ML17326B526
| ML17326B526 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/06/1989 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1067B, NUDOCS 8902130486 | |
| Download: ML17326B526 (6) | |
Text
~get..ED ~TED DI~BUTlON DE }d0% STR+lOY SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
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SUBJECT:
Responds to NRC 890124 ltr re request for addi info on reduced temp
& pressure.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES ACCESSION NBR:8902130486 DOC.DATE: 89/02/06 NOTARIZED: NO DOCKET g FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
RECIPIENT ID CODE/NAME PD3-1 LA STANG,Z INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/S ICB NUDOC B CT FILE 0
EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
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1 1
0 1
1 1
1 1
1 1
1 1
1 l
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 OGC/HDS1 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 2
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NOIE TO ALL "RIDS" RECIPIEÃIS'IZASE HELP US TO REDUCE HASTE!
(XVI'ACZ 'lHE DOCXMMZ CGNIBOL DESK, RXM Pl-37 (EXT. 20079) K) ELIK2VZE YOUR NAME FRCH DISTlGBVTIGN LISTS FOR DOCKKWZS YOU DQNiT NEED(
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL 16
4 II
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1067B Donald C.
Cook Nuclear Plant Unit 1 Docket No. 50-315 License No.
DPR - 58 ADDITIONALINFORMATION ON REDUCED TEMPERATURE AND PRESSURE SUBMITTAL'ORON DILUTION ACCIDENT U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley February 6,
1989
Dear Dr. Murley:
This letter responds to a January 24, 1989 request from your staff for additional info'rmation regarding the analyses supporting our Unit-'1 Reduced Temperature and Pressure (RTP) Program (refer to AEP:NRC:1067, dated October 14, 1988).
Specifically, your staff reque'sted'.th'e time that would elapse from the beginning of a boron dilution'ransient until shutdown margin is lost.
The results of the analysis of the boron dilution transient indicate that the reactor will return critical after reactor trip for the at, power case or will become critical for the startup case at the following times after the boron dilution begins:
At Power:
45.0 minutes Startup:
68.3 minutes This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M: P; Al'exich':>>'".
Vice Piesident
.'PA/eh L
35'02i30486 S90206 PDR ADQCK 05000315 P
PDC yjo(
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Dr. T.
E. Murley AEP:NRC:1067B cc:
D. H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. CharnofE G. Bruchmann A. B. Davis
- Region III NRC Resident Inspector
- Bridgman
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