ML17331B131: Difference between revisions
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{{#Wiki_filter:"'ACCELERATED ISTRIBUTION DEMON/'RATION SYSTEM I'!REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS) | {{#Wiki_filter:" ' ACCELERATED ISTRIBUTION DEMON/'RATION SYSTEM I '! | ||
YES FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRXCK,E. | REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS) | ||
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECXP.NAME RECIPIENT AFFILIATION R MURLEY,T.E. | ACCESSXON NBR:9312230045 DOC.DATE: 93/12/17 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRXCK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECXP.NAME RECIPIENT AFFILIATION R MURLEY,T.E. Document Control Branch (Document Control Desk) | ||
Document Control Branch (Document Control Desk) | |||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards"DC Cook Units 1&2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," to replace analysis attached to 921111 submittal to justify TS change to increase allowable tolerances. | Forwards "DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," to replace analysis attached to 921111 submittal to justify TS change to increase allowable tolerances. | ||
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR | DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution ENCL SIZE SF/ | ||
General Distribution NOTES: | NOTES: | ||
RECXPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 XNTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DS SA/S PLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 O~CLFDCB 1 0 OGC/HDS2 1 0 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D | |||
D D | |||
NOTE TO ALL "RIDS" RECIPIENTS: | |||
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION, LISTS FOR DOCUMENTS YOU DON'T NEED! | |||
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 | |||
==Dear Dr.Murley:== | Indiana Michi~ | ||
This letter is submitted to replace an analysis that was attached to our November 11, 1992 submittal to justify a technical specification change to increase the allowance tolerances for the main steam safety valves for Donald C.Cook Nuclear Plant Units 1 and 2 to+3%.The analysis issued as Attachment 4 in the original submittal assumes nominal rather than minimum auxiliary feedwater flows for Unit 1.This is a non-conservative assumption when considering a small break LOCA, as was discussed with your staff on November 12, 1993.Westinghouse Report SECL-91-429, Revision 2,"Donald C.Cook Units 1 and 2, Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," is found in Attachment 1 of this letter.Unit 2 auxiliary feedwater flow assumptions were correct in the original submittal. | Power Compai~ | ||
Attachment 1 has been updated with the correct auxiliary feedwater flows for Unit 1 and the results do not change the conclusions reached in the original submittal letter.Please replace Attachment 4 of the November ll, 1992 letter with Attachment 1 of this letter.9312230045 931217 PDR ADOCK 05000315.P ,'DR Dr.T.E.Murley 2-AEP NRC:1169A This letter is submitted pursuant to 10 CFR 50.54(f)and, as such an oath statement is attached.Sincerely, Vice President cad Attachment cc: A.A.Blind G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector J.R.Padgett Dr.T.E.Murley 3 AEP:NRC:1169A bc: S.J.Brewer D.H.Malin M.L.Horvath-Bridgman-w/o attachment J.B.Kingseed D.F.Powell J.B.Shinnock-w/o attachment W.G.Smith, Jr.J.B.Hickman, NRC-Washington, D.C.AEP'NRC'1169A DC-N-6015.1 | P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1169A Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley I | ||
-w/o attachment STATE OF OHIO)COUNTY OF FRANKLIN)E.E.Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES and knows the contents thereof;and that said contents are true to the best of his knowledge and belief.Subscribed and sworn to before me this~~~day of 19~8 NOTAR PUBLIC RITA D.HILL HOTARV PUCI.IC.STAT OF OHIO f8 COI,IMISSIOX DIPIRiS ATTACHMENT 1 to AEP:NRC:1169A WESTINGHOUSE REPORT SECL-91-429, Revision 2,"DONALD C.COOK UNITS 1 AND 2 MAIN STEAM SAFETY VALVE LIFT SETPOINT TOLERANCE RELAXATION" hy I!1}} | December 17, 1993 | ||
==Dear Dr. Murley:== | |||
This letter is submitted to replace an analysis that was attached to our November 11, 1992 submittal to justify a technical specification change to increase the allowance tolerances for the main steam safety valves for Donald C. Cook Nuclear Plant Units 1 and 2 to + 3%. The analysis issued as Attachment 4 in the original submittal assumes nominal rather than minimum auxiliary feedwater flows for Unit 1. This is a non-conservative assumption when considering a small break LOCA, as was discussed with your staff on November 12, 1993. Westinghouse Report SECL-91-429, Revision 2, "Donald C. Cook Units 1 and 2, Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," is found in Attachment 1 of this letter. Unit 2 auxiliary feedwater flow assumptions were correct in the original submittal. Attachment 1 has been updated with the correct auxiliary feedwater flows for Unit 1 and the results do not change the conclusions reached in the original submittal letter. Please replace Attachment 4 of the November ll, 1992 letter with Attachment 1 of this letter. | |||
