ML17326A892
| ML17326A892 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/07/1981 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17326A893 | List: |
| References | |
| AEP:NRC:0564A, AEP:NRC:564A, NUDOCS 8105130201 | |
| Download: ML17326A892 (6) | |
Text
I REGULATOR'FORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBRe8105130201 DOC ~ DATE: 81/05/07 NOTARIZED:
NO DOCKET FACIL:50 3i6 Donald C>>
Cook Nuclear Power Plant< Unit 2E Indiana 8
05000316 AUTH ~ AAME AUTHOR AF F ILIATI ON HUNTERER ~ S ~
Indiana 8 Michigan Electric Co, RECIP ~ NAME" RECIPIENT AFFILIATION DENTONPH ~ RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
For wards supporting info for1 Tech Specs change request; Includes Figure 0. l of WCAP-9828 re nucleai design 8 core mgt for Cycle 3
& "Reload Safety EvaluationgDC-Cook Nuclear PfantEUnit 2~Cycl*e. 3."
DISTRIBUTION CODE,:
AOOIS COPIES RECEIVED:LTR $
ENCL J' SIZE:: C2dl7 TITLE1: General Distr ibution for after Issuance of Operating License' NOTES:Send 3 copies of all material to ILES 05000316 RECIPIENT IO CODE/NAME, ACTION:
VARGAP8>>
00 INTERNAL: D/DIRrHUM FAC08
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1 2
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RECIPIENT ID CODE/NAME DIRE DIV OF LIC NRC PDR 02 OR ASSESS BR 10 01 COPIES LTTR ENCL 1
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1-EXTERNAL: ACRS NSLC 09 05 16 16 1
1 LPDR 03 1
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BO WLIN G G R E EN ST ATION NEW YORK, N. Y. 10004 May 7, 1981 AEP:NRC:0564A Donald C.
Cook Nuclear Plant Unit No.
2 Docket No. 50-316 License No.
DPR-74 Additional Support Information for Technical Specification Change Request gpà 1>'98~
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e Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dear'r.
Denton:
Please find attached to this letter one copy of each of the following two items:
a)
"Reload Safety Evaluation for D.
C.
Cook Nuclear Plant Unit 2, Cycle 3", December 1980.
b)
Figure 4.1 of "The Nuclear Design and Core Management of the Donald C.
Cook Unit 2 Nuclear Plant Cycle 3", WCAP-9828, December 1980.
Item a) was used as reference in our request for a Technical Specifica-tion Change contained in Attachment 1 to our letter AEP:NRC:0564 dated May 1, 1981.
Item b) is being supplied at the request of your Staff to assist them in the review of our above mentioned request.
Very truly yours, RE S. Hunter Vice President cc:
John E. Dolan - Columbus R.
C. Callen G. Charnoff R.
W. Jurgensen D. V. Shaller Region III Resident Inspector - Bridgman gao i
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4 Core Height (Ft)
~ A 10 12 Top Maximum Fq PRel vs Axial Core Height.
During Normal Core Operation
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