensee for the Wolf Creek Generating Station, requested a revision to Technical Specification 3.5-1 concerning plant operating mode when one accumulator is declared inoperable.
The proposed revision will' bring into consistency the technical specification limiting condition of operation and the corresponding ACTION statement.
In addition, the proposed revision is in agreement with the latest version of the Westinghouse Standard Technical Specifications.
EVALUATION The accumulators function as part of the Emergency, Core Cooling System. The main function is to provide emergency core cooling in the event of a loss of-coolant accident and to provide cooling water and boration'in the event of a
.l steam line break or a feedwater line break. All accumulators-feed into the cold legs.
Technical Specification 3.5-1 is applicable in modes.1, 2 and 3 and when (pressurizer) pressure is above 1,000 psig, i.e., when all accumulators are i
(The accumulator nitrogen cover-pressure in Wolf Creek is between 585and665psig.) Normal operation procedures require the control room operators to close the accumulator discharge valves whenever the RCS pressure is reduced below 1,000 psig.
The present Technical Specification 3.5-1 ACTION statements require the plant to be in hot standby (mode 3) within seven hours from the moment an accumulator i
has been declared inoperable
- and in hot shutdown (mode 4) within the following-6 hours. The proposed amendment would revise the ACTION statements.to require-the plant to be in mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and require a reduction of the RCS pressure to less than or equal to 1,000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
T' The present requirement conforms with Rev. 4 of NUREG-0452, Westinghouse Standard Technical Specifications.
.l 8711100235 871102 JPDR-ADOCK 05000402 1
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.. j The proposed requirement:
j (a) Avoids mode 4 which would impose thermal cycling on the RCS containment and reactor internals;
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(b) Conforms with the current version of the Westinghouse Standard Technical l
Specifications, NUREG-0452, Rev. 5; and (c) Does not affect the scope of the technical specification.
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Therefore, we find the proposed amendment for Technical Specification 3.5-1 l
acceptable.
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SUMMARY
We have reviewed the submitted information for the amendment of Technical i
l Specification 3.5-1 ACTION Statement.
We find that the proposed change (1)
I will bring the technical specification in agreement with the current version of the Westinghouse Standard Technical Specifications, (2) will avoid thera l l
cycling of the RCS containment, and (3) will keep the scope of the original specification. Therefore we conclude that the proposed amendment is l
acceptable.
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ENVIRONMENTAL CONSIDERATION The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or in a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in I
the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.
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.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 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.
CONCLUSION The staff 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, and (2) 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 l
and security or to the health and safety of the public.
Date: November 2,1987 Principal Contributor:
Lambrois Lois Paul O'Connor l
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