ML17320A632
| ML17320A632 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/29/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 8307250239 | |
| Download: ML17320A632 (5) | |
Text
Docket Wo. 50-315
~vN 2s lgIO ter.
John Dolan, Vice President Indiana and Michigan Electric Company Post Office Box 18 Bowling Green Station New York, New York 10004 DISTRIBUTION Docket File NRC PDR Local PDR ORB1mI 1
Reading D. Eisenhut OELD E, Jordan D. Higginton C. Parrish NSIC J. Taylor ACRS (10)
Enclosure:
as ~Rated Steven A. Yar ga, Chief Operating Reactors Branch No.
1 Division of Licensing
Dear thr. Dolan:
In our review of the D. C.
Cook Unit 1-cycle 8 reload analysis submitted on I<ay ll, 1983, we have identified additional information which we need to support our review.
The enclosed questions are on reactor physics and fuels. If you have any ques)dons on the enclosed, please let us know.
Sincerely, e
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Mr. John Dolan Indiana and Michigan Electric Company cc:
Mr. M. P. Alexich Assistant Vice President for Nuclear Engineering American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gera'ld Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 W.
G. Smith Jr., Plant Manager Donald C.
Cook Nuclear Plant P.
0.
Box 458 Bridgman, Michigan 49106 U. S.
Nuclear Regulatory Commission.
Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 The Honorable Tom Corcoran United States House of Representatives Washington, D.
C.
20515 James G. Keppler Regional Administrator - Region III U. S.
Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137
QUESTIONS FOR D. C.
COOK UNIT 1
RELOAD REACTOR PHYSICS SECTION 1.
Since this is apparently to be the reference cycle for the use of the Mestinghouse OFA design fuel, please provide a summary table of core nuclear parameters against which future cycles may be compared.
Also provide a comparison of these parameters to those for the present reference cycle.
2.
In Table 2, of Attachment C, notes (2) and (3), the equations seem to be for power Doppler coefficient rather than for Doppler defect.
Please confirm.
3.
In Section 6.3.2, what is the value of the conservatively large negative moderator coefficient7 II 4.
In Figures 10, 11, and 12 of Attachment C, the distinction between maximum and minimum feedback curves is not clear.
Please clarify.
5.
In Figures 4 through 9 of Attachment C are the reactivity values given as part of the title the total rod worths or should they be reactivity insertion rates in pcm/sec.
Please clarify.
6.
Please provide a loading diagram for Cycle 8 along with a table of the nuclear parameters for comparison to those used in the safety evaluation.
FUELS SECTION 1.
Please provide the projected maximum assembly - averaged burnups of ENC and Westinghouse fuel for Cycle'-8.
What will be the maximum discharge batch - averaged burnup at the end
.- of Cycle-8?
2.
The Cycle-8 and future cores will consist of ENC and Westinghouse fuel assemblies, please provide an analysis of the structural adequacy of the fuel assemblies during the de5ign seismic event for mixed core.