ML17320B057

Amend 62 to License DPR-74,allowing 30 Fuel Assemblies to Be Discharged from Reactor Vessel W/Only One Source Range Flux Monitor Assemble Operable

ML17320B057
Person / Time
Site:	Cook
Issue date:	04/25/1984
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17320B058	List: ML17320B057
References
NUDOCS 8405210079
Download: ML17320B057 (9)

Text

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Op 00 pN 4***4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 l

INDIANA AND NICIIIGAN EI.ECTRIC COtiPANY DOCKET NIO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AIAENDMENT TO FACILITY OPERATING LICENSE Amendment No,62 License No.

DPR-74 1.

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

A.

The application for amendment by Indiana and h1ichigan Electric Company (the licensee) dated April 24, 1984, 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; C.

The facility will operate in conformi ty with the application, the provisions of the Act, and the rules and regulations of the Commission; 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'e, 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 IO CFR Part 51 of the Commission's regulations and all applicable requi rements 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-74 is hereby amended to read as follows:

8405210079'40425, PDR ADOCK 05000316

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(2)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.

62, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COINISSION

Attachment:

Changes to the Technical Specifications Opera t~ ng Reactors~ Branch //I Division of Licensing Date of Issuance:

April 25, 1984

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO, DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:

Remove Pa es 3/4 9-2 Insert Pa es 3/4 9-1*

3/4 9-2

• Included for convenience only.

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3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concen-tration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a.

Either a' of 0.95 or less, which includes a

1% ak/k conserv-ative allowance for uncertainties, or

'0 b.

A boron concentration of

> 2000 ppm, which includes a

50 ppm conservative allowance for uncertainties.

APPLICABILITY:

MODE 6.*

ACTION:

With the, requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERS'TIONS or positive reactivity changes and initiate and continue boration at 10 gpm of 20,000 ppm boric acid solution,dr its equivalent until K

iq reduced to

< 0.95 or the boron'oncentration is restored to

> 201$..ppm, whichever 7s the more restrictive.

= The provisions of Specification 3.9.3 are not applicable.

r<

SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel

head, and b.

Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.

D.

C.

COOK - UNIT 2 3/4 9-1

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