ML17319A457

Notifies That Fourth Refueling Outage Initiated on 800530. Startup Date for Cycle 5 Operation Scheduled for 800731

ML17319A457
Person / Time
Site:	Cook
Issue date:	06/18/1980
From:	Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:00426, AEP:NRC:426, NUDOCS 8006240491
Download: ML17319A457 (5)

Text

REGUI ATORY ORMATION DISTRIBUTION SY =M (RIDS)

ACCESSION NBR:8006240491 DOC ~ DATE: 80/06/18 NOTARIZED; NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plantr Unit ir Indiana 8 05000315 AUTH, NAME AUTHOR AFFILIATION DOLANrJ.ED Indiana 8 Michigan Electric Co ~

RECIP.NAME'ECIPIFNT AFFILIATION DENTONgH,RE Office of Nuclear Reactor'Regulation SUBJECT; Notifies that fourth refueling outage initiated on 800530 startup date for Cycle 5 operation scheduled for 800731 CODE: .A001S COP IE'S RECEI YED: LTR JENCL Q SIZE o~ 'ISTRIBUTION TITLE! Gener al Distribution for af ter Issuance of Operating Lic-

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COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTIONS BC V~g g 05 7 7 INTERNAL: A/D CORE 8 C 821, A/D REACT SYS18 1 CHEM ENG BR 17 EMERG PREP 16 HANAUERrS ~ 20 I8E 12 2 MOOREpV ~ 22 NRC PDR 02 1 OELD 14 OR A S BR 19 1 QA BR 15 G L 01 EXTERNAL: ACRS 20 16 1 03 .1 NSIC 04 1 FAUN 25 ]ging 0

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INDIANA L MICHIGAN ELECTRIC COMPANY P. 0. BOX 18 BOWLING 'GREEN STATION N E W Y 0 R K, N. Y. 10004 June 18, 1980 AEP:NRC:00426 Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 License No. DPR-58 Refueling Outage Plans Mr. Harold R. Denton Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This is to advise you that Unit No. 1 of the Donald C. Cook Nuclear Plant has,been-brought to an orderly shutdown on May 30, 1980 for its fourth refueling outage. This outage is expected to last 60 days. The startup date for Cycle 5 operation is presently scheduled for July 31, 1980.

During this refueling outage 63 fuel assemblies manufacture'd by Exxon Nuclear Corporation (ENC) and 2 fuel assemblies manufactured by Westinghouse Electric Corporation will be removed and replaced with 65 fresh ENC fuel assemblies enriched to 2.9 w/o of U-235. The Cycle S core will be operated with ENC fuel assemblies. The mechanical and thermal hydraulic designs of"the reload fuel are identical to those f'r the fuel from the previous reloads.

The fuel perfot'mat1ce and safety anqlysi;s methods and procedures pre the same as those used for the. previous reloads. The results of these, analysis remain unaltered for Cycle S core inasmuch as the Plant Safety is concerned. r

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Nr. Harold R. Denton AEP:NRC:00426 Activities other than refueling include installation of new Steam Generator Feedwater elbows with thermal sleeves, water addition to the ice baskets and completion of the installation of a Unit-specific auxiliary feedwater system.

The AEP Service Corporation Nuclear Safety Design Review Committee (offsite review committee) and the Plant Nuclear Safety Review Committee have reviewed the reload design and the other activities associated with the refueling outage and concluded that these activities neither con-stitute unreviewed safety questions as defined in 10 CFR 50.59c nor would compromise the health and safety of the general public.

Very truly yours, ohn E. Dolan Vice President cc: R. C. Callen G. Charnoff R. S. Hunter R. W. Jurgensen D. V. Shaller - Bridgman