ML17329A644: Difference between revisions
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{{#Wiki_filter:<ccrc.Ea<TED | {{#Wiki_filter:<ccrc.Ea<TED o ra.mmrow ozMOw RwTj:ON SvSrEM REGULAT Y INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9210300110 DOC.DATE: 92/10/26 NOTARIZED: | ||
92/10/ | 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 FITZPATRICK,E. | ||
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. | |||
Document Control Branch (Document Control Desk) | |||
==SUBJECT:== | ==SUBJECT:== | ||
Suppl to 910726 application for amends to Licenses DPR-58 I DPR-74,requesting that provisions of TS 3/4.9.7 be inapplicable for loads moved over spent fuel pool for duration of reracking project,per NUREG-0612. | |||
DISTRIBUTION CODE. | DISTRIBUTION CODE.A033D COPIES RECEIVED.LTR t ENCL f SIZE./(7 S TITLE: OR Submittal: | ||
USI A-36 Control of Heavy Load Near Spent Fuel-NUREG-06 | |||
/NOTES:RECIPIENT | /NOTES: RECIPIENT ID CODE/NAME EB NRR SINGH,A STANGiJ INTERNAL: NRR/DST/SPLB 8D OC/LFMB RES DE RES/DSR/RPSB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 4 4 2 2 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 LA PD3-1 PD RR/+ST~XB 8E REG FIL~01 ES~STR7EIB NSIC COPIES LTTR ENCL.1 0 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS: | ||
NRR/DST/SPLB | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16 0 0 Indiana Michigan~Power Company P.O.Box 16631 Coiumbus, OH 43216 N AEP:NRC:1146D Donald C.Cook Nuclear Plant Units 1 and 2 License Nos.50-315 and 50-316 Docket Nos.DPR-58 and DPR-74 SPENT FUEL POOL RERACKING LICENSE CONDITION U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley October 26, 1992 | ||
== | ==Dear Dr.Murley:== | ||
==Reference:== | ==Reference:== | ||
Letter,AEP:NRC:1146, E.E.Fitzpatrick | Letter, AEP:NRC:1146, E.E.Fitzpatrick to T.E.Murley, July 26, 1991, and its attachments,"Licensing Report for Storage Densification of D.C.Cook Spent Fuel Pool," Holtec International Our letter AEP:NRC:1146, dated July 26, 1991, requested technical specification changes associated with reracking the Cook Nuclear Plant spent fuel storage pool.The purpose of this letter is to supplement that request such that a licensing condition will be put in place for the duration of the installation phase of the spent fuel pool reracking project.Attachment 1 is the existing Technical Specification pages marked to reflect proposed changes and Attachment 2 is the proposed revised Technical Specification pages.Specifically, we request that the provisions of Technical Specification 3/4.9.7 be"non-applicable for loads being moved over the spent fuel pool for the duration of the spent fuel pool reracking project.Further, control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612,"Control of Heavy Loads at Nuclear Power Plants." Lastly, administrative controls shall be in place to prevent any loads not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks required by Technical Specification 3/4.9.7 disengaged. | ||
As discussed in the referenced submittal, we have committed to moving rerack-related loads in accordance with NUREG-0612 and to move no heavy loads over fuel assemblies. | |||
No loads will be moved over the spent fuel pool when the rigging is not in compliance with NUREG-0612. | |||
For these reasons, this request does not affect 9210300ii0 5'21026 PDR,,ADOCK 05000315 ('PDR 0~/*r~<<~b r Dr.T.E.Murley-2-AEP:NRC:1146D the conclusions of the significant hazards determination in our original submittal, AEP:NRC:1146, dated July 26, 1991, regarding the spent fuel pool reracking. | |||
Additionally, | Additionally, the change will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.It is anticipated that physical rack movement associated with the rerack installation phase will commence in January 1993 and end in July 1993.This letter is submitted pursuant to 10 CFR 50.54(f)and, as such, an oath statement is enclosed.pP E.E.Fitzpatrick Vice President eh Attachment cc: D.H.Williams, Jr.A.A.Blind-Bridgman J.R.Padgett G.Charnoff NFEM Section Chief A.B.Davis-Region III NRC Resident Inspector-Bridgman 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 Spent Fuel Reracking License Condition 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~4~day of P TARY PU LIC AtTh D.Hl L tTOTARY PUBLlC.STATE Oi ONl0 NY COMhllSSIDtl EXPIIIES~>~ | ||
-Bridgman | |||
~+ | ~+ | ||
0 k S Dr.T.E.Murley-3-AEP:NRC:1146D bc: S.J.Brewer D.H.Malin/E.G.Lewis M.L.Horvath-Bridgman J.B.Shinnock W.G.Smith, Jr.J.F.Stang, NRC-Washington, D.C.AEP:NRC:1146D DC-N-6015.1}} |
Revision as of 08:40, 6 July 2018
ML17329A644 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 10/26/1992 |
From: | FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17329A645 | List: |
References | |
RTR-NUREG-0612, RTR-NUREG-612 AEP:NRC:1146D, NUDOCS 9210300110 | |
Download: ML17329A644 (8) | |
Text
<ccrc.Ea<TED o ra.mmrow ozMOw RwTj:ON SvSrEM REGULAT Y INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9210300110 DOC.DATE: 92/10/26 NOTARIZED:
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 FITZPATRICK,E.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Suppl to 910726 application for amends to Licenses DPR-58 I DPR-74,requesting that provisions of TS 3/4.9.7 be inapplicable for loads moved over spent fuel pool for duration of reracking project,per NUREG-0612.
