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MONTHYEARML0507500692005-03-0404 March 2005 90 Day Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Project stage: Request ML0525105122005-08-31031 August 2005 Response to NRC Generic Letter 2004-02 - Information Requested by 09/01/05 Project stage: Request ML0600304592005-12-19019 December 2005 Nuclear Regulatory Commission Generic Letter 2004-02 Revision of Commitments Project stage: Request ML0603705472006-02-0909 February 2006 Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: Other ML0618602572006-06-27027 June 2006 Update to Response to Nuclear Regulatory Commission Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0620207682006-07-28028 July 2006 Extension of Completion Date for Actions in Response to Generic Letter 2004-02 Project stage: Other ML0710603252007-04-17017 April 2007 Notice of Meeting with D. C. Cook Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: Meeting ML0712202582007-05-23023 May 2007 Summary of Meeting with Indiana Michigan Power Company, LLC (I&M), on Status and Issues Related to Dccnp Implementation of Generic Letter 2004-02 Project stage: Meeting 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 Project stage: Supplement 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 Project stage: Request AEP-NRC-2008-17, Final Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors and Associated Request for Additional Information2008-08-29029 August 2008 Final Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors and Associated Request for Additional Information Project stage: Request ML0825200272008-08-29029 August 2008 Attachment 6 to AEP-NRC-2008-17, Cold Galvanizing Compound Testing Photographs Project stage: Request ML0907708662009-03-18018 March 2009 Draft RAIs Supplemental Responses to GL 2004-02 Project stage: Draft RAI ML0907708432009-03-18018 March 2009 Transmitting Draft RAIs Supplemental Responses to GL 2004-02 Project stage: Draft RAI ML0908607422009-04-0303 April 2009 Notice of Meeting with the Donald C. Cook Nuclear Plant to Discuss Draft Requests for Additional Information Associated with Supplemental Response to GL 2004-02 Project stage: Draft RAI ML0911902562009-05-13013 May 2009 Summary of Category 1 Meeting with the Donald C. Cook Nuclear Plant to Discuss Draft Requests for Additional Information Associated with GL 2004-02 Project stage: Draft RAI ML0914904212009-06-18018 June 2009 Transmittal of Final Request for Additional Information Supplemental Responses to Generic Letter 2004-02 Project stage: RAI ML0918801642009-07-0808 July 2009 Notice of Meeting, (Conference Call), with Indiana Michigan Power Company to Discuss the NRC Request for Additional Information Associated with Generic Letter 2004-02 Project stage: RAI ML0920200672009-07-24024 July 2009 Notice of Conference Call with Indiana Michigan Power Company to Discuss the Proposed Responses to Requests for Additional Information Associated with Generic Letter 2004-02 for the Donald C. Cook Nuclear Plant Project stage: RAI ML0920202652009-07-31031 July 2009 Summary of Conference Call with Indiana Michigan Power Company to Discuss Requests for Additional Information Associated with Generic Letter 2004-02 Project stage: RAI ML0922500022009-08-13013 August 2009 Notice of Conference Call with Indiana Michigan Power Company to Discuss the Proposed Responses to Requests for Additional Information Associated with Generic Letter 2004-02 for the Donald C. Cook Nuclear Plant Project stage: RAI ML0923103092009-08-25025 August 2009 Summary of Category 1 Public Meeting Held Via Conference Call with Indiana Michigan Power Company to Discuss Draft Responses to Requests for Additional Information Associated with GL-04-002 Project stage: Draft RAI ML0912003642009-08-26026 August 2009 License Handouts Provided During Category 1 Meeting with the Donald C. Cook Nuclear Plant to Discuss Draft Request for Additional Information Associated with GL 2004-02 Project stage: Draft RAI ML0924000752009-08-31031 August 2009 Modification of a Request for Additional Information Associated with Supplemental Responses to Generic Letter 2004-02 (MC4679 and MC4680) Project stage: RAI ML0924405532009-09-0909 September 2009 Notice of Meeting with Indiana Michigan Power Company to Discuss Proposed Responses to Requests for Additional Information Associated with Generic Letter 2004-02 for the Donald C. Cook Nuclear Plant, Units 1 & 2 Project stage: RAI ML0924002992009-09-16016 September 2009 Summary of Meeting with Indiana Michigan Power Company to Discuss Proposed Responses to Requests for Additional Information Associated with Generic Letter 2004-02 for the Donald C. Cook Nuclear Plant, Units 1 and 2 Project stage: RAI ML0932003122009-11-20020 November 2009 Summary of Category 1 Public Meeting with Indiana Michigan Power Company and NRC Staff to Discuss Responses to Generic Letter 2004-02 Requests for Additional Information Project stage: RAI ML1012504122010-05-13013 May 2010 Summary of Category I Public Meeting with Indiana Michigan Power Company to Discuss Draft Responses to Requests for Additional Information Associated with Generic Letter 2004-02 Project stage: Draft RAI AEP-NRC-2010-39, Donald Cook, Units 1 & 2, Updated Final Response to Generic Letter 2004-02 and a June 2009 Request for Additional Information2010-05-26026 May 2010 Donald Cook, Units 1 & 2, Updated Final Response to Generic Letter 2004-02 and a June 2009 Request for Additional Information Project stage: Request ML1019601282010-07-27027 July 2010 Comments on the Licensees Supplemental Responses to GL 2004-02 Project stage: Other 2009-05-13
