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MONTHYEARML0600304592005-12-19019 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 Donald C. Cook, Unit 1 & 2, 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 ML0618602512006-06-27027 June 2006 Donald C. Cook, Unit 1, Request for Extension of Completion Date for Unit 1 Actions in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Rea Project stage: Request 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 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 Licensee'S Supplemental Responses to GL 2004-02 Project stage: Other 2006-07-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
.rul.y 27, 2010 Mr. