Letter Sequence RAI |
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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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Similar Documents at Cook |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 31, 2009 Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - MODIFICATION OF A REQUEST FOR ADDITIONAL INFORMATION (RAI) ASSOCIATED WITH SUPPLEMENTAL RESPONSES TO GENERIC LETTER (GL) 2004-02 (TAC NOS. MC4679 AND MC4680)
Dear Mr. Jensen:
On August 26, 2009, a public meeting via conference call (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092250002) was held between staff of the U.S.
Nuclear Regulatory Commission (NRC) and the Donald C. Cook Nuclear Plant. The meeting was held to discuss RAls previously transmitted in a June 18, 2009, letter (ADAMS Accession No. ML091490421) associated with your staffs supplemental responses to GL 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors."
During the meeting, it was determined that RAI Question 21 required modification to provide additional clarification. The NRC staff modified the RAI as follows:
Please provide justification that the flow rate assumed at the main strainer during chemical effects testing was bounding with respect to the condition that could occur in the plant. Because of the amount of debris assumed at the main strainer, the corresponding flow assumed during testing may have been lower than could occur in the plant. A lower flow rate can affect the head loss value attained during testing and thus affect the bump up factor determined by the chemical effects head loss test.
Mr. Joe Waters and Mr. Paul Leonard of your staff stated that they understood the intent of the proposed RAI and agreed that it could be formally issued.
Please respond to this RAI as part of your response to the RAls in the June 18, 2009, letter.
J.Jensen
- 2 Feel free to contact me at (301) 415-3049 if you need further clarification or have any comments.
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 cc: Distribution via Listserv
ML092400075 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA t\\lRR/SSIB/BC NRR/LPL3-1/BC NAME TBeltz THarris MScott LJames DATE 08/28/09 08/28/09 08/28/09 08/31/09
