ML17320A554
| ML17320A554 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/05/1983 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17320A555 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR AEP:NRC:0514G, AEP:NRC:514G, NUDOCS 8307110290 | |
| Download: ML17320A554 (6) | |
Text
REGULA
'Y INFORMATION DISTRIBUTI(
SYSTEM (RIDS),
ACCESSION NBR: 8307110290, DOC. DATE: 83/07/05 NOTARIZED:
NO FACIL:50-315 Donald C ~
Cook Nuclear Power Planti Unit 1i Indjana L
50-316 Donald C.
Cook Nuclear Power Planti Unit 2i Indiana 8
AUTH.NAME AUTHOR AFFILIATION ALEXICH.M.P.
Indiana 8 Michigan Electric Co ~
RECIP.NAME RECIPIENT AFFILIATION DENTONiH.R.
Office of Nuclear Reactor Reoulationi Director DOCKET 0
05000315 05000316
SUBJECT:
Forwards NCAP-. 10230i "Evaluation of Acceptabilitv of Reactor Vessel Head Lift Ria.Reactor Vessel Internals Lift RiaiLoad Cella "Load Cell Linkaae to Reauirements of NUREG 0612'i" 8
responses (o
NRC rectum endation DISTRIBUTION CODE:
A 33S OPIES RECEI D:LTR 'L~", ENCL '
SIZE!'ITLE:
OR Submittal:
USI A-36 Control of Heavv Load Near Spent Fuel-NUREG 06 NOTES:
RECIPIENT ID CODE/NAME NRR ORB1 BC INTERNAL: NRR REQUA,G 09 AEB REG FI 04 COPIES LTTR ENCL 7
7 1
1 RECIPIENT ID CODE/NAME NRR SINGHi A 01 NRR/DL/ORAB 12 NRR/DS I/ASI RGN3 COPIES LTTR ENCL EXTERNAL: ACRS NRC PDR NTIS 13 02 6
1 1
1 1
LPOR NSIC 03 06 TOTAL NUMBFR OF COPIES REQUIRED:
LTTR 28 ENCL
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O.
BOX 10 BOWLING GREEN STATION NEW YORK, N. Y, 10004 July 5, 1983 AEP:NRC:0514G Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 CONTROL OF HEAVY LOADS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
This letter and its Attachments address the analysis of the lifting arrangement for the reactor vessel head and upper internals.
This completes our response to Section 2.1 of Enclosure 3 to Mr. D. G.
Eisenhut's letter of December 22, 1980.
Attachment No.
1 is the Westinghouse report "Evaluation of the Acceptability of the Reactor Vessel Head LiftRig, Reactor Vessel Internals Lift Rig, Load Cell, and Load Cell Linkage to the Requirements of NUREG-0612" (WCAP-10230).
Attachment No.
2 contains Indiana 6 Michigan Electric Company's responses to the Westinghouse recommendations contained in Section 6 (main body) of WCAP-10230.
We also wish to point out that our review of a related previous submittal, letter No. AEP:NRC:0514E, dated September 29, 1982, has revealed a small error on one of the marked-up drawings (Drawing No. 12-5169).
This drawing indicated the crane and hoist locations.
The drawing's notation is revised as follows:
a)
Item 20 5 ton hoist is North of Column line "12" ~
b)
Item 27 2b ton hoist, is South of Column line "12".
We have indicated in Attachment No.
3 to this letter the modified locations.
S307110290 830705 PDR ADOCK 050003i5 P
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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, M.. Al ch Vice President
/md Attachment cc:
John E. Dolan - Columbus R.
S. Hunter R.
W. Jurgensen W. G. Smith, Jr.
R.
C. Callen G. Charnoff NRC Resident Inspector.at Cook Plant - Bridgman
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