ML20084R817
| ML20084R817 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/30/1995 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084R819 | List: |
| References | |
| NUDOCS 9506090422 | |
| Download: ML20084R817 (5) | |
Text
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ki UNITED STATES NUCLEAR REGULATORY COMMISSION
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated March 24, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized 1
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 87, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NVCLEAR REGULATORY COMMISSION James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 30, 1995
ATTACHMENT TO LICENSE AMENOMENT NO. 87 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains marginal lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 3/4 5-2 3/4 5-2 l
l 3/4. 5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator shall be OPERABLE with:
The isolation valve open and power removed, a.
b.
A contained borated water volume of between 6122 and 6594 gallons, A boron concentration of between 2300 and 2500 ppa, and c.
d.
A nitrogen cover pressure of between 585 and 665 psig.
APPLICABILITY: MODES 1, 2, and 3*.
ACTION:
With one accumulator inoperable, except as a result of a closed a.
isolation valve, restore the inoperable accumulator to OPERABLE status within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HDT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
a.
1)
Verifying, by the absence of alarms the contained borated water volume and nitrogen cover pres,sure in the tanks, and 2)
Verifying that each accumulator. isolation valve is apan.
" Pressurizer pressure above 1000 psig.
WOLF CREEK - UNIT 1 3/4 5-1 Amendment No. ZZ,23
.i EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 70 gallons by verifying the boron concentration of the accumulator solution.
This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that its boron concentration is within limits of Specification 3.5.5.
At least once per 31 days when the RCS pressure is above 1000 psig c.
by verifying that the circuit breaker supplying power to the isolation valve operator is open.
4.5.1.2 Each accumulator water level and pressure channel shall be demonstrated OPERABLE at least once per 18 months by the performance of a CHANNEL CALIBRATION.
WOLF CREEK - UNIT 1 3/4 5-2 Amendment No. 87