ML17320A424
| ML17320A424 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/07/1983 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0637L, AEP:NRC:637L, NUDOCS 8303140344 | |
| Download: ML17320A424 (6) | |
Text
REGULA RY INFORMATION DISTRIBUTIO" SYSTEM (RIDS)
ACCBSSION NBR:8303140344 DOC ~ DATE: 83/03/07 NO ARIZED:
NO FACIL:50-316 Donald C.
Cook Nuclear Power Pl anti Unit 2i Indiana
~
'AUTH BYNAME AUTHOR AFFILIATION HUNTERgR,Se Indiana
& Michigan Elect ic Co, R E<<C I P ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulation~
Director DOCKET 05000316 SUSJECTs Discusses License DPR-74 amend authorizing Cycle 4 which contains number of restrictions re reactor operations, Meeting requested for 5 830315 to present "util program for obtaining info 8 justifying removal of licensing condi,,tions
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INOIANA L MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 80 WLING GR E EN STATION NEW YORK, N. Y, 10004 March 7, 1983 AEP:NRC: 0637L Donald C. Cook Nuclear Plant Unit No.
2 Docket No. 50-316 License No. DPR-74 MEETING REQUEST D. C.
COOK UNIT 2 LICENSING Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
The license amendment authorizing Cycle 4 contains a number of restrictions regarding reactor operations.
In addition, the Safety Evaluation Report accompanying the license amendment includes requirements for further safety analyses and additional information.
These analyses and additional information are to be provided prior to Cycle 5; in fact, some information is to be provided by this April.
We have developed a program for obtaining the required information and for justifying removal of these new licensing restrictions.
We are requesting a meeting on March 15, 1983 with members of your staff and representatives of the involved technical review groups to present this program and to reach a firm agreement with them regarding the objectives, information to be provided, and schedule.
Specific subjects which we wish to discuss are those identified in your Safety Evaluation Report accompanying the Cycle 4 license amendment.
These subjects are as follows:
1.
Analyses to be performed following approval of the RODEX-2 fuel performance code:
a ~
Strain, oxidation, and PCI characteristics.
b.
The stored energy of the fuel as necessary input to the ECCS analysis.
c ~
The fuel rod pressure up to end of fuel life.
8303i40344 830307 PDR ADOCK 050003i6 P
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0 Mr. H. R. Denton AEPlNRCl0637L 2.
The fuel rod cladding creep-collapse analysis.
3, Analysis of fuel mechanical integrity following a design basis seismic event.
4.
The plant transient analysis model review and specific additional plant transient analyses requirements.
5.
The rod drop event.
6.
Environmental impact analyses for future cycles with ENC fuel at higher exposures.
The proposed agenda for the meeting is as follows:
SUBJECT REPRESENTATIVE Introduction Review of Cycle 4 Licensing Proposed Licensing Program Discussion and Resolution of Issues J. J. Weiss AEP G. F. Owsley ENC J.
C. Chandler ENC NRC/AEP/ENC We believe three hours should be sufficient time for this meeting.
We would be available for either a morning or afternoon session.
Very truly yours, R.
S. Hunter Vice President RSH:mm cc:
John E. Dolan M. P. Alexich
'R.
W. Jurgensen W. G. Smith, Jr.
Bridgman R.
C. Callen G. Charnoff NRC Resident Inspector at Cook Plant Bridgman
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