ML18219E010

D.C Cook Unit 1 - Letter Requesting That Operating License Be Amended to Permit Operation at Steady State Core Power Levels Not to Exceed 3250 Megawatts Thermal for Cycle 2

ML18219E010
Person / Time
Site:	Cook
Issue date:	07/20/1976
From:	Tillinghast J Indiana Michigan Power Co
To:	Rusche B Office of Nuclear Reactor Regulation
References
Download: ML18219E010 (15)

Text

U.S. NUCLEAR REGULATORY COMM'""ION NRC FORM 195

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MR B RUSCHE INDIANA & MICHIGAN PWR CO NEW YORK, NY JOHN TXLLINGHAST DATE OF DOCUMENT "l-ko - "t 4 DATE RECEIVED

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LTR REQUESTING THAT THE OPERATING LICENSE BE AMENDED TO PERIIIT OPERATION AT STEADY STATE CORE POWER LEVELS NOT IN EX-CESS OF 3250 MEGAWATTS........

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y 20) 1976 Donald C.

Cook Nuclear Plant Docket No.

$0-315 DPR No.

58 Mr. Benard Rusche, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Nashington, D.C.

20555

Dear Mr. Rusche:

In accordance with the requirements of 10 CFR $0.90, Indiana

& Michigan Electric Company and Indiana 8c Michigan Power Company (Licensees) hereby request that the operating license of the Donald C.

Cook Nuclear Plant Unit No. 1 (License No. DPR-g8) be amended to permit operation at steady state core power levels

'not in excess of 3250 megawatts thermal (100percent of rated thermal power) for Cycle 2.

This cycle will begin after the first refueling in which approximately sixty-five (6g) assemblies will be discharged from the core and replaced with fuel assemblies designed and manufactured by the Exxon Nuclear Company.

It is currently planned to terminate Unit 1, Cycle 1 operation about the end of the year for the purpose of reloading the core and. performing other maintenance and surveillance work.

Based on this, Qe would expect to return to criticality and commence Cycle 2 operation by February 1977.

The plant has operated since initial criticality on January 18, 1975 with 193 fuel assemblies designed.

and fabricated by tIItestinghouse Electric Corporation.

The Donald C.

Cook Nuclear Plant Unit No. 1 is currently operating under the provisions of License No.

DPR-5'8,,

as

amended, at steady state reactor core power levels not in excess of $250 megawatts thermal (100 percent of rated power).

The operation at 100 percent power level was authorized by Amendment No.

14 to Facility Operating License DPR-58 issued by"

the Commission on May 28, 19'76.

This authorization is effective

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July,20<,

1976 only until such time as the reactor is next refueled. at which time, unless the Commission has taken further licensing action with respect to the authorized power level, the authorized.

power level will be 2632.5 megawatts thermal (81 percent of rated power).

This restriction on maximum operating'power after the

'first cycle, until the Commission has taken further licensing

action, was made by the Nuclear Regulatory Commission in accordance with the advice of the Advisory Committee on Reactor Safeguards (henceforth referred to as "ACRS") in the March 11, 1976 letter from Dade W. Moeller, ACRS Chairman, to Honorable William A. Anders, Chairman of the U.S. Nuclear Regulatory Commission.

The ACRS expressed a desire to be kept informed with regard to the inventory of ice in the ice condenser, as measured by the quarterly sampling program which has continued.

Periodic results of the ice condenser basket weighing and surveillance program have been forwarded to the NRC.

A formal report of the results of the January and April 19/6 ice weighings will be submitted to the NRC by the end of July 1976.

Another ice weighing was conducted during a July 1976 outage and an analysis of the results will be submitted.

by October 4, 1976.

Since authorization to increase power levels above 81$ was received on March 30,4'1976, we have continued our operating philosophy of employing frequent in-core flux mapping to determine actual peaking factors at power levels above 81'p to and including 100/o operation.

The results continue,to be favorable.

Performance of the Axial Power Distribution Monitoring System in this period has yielded similar results'pecific information on maximum allowable nuclear peaking factor (F~) during Cycle 2 operation will be submitted as a part of this amendment request by October 18, 1976.

Licensees and. Exxon Nuclear Company are developing technical information concerning the reload core in conformance with the NRC Staff's proposed "Guidance for Proposed.

License Amendments Relating to Refueling" of June 1975.

The technical information includes a general description of the, reload core, detailed mechanical data on the reload fuel, specifics of the

July 20','976 nuclear design, specifics of the thermal hydraulic design, and the accident and transient analyses.

