ML17326A144
| ML17326A144 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/17/1999 |
| From: | Bakken A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| C0999-03, NUDOCS 9909240199 | |
| Download: ML17326A144 (11) | |
Text
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CATEGORY 2
REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)
ACCESSION NBR:9909240199 DOC.DATE: 99/09/17 NOTARIZED! NO DOCKET ¹ FACIL:50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR APFXLZATZON BAKKEN,A.C.
(formerly Indiana
& Michigan Ele RECXP.NAME RECIPIENT APPXLZATZON Region 3
(Post 820201)
SUBJECT:
Submits trace on second shipment of two plant, Unit 2 steam generators. Info re shipment submitted.
DISTRIBUTION CODE:
ZEOZD COPIES RECEIVED:LTR I ENCL KKSIZE:
TITLE: General (50 Dkt) -Insp Rept/Notice of Violation Response NOTES:
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RECIPIENT ID CODE/NAME LPD3-1 COPIES LTTR ENCL RECXPXENT ZD CODE/NAME STANG, J COPIES LTTR ENCL INTERNAL: AEOD/TTC PXLE CENTER~~
NRR/DZPM/OLHP NUDOCS-ABSTRACT OGC/RP EXTERNAL: LMITCO MARSHALL NRC PDR 1
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DEDRO NRR/DIPM/XIPB NRR/DRIP/REXB OE RGN3 PILE 01 NOAC NUDOCS PULLTEXT 1
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NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATIONi CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL
Indiana Michigan Powac Company Cat Nues hn Oneox'n Bdymn N491%
616 465 5901 RA DRA RC EIC t'RIOR1 RO
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IN'ce NlCHleaN POHNN C0999 03 10 CFR 70 September
- 17. 1999 Docket No.: 50-316 United States Nuclear Regulatory Commission Regional Administrator, Region III 801 Warrenville Road Lisle, IL 60532-4351 Donald C. Cook Nuclear Plant Unit 2 UNIT2 STEAM GENERATOR SHIPMENT In accordance with the requirements of 10 CFR 20, Appendix G, Section III E, which requires that any shipment or part ofa shipment for which acknowledgement is not received within 20 days of transfer shall be traced and reported to the Nuclear Regulatory Commission, this letter is submitted for the second shipment ofthe two Donald C. Cook Unit 2 steam generators.
On June 11, 1999, the second shipment oftwo Unit 2 steam generators was made from Indiana Michigan {IAM)Power Company's Donald C. Cook Nuclear Plant to Barnwell, South Carolina.
The generators completed the rail portion of the shipment on July 12, 1999, and were subsequently transferred to the Barnwell site using a heavy haul trailer. The first generator was received at the Barnwell burial site on July 15, 1999, and the second generator was received on July 17, 1999.
Chem-Nuclear Systems sent NRC Form 450 to D. C. Cook on August 3, 1999, which acknowledged Barnwell's receipt ofboth generator shipments. The elapsed time from transfer ofthe components until Cook received acknowledgment ofthe arrival ofthe steam generators was in excess ofthe allowed 20 davs.
Due to the unusual size and weight of the steam generator component
. th s.
e T
s ipment was made under a specific exemption from the Departme t f ransportation DOT-E 12190 regulations. As part of the operational controls required by the DOT exemption and Chem-Nuclear procedure "Transportation and Emergency Response Plan for D. C. Cook Unit 2 Steam Generator Project, Project No. 46628," three individuals accompanied the shipment while in transit to Barnwell.
9909240199 990917 PDR ADOCK 0500031b P
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U. S. Nuclear Regulatory Commission Page 2 C0999-03 Because the shipment was accompanied and the location known at all times, positive control of the steam generators was maintained.
No further formal investigation for this shipment is required.
This letter shall service to fulfillthe reporting requirement of 10 CFR 20, Appendix G.Section III E.
Sincerely, A. Christopher Bakken, III Site Vice President
/dms Document Control Desk J. E. Dyer MDEQ DW0 RPD NRC Resident Inspector R. Whale
Indiana Michigan Power Company Cook Nudear Rara One CookRar EIkkrnan. MI49106 61 6 4i5 6901 O
Z INDIANA NICHIGAN POWER C0999-03 10 CFR 20 September 17, 1999 Docket No.: 50-316 United States Nuclear Regulatory Commission Regional Administrator, Region III 801 Warrenville Road
'Lisle, IL 60532-4351 Donald C. Cook Nuclear Plant Unit 2 UNIT2 STEAM GENERATOR SHIPMENT In accordance with the requirements of 10 CFR 20, Appendix G, Section IIIE, which requires that any shipment or part ofa shipment for which acknowledgement is not received within 20 days of transfer shall be'traced and reported to the Nuclear Regulatory Commission, this letter is submitted for the second shipment ofthe two Donald C. Cook Unit 2 steam generators.
On June 11, 1999, the second shipment oftwo Unit 2 steam generators was made from Indiana Michigan (18'cM) Power Company's Donald C. Cook Nuclear Plant to Barnwell, South Carolina.
