ML20059L192

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Amends 145 & 149 to Licenses DPR-24 & DPR-27,respectively, Splitting TS 15.3.1.E.2 Into Two Individual LCOs & Adding 24-hr Hot Shutdown Action Statement to Reactor Coolant Impurity Limit Lcos.Corresponding TS Bases Also Modified
ML20059L192
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/27/1994
From: Hansen A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059L195 List:
References
NUDOCS 9402030272
Download: ML20059L192 (7)


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NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D.C. 20666-0001 f

WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 License No. DPR-24 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 14, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the A.ct), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized 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 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-24 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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, 3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.

i FOR THE NUCLEAR REGULATORY COMMISSION k

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Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

January 27, 1994 i

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UNITED STATES O

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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 l

i POINT BEACH NUCLEAR PLANT. UNIT NO. 2 l

AMENDMENT TO~ FACILITY OPERATING LICENSE' l.

Amendment No.149 License No. DPR 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company-(the licensee) dated January 14, 1993, complies with-the standards and requirements of the Atomic Energy Act of 1954, as amended (the.

Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the -

Comission; C.

There is reasonable' assurance (i) that the activities authorized by this amendment can be conducted without endangering the' health and safety of the public, and (ii) that such activities will be-l conducted in compliance with the Comission's regulations;

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D.

The issuance 'of this amendment will' not be inimical. to the comon i

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 Comission'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 3.B of~ Facility Operating License No.

DPR-27 is hereby amended to read as follows:

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B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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3.

This. license amendment is effective inmediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.

FOR THE NUCLEAR REGULATORY CON 4ISSION fn Allen G..Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V f

Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications Date of issuance:

January 27, 1994 l

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.s ATTACHMENT TO LICENSE AMENDMENT NOS 145 AND 149 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 15.3.1-15 15.3.1-15 15.3.1-16 15.3.1-16 i

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E.

Maximum Reactor Coolant Oxvoen and Chloride and Fluoride Concentration For Power Operatiqn Specification:

1.

The concentration of oxygen in the reactor coolant shall not exceed 0.1 ppm.

2.

The concentration of chloride in the reactor coolant shall not exceed 0.15 ppm.

3.

The concentration of fluoride in the reactor coolant shall not exceed 0.15 ppm.

4.

If oxygen, chloride or fluoride concentrations in the reactor coolant exceed the limits given in 1), 2) or 3), corrective action is to be taken immediately to return the system to within normal operation specifications.

If the normal operational limits are not achieved within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of the out-of-specification condition, the reactor is to be brought to a hot shutdown condition within an additional 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

If the system is not brought to within specifica-tions within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of discovery, the system is to be brought to a cold shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and the cause of the out-of-specification operation ascertained and corrected.

Basis:

By maintaining the oxygen, chloride and fluoride concentration in the reactor coolant within the limits as specified by E 1), 2) and 3),'the functional integrity of the materials of the Reactor Coolant System is assured under all operating conditions.cu if these limits are exceeded, measures can be taken to correct the condition, e.g., replacement of ion exchange resin or adjustment of the hydrogen 15.3.1-15 Unit 1 - Amendment No. JJ0,145 Unit 2 - Amendment No. 113.149

w concentration in the volume control tank (2), and further because of the time-dependent nature of any adverse effects arising from oxygen, chloride and fluoride concentration in excess of the limits, it is unnecessary to shut down immediately since the condition can be corrected. Thus the period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for corrective action to restore the concentrations within the limits has been established.

If the corrective action has not been effective at the end of the 24-hour period, then the reactor will be brought to the hot shutdown condition in a normal controlled manner and the corrective action will continue.

If at the end of the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period the corrective action has not been effective, long term corrective action could be required.

The reactor will be brought to the cold shutdown condition in a normal, controlled manner and action continued to correct the out-of-specification condition.

References I"

FSAR Section 4.2 (2)

FSAR Section 9.2 15.3.1-16 Unit 1 - Amendment No.145 Unit 2 - Amendment No.149