In support of this request for an amendment to License DPR-)8, Exxon Nuclear Company is transmitting directly to the NRC, under separate cover of a letter dated July 19, 1976, 40 copies of a report prepared by Exxon Nuclear Company (Report No. XN-76-25 "Donald C.

Cook Nuclear Plant Unit 1 Cycle 2 Reload Fuel Licensing Data Submittal.~<')-'.-'his report includes technical information on the Cycle 2 reload in the areas of mechanical

design, thermal hydraulic design, neutronics, operational summary of Cycle 1 as it pertains to the Cycle 2

reload and the startup testing program for Cycle 2.

The remainder of the technical information will be submitted to the Commission on the following approximate schedule:

Description of ECCS Model Update July 31, 1976 Results of January 8c April ice weights Safety and. Plant Transient Analysis including ECCS Example Problem July 31, 1976 August 20, 1976

Proposed, Technical Specification Changes (excluding ECCS-related)

September 15, 1976 Results of July, 1976 Ice Condenser Neighing October 4,i"1976 ECCS Analysis and Related Technical Specification Changes October 18, 1976 The ECCS analysis for Cycle 2 operation to demonstrate conformance to 10 CFR 50.46 and Appendix K will use the NREM computer model as modified. by Exxon Nuclear Company for application to the Donald. C.

Cook Nuclear Plant, Unit No. 1.

Ne specifically are requesting the following change to Facility Operating License No. DPR-)B, Section 2.C(1) to read:

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imum Po er Leve The licensees are authorized. to operate the Donald C.

Cook Nuclear Plant, Unit 1, at steady state reactor core power levels not to exceed 3250 megawatts thermal (100 percent of rated power)".

We would appreciate your review of this reload application to permit startup of Cycle 2 by February, 1977.

Very truly yours, JT +mam 0

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Vice Presiden Sworn an/, subscribe/ to before me

. this QO~ day of

~~~y 1976

,in New York County, New York Notary Public DAVIDG. HUME G ~ CharnOff NOTARY PUSf.lC. State of New York No. 314608113 R. J. Vollen Qualified in New York County C ~ Callen commission Expires March 30, 1977 P.

W. Steketee R. Walsh R. S. Hunter R.

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Docket No. 50-315

""~l 9 1976 Indiana 5 Michigan Electric Company Indiana 5 Michigan Power Company ATTN:

Mr. J. A. Tillinghast Vice President P. 0. Box 18 Bowling Green Station New York, New York 10004 Gentlemen:

RE:

DONALD C.

COOK NUCLEAR STATION UNIT NO.

1 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Mater-Cooled Power Reactors,"

was published Pebruary 14, 1973.

Since many nuclear plants had either received an operating license or their containments had reached advanced stages of design or construction at that time, some plants may not now be in full compliance with the requirements of this regulation.

You are~equested to determine if you are conducting containment leakage testing in full compliance with Appendix J.

This determination should include the identification of any design features that do not permit conformance with its requirements or existing technical specification requirements which are in conflict with Appendix J, {i.e.P less restrictive than). It should be understood that while a containment leakage testing program may be in compliance with the technical specifications for your facility, the program may not be in conformance with Appendix J.

I If you are not in full compliance, you should identify your planned actions and schedule to attain conformance to the Regulations.

Possible courses of action include design modifications, amendments to the technical specifications, and requests for exemption pursuant to 10 CPR Part 50, Section 50.12.

OPPICEW SVIINAMCW nATOW Form ARC-318 (ROT. 9.53) hECM 0240 4 U 0,'OVOIINMKNTPIIINTINO OPPIcm IOTA OOO IOO 4

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Indiana 5 Michigan Electxic Company Indiana 9 Michigan Power Company 2-JUL 19 1976 Please submit the results of your study to us as soon as possibly but no later than 30 days from xeceipt of this letter.

This request for generic information was approved by GAO under a blanket clearance number B-180225 (R0072); this clearance expires July 31, 1977.

Sincerely, OriglnQ. SiGne Dennis I, Ziema Enclosuxe:

Appendix J cc w/enclosure:

See next page Dennis L. Ziemann, Chief Operating Reactors Branch N2 Division of Operating Reactors DISTRIBUTION:

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& Mighican Electric Company Indiana 6 Michigan Power Company cc w/enclosure:

Fir. Robert Hunter Vice President American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff Shaw, Pittman, Potts 6

Trowbridge 1800 M Street, N.

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Washington, D.

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, 20036 Businessmen for the Public Interest Suite 1001 109 North Dearborn Street Chicago, Illinois 60604

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