ML20133D341

Amend 155 to License DPR-72,consisting of Changes to TS in Response to 960923 Application to Delete Note for SR 3.3.7.1 for Engineered Safeguard Actuation Sys Logic

ML20133D341
Person / Time
Site:	Crystal River
Issue date:	01/06/1997
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML20133D338	List: ML20133D335 ML20133D341 ML20133D347
References
NUDOCS 9701090148
Download: ML20133D341 (5)

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@ %q g t UNITED STATES g ,j

't NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001

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FLORIDA POWER CORPORATION CITY OF ALACHVA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIPMEE CITY OF LEESBURG CITY OF NEW SNYRNA BEACH AND UTILITIES COMMISSION. CITY c NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMIN0LE ELECTRIC COOPERATIVE. INC.

CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.155 License No. DPR-72

1. The Nuclear Regulatory Commiss% (the Commission) has found that:

A. The application for amendment by Florida Power Corporation, et al.

(the licensees) dated September 23, 1996, 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 confc mity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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 af this amendment is in accordance with 10 CFR Part 51 l of the Commission's regulations and all applicable requirements have l been satisfied.

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l 9701090148 970106 PDR ADOCK 05000302 P PDR l

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-72 is hereby amended to read as follows:

Technical Soe'ications Tne Technical Specifications contained in Appendices A and B, as revised through Amendment No.155 , are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION 9Alg.WA Frederick J. Heb on, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications Date of Issuance: January 6,1997 l

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ATTACHMENT TO LICENSE AMENDMENT NO.155 l

l FACILITY OPERATING LIrENSE NO. DPR-72 DOCKET NO. 50-302 l Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and l contain vertical lines indicating the area of change. The corresponding

! overleaf pages are also provided to maintain document completeness.

Remove -

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3.3-19 3.3-19 B 3.3-63 B 3.3-63 l

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ESAS Automatic Actuation Logic )

3.3.7 i

SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY  !

l SR 3.3.7.1 Perform automatic actuation logic CHANNEL 31 days on a FUNCTIONAL TEST. STAGGERED TEST BASIS l

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Crystal River Unit 3 3.3-19 Amendment No.155 J

ESAS Automatic Actuation Logic l B 3.3.7  !

BASES ACTIONS A.1 and A.2 (continued)

With one or more automatic actuation logic matrices inoperable, the associated component (s) should be placed in the ES configuration. This manual Action essentially fulfills the i safety function of the automatic actuation logic. In some l circumstances, placing the component in its ES configuration would impose an undue operational restriction. In these cases, Required Action A.2 allows for the component status be left as-is, and the supported system component declared inoperable.

Conditions which would potentially preclude placing of a l component in its ES configuration include, but are not limited to, violation of system separation, activation of fluid systems that could lead to thermal shock, or isolation of fluid systems that are normally functioning. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on operating experience and reflects the urgency associated with the inoperability of a safety system component.

SURVEILLANCE SR 3.3.7.1 REQUIREMENTS SR 3.3.7.1 is the performance of a CHANNEL FlMCTIONAL TEST on a 31 day STAGGERED TEST BASIS. The CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic need only demonstrate one combination of the three two-out-of-three logic combinations that are required to be OPERABLE. A different combination is tested at euch test interval, such that all three conibinations will be confirmed to be OPERABLE by the time the third successive test is completed. The Frequency is based on operating experience that demonstrates the low likelihood of more than one channel failing within the same 31 day interval.

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(continued)

Crystal River Unit 3 8 3.3-63 Amendment No.155 J