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11ý Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place P/IWER Bridgman, Ml 49106 AEPcom A unit of American Electric Power February 29, 2008 AEP:NRC:8054-02 10 CFR 50.54(f)
Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852 Donald C. Cook Nuclear Plant Units 1 and 2 SUPPLEMENTAL RESPONSE TO NUCLEAR REGULATORY COMMISSION GENERIC LETTER 2004-02:
POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS This letter provides I&M's supplemental response to GL 2004-02. The documents referenced in this letter and its attachments are identified in Attachment 1. The abbreviations, acronyms, and symbols are defined in Attachment 2.
By GL 2004-02 (Reference 1), the NRC identified concerns regarding the potential for post-accident debris to impede or prevent the recirculation functions of emergency core cooling and containment spray systems at PWRs. The NRC requested that PWR licensees mechanistically evaluate this potential for their plants and identify corrective measures that would be taken.
By Reference 2, I&M provided initial information regarding the methodology and containment walkdowns that would be used for the requested mechanistic evaluations at CNP, and the planned completion date for these activities. By Reference 3, I&M provided a comprehensive description of the in-progress and planned actions to address the concerns identified in GL 2004-02, including plant modifications, implementation schedule, mechanistic evaluation methodology, emergency core cooling system head margin, sump strainer areas, postulated head loss, potential flow path choke points, downstream effects, sump strainer structural considerations, licensing basis changes, and programmatic controls. By Reference 4, I&M provided revised commitments and updated a portion of the information previously provided by Reference 3.
By Reference 5, the NRC requested additional information regarding the responses provided in References 2, 3, and 4.
By Reference 6, the NRC authorized an alternative approach that permitted an extended due date for the requested additional information.
By Reference 7, I&M updated the information provided in References 2, 3, and 4, and provided a portion of the additional information requested by Reference 5.
U. S. Nuclear Regulatory Commission AEP:NRC:8054-02 Page 2 By Reference 8, I&M committed to provide the remainder of the requested additional information in an update to the GL 2004-02 response no later than December 31, 2007. This commitment was consistent with the NRC expectation, stated in Reference 150, that PWR licensees submit supplemental responses by December 31, 2007.
By Reference 151, the NRC authorized an extension to February 29, 2008, for submittal of supplemental responses. to this letter provides the supplemental response to GL 2004-02 for CNP.
The information in this supplement supersedes that provided in References 2, 3, 4, 7, and 8. provides general figures. provides jet impingement testing photographs. Attachment 6 lists each RAI question from Reference 5 and provides a reference to the section of Attachment 3 in which the requested information is provided, and/or provides other information to address the question. Attachment 7 provides the new regulatory commitments made in this letter in tabular form.
Should you have any questions, please contact Mr. James M. Petro, Jr., Regulatory Affairs Manager, at (269) 466-2491.
Sin ce r Iy, 4M~rk'A. Pe e Site Vice President JRW/rdw Attachments:
- 1.
References
- 2.
Abbreviations and Acronyms
- 3.
Supplemental Response to GL 2004-02 and Request for Additional Information
- 4.
General Figures
- 5.
Jet Impingement Testing Photographs
- 6.
Response to NRC Request for Additional Information
- 7.
Regulatory Commitments c:
J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne (w/o attachments)
J. T. King - MPSC (w/o attachments)
MDEQ - WHMD/RPMWS (w/o attachments)
NRC Resident Inspector P. S. Tam - NRC Washington, DC
U. S. Nuclear Regulatory Commission Page 3 AEP:NRC:8054-02 AFFIRMATION I, Mark A. Peifer, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS
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