ML19350E346

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Amend 70 to License DPR-49,reflecting Changes in Surveillance Requirements Associated W/River Water Supply Sys
ML19350E346
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 06/08/1981
From: Ippolito T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19350E347 List:
References
NUDOCS 8106170352
Download: ML19350E346 (4)


Text

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%o UNITED STATES g

h NUCLEAR REGULATORY COMMISSION g

,, j WASHINGTON, D. C. 20555 e

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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. OPR-49 1.

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

A.

The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power Cooperative (the licensee) dated May 24, as supplemented June 2,1981, 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, 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 of this amendment is in accordance with 10 CFR Part 51 of the Commission'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 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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2-3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

Thomas W. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 8,1981 e

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ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page -is identified by Amendment Number and contains a vertical line indicating the area of change.

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LIMITING CONDITIONS.FOR OPERATION h

SURVEILLANCE REQUIREMENT J.

River Water Suoply System -

J.

River Water Sucoly System 1.

Except as specified in 3.5.J.2 1.

River Water Supply System Testing:

below, at least one pump in eacn river water supply system loop a.

Item Frequency shall be operable whenever irradiated IIEulated auto-Eacn refueling fuel is in the reactor vessel and matic actuation outage.

reactor coolant temperature is Test.

greater than 212"F.

b.

Pump and motor Once/3 months operated valve operability.

c.

Flow Rate Test Each river water After major pump supply system maintenance and purap shall deli-monthly.

ver at least 6000 gpm at TDH Daily when river of 46 f t. or more. elevation is less than 727 feet.

d.

Operating Pump Flow Rate Demonstration Each Opgrating Daily River Water.

Supply System Pump shall deli-ver at least 6000 gpm.

2.

From and after the date that one 2.

When one river water supply system river water supply system loop is loop becomas inoperable, the.

made or found to be inoperable for operable loop and the diesel-any reason, reactor operation must generators requ; red for operation De limited to seven days unless of such components shall be operability cif that subsystem is demonstrated to be operable restored within this period. During immediately and daily thereafter.

such seven days all active components of the other river water supply loop shall be oparable.

3.

If the requirements of 3.5.J.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment 70

.3.5-12

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