ML17319B590
| ML17319B590 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/18/1982 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0745, AEP:NRC:745, NUDOCS 8210220393 | |
| Download: ML17319B590 (7) | |
Text
REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
AOCBSSION NBR:8210220393 DOC ~ DATE: 82/10/18 NOTARI'ZED:
NO DOCKET ¹ FAOIL:50 315 Donald C ~
Cook Nucleab Power PlantP,Unit 1i Indiana L
05000315 AUTH BYNAME AUTHOR AFFILIATI6N HUNTEReR ~ ST Indiana L Michigan Electric Co, "RBC IP ~ NAME RECIPIENT AFFILIATION DENTONg HiRe Office of Nuclear Reactor Regulationg Director
SUBJECT:
Advises;that util will reload w/Westinghouse 15xi5 optimized fuel assemblies during Cycle 8 Tscheduled for 830831
~ Meeting w/NRC requested on 821103 Ito clearly define licensing review schedule.
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INDIANA It MICHIGAN ELECTRIC COMPANY P. O.
BOX 10 BOWLING GREEN STATION NEW YORK, N. Yo 10004 October 18, 1982 AEP: NRC: 0745 Donald C. Cook Nuclear Plant, Unit No.
1 Docket No. 50-315 License No. DPR-58 Unit No.
1 Cycle 8 Reload Licensing Letter of Notification Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
'Washington, D. C.
20555
Dear Mr. Denton:
This is to advise you that Indiana
& Michigan Electric Company will reload the Donald C. Cook Nuclear Plant Unit No. 1, Cycle 8 with Westinghouse 15 X 15 Optimized Fuel Assemblies (OFAs).
Cycle 8
criticality is currently scheduled for August 31, 1983.
The Westinghouse OFA design features and methodology have been generically approved by the NRC via the review of Westinghouse Topical
- Report, WCAP 9500, "Reference Core Report 17 X 17 Optimized Fuel Assembly".
We expect to complete our review of the Westinghouse Plant specific analyses justifying the transition from the current Exxon fueled core to a Westinghouse 15 X 15 OFA core for D. C. Cook Unit 1 in early 1983.
Upon completion of this review, we will submit the appropriate reload licensing documentation.
Although we currently intend to operate D. C. Cook Unit 1, Cycle 8 at the present licensed maximum. level of 3250 MWt, the core safety analyses (with the exception of large break LOCA) will be performed at an uprated power level of 3425 MWt.
This conservative design basis will provide early identification of those safety/accident analysis limits and associated Technical Specifications for a potential uprating.
This also provides your Staff ample review opportunity prior to our intended future application for operation at an uprated power level.
The licensing applications and supporting analyses will utilize the approved Westinghouse Xmproved Thermal Design Procedure (XTDP) and the WRB-1 DNBR correlation for the first time on Cook Unit 1.
These were previously employed to license Cook Unit 2 operations.
Other features PDQ ggDCg 8>1018 8akoai0393 I
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Mr. Harold R nton AEP:NRC:0745 being introduced with the Cycle 8 reload include the Westinghouse Wet Annular Burnable Absorber (WABA) and a revision to the Westinghouse fuel thermal safety model (PAD Code) applied to LOCA.
Both of these design features were discussed with members of the Nuclear Regulatory Commission Core Performance Branch in meetings with Westinghouse on August 16th and 17th.
Westinghouse is submitting generic topical reports on these subjects and is committed to support the NRC's review consistent with our Cycle 8 reload schedule startup date of August 31, 1983.
In order to clearly define the licensing review and schedule requirements associated with the Cook Unit 1, Cycle 8 transition reload, we request a meeting with appropriate NRC personnel on November 3, 1982.
Westinghouse personnel would also participate at this meeting.
A proposed agenda for the meeting is attached.
Please advise us of the acceptability of our proposed meeting date and agenda topics.
This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, R.
S. Hunter Vice President Attachment.
cc:
John E. Dolan M. P. Alexich R.
W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at Cook Plant - Bridgman
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PROPOSED AGENDA NRC/AEP/WESTINGHOUSE - D. C.
COOK UNIT 1 YEETING I.
Introduction Background/Purpose of Heeting Cook Unit 1 Transition Plans II.
Licensing Actions Planned Submittal for Cycle 8 Transition at 3250 Hh't Core Design Accident Analyses/Technical Specification Hodifications Fuel Storage Considerations III. Design Features of Cycle 8 Core Design 15 X 15 OFA Met Annular Burnable Poison Westinghouse Revised Fuel Thermal Safety Hodel Improved Thermal Design Procedure (ITDP)
DNB Correlations IV.
NRC/AEP/Westinghouse Open Discussion Conclusion/Actions