The generators completed the rail portion of the shipment on July 12, 1999, and were subsequently transferred to the Barnwell site using a heavy haul trailer. The first generator was received at the Barnwell burial site on July 15, 1999, and the second generator was received on July 17, 1999.
Chem-Nuclear Systems sent NRC Form 450 to D. C. Cook on August 3, 1999, which acknowledged Barnwell's receipt ofboth generator shipments. The elapsed time from transfer ofthe components until Cook received acknowledgment ofthe arrival ofthe steam generators was in excess ofthe allowed 20 days.
Due to the unusual size and weight of the steam generator components, the shipment was made under a specific exemption from the Department of Transportation DOT-E 12190 regulations. As part of the operational controls required by the DOT exemption and Chem-Nuclear procedure "Transportation and Emergency Response Plan for D. C. Cook Unit2 Steam Generator Project, Project No. 46628," three individuals accompanied. the shipment while in transit to Barnwell.
0P> l> ~~ 4~
AEP: ~Ir0ericn's Seegar Pnrlrrer
U. S. Nuclear Regulatory Commission Page 2 C0999-03 Because the shipment was accompanied and the location known at all times, positive control of the steam generators was maintained.
No further formal investigation for this shipment is required.
This letter shall service to fulfillthe reporting requirement of 10 CFR 20, Appendix G, Section IIIE.
Sincerely, A. Christopher Bakken, III Site Vice President
/dms c'ocument Control Desk J. E. Dyer MDEQ DW A RPD NRC Resident Inspector R. Whale
Distri65.txt Distribution Sheet D-34
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Priority: Normal From:
Esperanza Lomosbog Action Recipients:
Toni L Harris NRR/DLPM/LPD3-1 J Stang Internal Recipients:
RidsNrrDssaSrxb RidsNrrDssaSplb RidsManager RidsAcrsAcnwMailCenter OGC/RP NRR/DSSA/SRXB NR~R/
SSA-/SBLB FILE CENTER 01 ACRS Copies:
1 1
1 Not Found Not Found Not Found OK OK OK OK Not Found Not Found Not Found Not Found Not Found External Recipients:
NOAC Not Found Total Copies:
Item:
ADAMS Document Library:
ML ADAMS"HQNTAD01 ID: 003681609
'I
Subject:
Letter submitting Annual Report of Loss-of-Coolant Accident Evaluation Model Changes and New Large Break Loss-of-Coolant Accident Analysis o
f Record for Unit 2.
Body:
Docket:
- 05000316, Notes:
N/A Page 1
One Cook Aaoe Bridynsn, Ml 49106 6164666901 FI February 2, 2000 Docket No: 50-316 C0200-08 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATT¹ Document Control Desk Mail Stop 0-P1-17 Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Unit 2 ANNUALREPORT OF LOSS-OF-COOLANT ACCIDENT EVALUATIONMODELCHANGES ANDSUBMITTALOF NEW LARGEBREAKLOSS-OF-COOLANT ACCIDENTANALYSISOF RECORD FOR UNIT2 Pursuant to 10CFR 50.46, Indiana Michigan Power Company (1AM), the Licensee for Donald C. Cook Nuclear Plant (CNP), is submitting an annual report of loss-of-coolant accident (LOCA) model changes affecting the peak cladding temperature (PCT) for Unit 2. This submittal includes a new large break LOCA (LBLOCA)analysis ofrecord provided forNRC information along with responses to previous NRC requests for information pertaining to that analysis.
Attachment 1 to this letter describes the background for the new LBLOCA analysis of record and describes assessments against the small break LOCA analyses of record.
Attachment 2 provides the analysis report for the new LBLOCAanalysis ofrecord. Attachment 3 provides PCT margin utilization tables for large break and small break LOCAs showing that the calculated PCTs remain within the limit specified in 10CFR50.46.
Attachment 4 contains 186M's responses to previous NRC requests for information pertaining to the new LBLOCA analysis of record.
Attachment 5 contains a summary of new IAM commitments made in this submittal.
Should you have any questions, please contact Mr. Robert C. Godley, Director of Regulatory Affairs, at (616) 466-2698.
Sincerely, M. W. Rencheck Vice President, Engineering AEP: Arnericn's Estergl'nrtner C4~r argo i
U. S. Nuclear Regulatory Commission Page 2 C0200-08
/dms Attachments J. E. Dyer MDEQ DW 8c RPD, w/o attachment NRC Resident Inspector R. Whale, w/o attachment
U. S. Nuclear Regulatory Commission Page 3 C0200-08 bc:
T. P. Beilman FOLIO D. J. Garner/S. A. Greenelee/W.
S. Lacey R. W. Gaston, w/o attachment S. B. Haggerty D. W. Jenkins/Hopkins A Sutter, w/o attachment J. B. Kingseed/G. J. Hill W. T. MacRae/M. J. Gumns, w/o attachments M. W. Marano J. F. Stang, Jr., NRC - Washington, D.C.
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