DISTRIBUTION CODE.A033D COPIES RECEIVED.LTR t ENCL f SIZE./(7 S TITLE: OR Submittal:
USI A-36 Control of Heavy Load Near Spent Fuel-NUREG-06
/NOTES: RECIPIENT ID CODE/NAME EB NRR SINGH,A STANGiJ INTERNAL: NRR/DST/SPLB 8D OC/LFMB RES DE RES/DSR/RPSB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 4 4 2 2 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 LA PD3-1 PD RR/+ST~XB 8E REG FIL~01 ES~STR7EIB NSIC COPIES LTTR ENCL.1 0 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16 0 0 Indiana Michigan~Power Company P.O.Box 16631 Coiumbus, OH 43216 N AEP:NRC:1146D Donald C.Cook Nuclear Plant Units 1 and 2 License Nos.50-315 and 50-316 Docket Nos.DPR-58 and DPR-74 SPENT FUEL POOL RERACKING LICENSE CONDITION U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley October 26, 1992
Dear Dr.Murley:
Reference:
Letter, AEP:NRC:1146, E.E.Fitzpatrick to T.E.Murley, July 26, 1991, and its attachments,"Licensing Report for Storage Densification of D.C.Cook Spent Fuel Pool," Holtec International Our letter AEP:NRC:1146, dated July 26, 1991, requested technical specification changes associated with reracking the Cook Nuclear Plant spent fuel storage pool.The purpose of this letter is to supplement that request such that a licensing condition will be put in place for the duration of the installation phase of the spent fuel pool reracking project.Attachment 1 is the existing Technical Specification pages marked to reflect proposed changes and Attachment 2 is the proposed revised Technical Specification pages.Specifically, we request that the provisions of Technical Specification 3/4.9.7 be"non-applicable for loads being moved over the spent fuel pool for the duration of the spent fuel pool reracking project.Further, control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612,"Control of Heavy Loads at Nuclear Power Plants." Lastly, administrative controls shall be in place to prevent any loads not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks required by Technical Specification 3/4.9.7 disengaged.
As discussed in the referenced submittal, we have committed to moving rerack-related loads in accordance with NUREG-0612 and to move no heavy loads over fuel assemblies.
No loads will be moved over the spent fuel pool when the rigging is not in compliance with NUREG-0612.
For these reasons, this request does not affect 9210300ii0 5'21026 PDR,,ADOCK 05000315 ('PDR 0~/*r~<<~b r Dr.T.E.Murley-2-AEP:NRC:1146D the conclusions of the significant hazards determination in our original submittal, AEP:NRC:1146, dated July 26, 1991, regarding the spent fuel pool reracking.
Additionally, the change will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.It is anticipated that physical rack movement associated with the rerack installation phase will commence in January 1993 and end in July 1993.This letter is submitted pursuant to 10 CFR 50.54(f)and, as such, an oath statement is enclosed.pP E.E.Fitzpatrick Vice President eh Attachment cc: D.H.Williams, Jr.A.A.Blind-Bridgman J.R.Padgett G.Charnoff NFEM Section Chief A.B.Davis-Region III NRC Resident Inspector-Bridgman 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 Spent Fuel Reracking License Condition 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~4~day of P TARY PU LIC AtTh D.Hl L tTOTARY PUBLlC.STATE Oi ONl0 NY COMhllSSIDtl EXPIIIES~>~
~+
0 k S Dr.T.E.Murley-3-AEP:NRC:1146D bc: S.J.Brewer D.H.Malin/E.G.Lewis M.L.Horvath-Bridgman J.B.Shinnock W.G.Smith, Jr.J.F.Stang, NRC-Washington, D.C.AEP:NRC:1146D DC-N-6015.1