ML060720034
ML060720034 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 03/01/2006 |
From: | Jensen J Indiana Michigan Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
AEP:NRC:6691 | |
Download: ML060720034 (3) | |
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Category:Letter
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Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-337 Through Page D-387 ML12362A0672012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-276 Through Page D-336 ML12362A0662012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-220 Through Page D-275 ML12362A0602012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-621 Through C-697 ML12362A0622012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-777 Through Appendix D, Page ML12362A0632012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-54 Through Page D-114 ML12362A0642012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-115 Through Page D-175 ML12362A0652012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-176 Through Page D-219 AEP-NRC-2012-83, Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3.2012-10-31031 October 2012 Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3. AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation2012-06-11011 June 2012 Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation AEP-NRC-2009-25, Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis2009-03-30030 March 2009 Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis ML0807400532008-02-29029 February 2008 Response to Request for Additional Information Regarding Reanalysis of Small Break Loss-Of-Coolant Accident ML0807703952008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 1, References, Through Attachment 3, Supplemental Response to GL 2004-02 and Request for Additional Information. ML0807200622008-02-29029 February 2008 License Amendment Request to Revise Ice Condenser Licensing Basis ML0807703962008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 3, I&M Response to Information Item 3.f.4, to NRC Information Item 3 - Conclusions. ML0807704002008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 4, Figure A4-1, General Arrangement of Recirculation Sump to Attachment 5, Figure A5-40, Scotch 77 Fire Retardant Tape Test 1 Pre-Test Picture. ML0807704042008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 5, Figure A5-41, Scotch 77 Fire Retardant Tape Test 1 Post-Test Picture to Attachment 7, Regulatory Commitments. 2024-07-25 |
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Indiana Michigan Power INDIANA Cook Nuclear Plant One Cook Place MICHIGAN Bridgman, Ml 49106 POWER' AEPcom A unit of American Electric Power March 1, 2006 AEP:NRC:6691 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 STEAM GENERATOR TUBE INSPECTION REPORT Technical Specification 5.6.7 of Appendix A to the Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Operating Licenses requires that complete results of the steam generator tube inservice inspection be submitted to the Nuclear Regulatory Commission for the inspection that was completed in the previous calendar year. Consistent with this requirement, a copy of the 2005 Steam Generator Tube Inspection Results are attached.
This letter contains no new commitments. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Supervisor, at (269) 466-2649.
Sincerely, Joseph N. Jensen Site Vice President DB/rdw Attachment
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U. S. Nuclear Regulatory Commission AEP:NRC:6691 Page 2 c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachment J. T. King, MPSC, w/o attachment MDEQ - WHMDJRPMWS, w/o attachment NRC Resident Inspector P. S. Tam, NRC Washington, DC
ATTACHMENT TO AEP:NRC:6691 2005 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT Unit 1:
There were no inservice eddy current inspections conducted on the Unit 1 steam generator tubing in 2005. The last inspection occurred in 2003 as reported in the 2003 annual report submittal, dated March 1, 2004. The Unit 1 steam generator inspection interval is governed by the provisions of Technical Specification 5.5.7. This specification allows an inspection interval of up to 40 calendar months, once two consecutive inspections have yielded degradation category C-1 results. Based upon the results of the 2003 inspection and the previous inspection which was conducted in 2002, the Unit 1 steam generators will next be inspected in the fall of 2006.
Unit 2:
There were no inservice eddy current inspections conducted on the Unit 2 steam generator tubing in 2005. The last inspection occurred in 2004 as reported in the 2004 annual report submittal, dated February 25, 2005. Based upon the favorable results of that inspection and in accordance with the provisions of Technical Specification 5.5.7, similar to that noted above, the Unit 2 steam generators continue to be on an inspection interval of up to 40 calendar months. As such, the Unit 2 steam generators will next be inspected in the fall of 2007.