ML20057A353

Amend 163 to License DPR-61,adding Footnote to TS 3.4.2.2 to Allow Relaxation in Pressurizer Safety Valve Point Tolerance to +3%,used for as Found Acceptance Criterion for Addl Valve Testing

ML20057A353
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/02/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20057A352	List: ML20057A351 ML20057A353 ML20057A355
References
NUDOCS 9309140062
Download: ML20057A353 (4)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT t

AMENDMENT TO FACILITY OPERATING LICENSE s

Amendment No. 163 License No. DPR-61 l

1.

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

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated March 18, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as i

amended (the Act), and the Commission's rules and regulations set l

forth in 10 CFR Chapter I; i

B.

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

There is reasonable assurance (1) 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 i

conducted in compliance with the Commission's regulations;

)

D.

The issuance of this amendment will not be inimical to the common 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.

93KP9140<hs2 930902 PDR ADOCK 05000213-P PDR

2 i 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. DPR-61 is hereby amended to read as follows:

1 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.163, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the l

Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

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FOR THE NUCl. EAR REGULATORY COMMISSION of Y

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John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

j Changes to the Technical l

Specifications Date of Issuance:

September 2, 1993 O

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ATTACHMENT TO LICENSE AMENDMENT NO. 163 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following page of the Appendix A Technical Specifications with the enclosed pag =.

The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

Remove Insert 3/4 4-17 3/4 4-17 l

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REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION l

3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with respective l!ft settings of 2485 psig 1%, 2535 psig 1% and 2585 psig 1%

i in accordance with their respective nameplates.*+

l APPLICABILITY: MODES 1, 2, and 3.

ACTION:

l With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.4.2.2 In addition to the requirements of Specification 4.0.5, each pressurizer Code safety valve shall be demonstrated OPERABLE by checking its setpoint each refueling.

i The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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1% applies when a safety valve is tested and set prior to installation

+

( as-l e f t). When a safety valve is removed and tested, the as-found setting may be within +3% and -l% of the setpoint.

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l gDDAMNECK 3/4 4-17 Amendment No. JJJ,163,

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