ML20137H664

Amend 94 to License DPR-40,revising Reactor Vessel Matls Surveillance Capsule Removal Schedule

ML20137H664
Person / Time
Site:	Fort Calhoun
Issue date:	01/10/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137H655	List: ML20137H649 ML20137H664 ML20137H697
References
TAC-59219, NUDOCS 8601210601
Download: ML20137H664 (4)

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/ \, UNITED STATES  !

[ g NUCLEAR REGULATORY COMMISSION L 8 wAsHWGTON, D. C. 20656 y.....j I OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-40 4

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

A. The application for amendment by the Omaha Public Power District (the licensee) dated July 11, 1985, 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 j in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the

,i Comission; C. There is reasonable assurance (1) that the activities authorized j by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be j conducted in compliance with the Comission'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 i

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, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contaired in Appendix A, as revised through Amendment No. 94 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective within 30 days of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMISSION

/h$ W' Ash C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: January 10, 1986

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ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-40

$ DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

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TABLE 3-6 REACTOR COOLANT PUMP SURVEILLANCE REQUIREMENT METHOD FREQUENCY 1.1 Reactor Coolant Visual inspection of upper When motor is dis-Pump Flywheels surface of top disc and assembled for bottom surface of bottom maintenance disc; volumetric inspection purposes, from circumference of all disc segments.

TABLE 3-7 CAPSULE REMOVAL SCHEDULE REMOVAL REFUELING SCHEDULE CAPSULE SEQUENCE EFPY** REMOVED j-1 2.4 225*

2 5.9 265' .

3 15 275' 4 20 45' 5 21 85' 6 27 95*

7 32 225**

8 Standby 265'*

• Replacement capsule assemblies were installed in the 225' and 265*

locations following early removal of the 265* capsule. These cap-sules benchmark the change in core loading design initiated at 5.9 EFPY. ,

• • Based on a rated power level of 1500 MWt.

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Amendment No. $$, /W, 94 3-27