9312230045 931217 PDR ADOCK 05000315 | |||
.P , 'DR | |||
Dr. T. E. Murley 2- AEP NRC:1169A This letter is submitted pursuant to 10 CFR 50.54(f) and, as such an oath statement is attached. | |||
Sincerely, Vice President cad Attachment cc: A. A. Blind G. Charnoff J. B. Martin - Region III NFEM Section Chief NRC Resident Inspector J. R. Padgett | |||
Dr. T. E. Murley 3 AEP:NRC:1169A bc: S. J. Brewer D. H. Malin M. L. Horvath - Bridgman - w/o attachment J. B. Kingseed D. F. Powell J. B. Shinnock - w/o attachment W. G. Smith, Jr. | |||
J. B. Hickman, NRC - Washington, D. C. | |||
AEP'NRC'1169A DC-N-6015.1 - w/o attachment | |||
STATE OF OHIO) | |||
COUNTY OF FRANKLIN) | |||
E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES and knows the contents thereof; and that said contents are true to the best of his knowledge and belief. | |||
Subscribed and sworn to before me this ~~~ | |||
day of 19 ~8 NOTAR PUBLIC RITA D. HILL HOTARV PUCI.IC. STAT OF OHIO f8 COI,IMISSIOX DIPIRiS | |||
ATTACHMENT 1 to AEP:NRC:1169A WESTINGHOUSE REPORT SECL-91-429, Revision 2, "DONALD C. COOK UNITS 1 AND 2 MAIN STEAM SAFETY VALVE LIFT SETPOINT TOLERANCE RELAXATION" | |||
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Latest revision as of 13:56, 22 October 2019
ML17331B131 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 12/17/1993 |
From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17331B132 | List: |
References | |
AEP:NRC:1169A, NUDOCS 9312230045 | |
Download: ML17331B131 (7) | |
Text
" ' ACCELERATED ISTRIBUTION DEMON/'RATION SYSTEM I '!
REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
ACCESSXON NBR:9312230045 DOC.DATE: 93/12/17 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRXCK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECXP.NAME RECIPIENT AFFILIATION R MURLEY,T.E. Document Control Branch (Document Control Desk)
SUBJECT:
Forwards "DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," to replace analysis attached to 921111 submittal to justify TS change to increase allowable tolerances.
DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution ENCL SIZE SF/
NOTES:
RECXPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 XNTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DS SA/S PLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 O~CLFDCB 1 0 OGC/HDS2 1 0 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION, LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14
Indiana Michi~
Power Compai~
P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1169A Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley I
December 17, 1993
Dear Dr. Murley:
This letter is submitted to replace an analysis that was attached to our November 11, 1992 submittal to justify a technical specification change to increase the allowance tolerances for the main steam safety valves for Donald C. Cook Nuclear Plant Units 1 and 2 to + 3%. The analysis issued as Attachment 4 in the original submittal assumes nominal rather than minimum auxiliary feedwater flows for Unit 1. This is a non-conservative assumption when considering a small break LOCA, as was discussed with your staff on November 12, 1993. Westinghouse Report SECL-91-429, Revision 2, "Donald C. Cook Units 1 and 2, Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," is found in Attachment 1 of this letter. Unit 2 auxiliary feedwater flow assumptions were correct in the original submittal. Attachment 1 has been updated with the correct auxiliary feedwater flows for Unit 1 and the results do not change the conclusions reached in the original submittal letter. Please replace Attachment 4 of the November ll, 1992 letter with Attachment 1 of this letter.
9312230045 931217 PDR ADOCK 05000315
.P , 'DR
Dr. T. E. Murley 2- AEP NRC:1169A This letter is submitted pursuant to 10 CFR 50.54(f) and, as such an oath statement is attached.
Sincerely, Vice President cad Attachment cc: A. A. Blind G. Charnoff J. B. Martin - Region III NFEM Section Chief NRC Resident Inspector J. R. Padgett
Dr. T. E. Murley 3 AEP:NRC:1169A bc: S. J. Brewer D. H. Malin M. L. Horvath - Bridgman - w/o attachment J. B. Kingseed D. F. Powell J. B. Shinnock - w/o attachment W. G. Smith, Jr.
J. B. Hickman, NRC - Washington, D. C.
AEP'NRC'1169A DC-N-6015.1 - w/o attachment
STATE OF OHIO)
COUNTY OF FRANKLIN)
E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this ~~~
day of 19 ~8 NOTAR PUBLIC RITA D. HILL HOTARV PUCI.IC. STAT OF OHIO f8 COI,IMISSIOX DIPIRiS
ATTACHMENT 1 to AEP:NRC:1169A WESTINGHOUSE REPORT SECL-91-429, Revision 2, "DONALD C. COOK UNITS 1 AND 2 MAIN STEAM SAFETY VALVE LIFT SETPOINT TOLERANCE RELAXATION"
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1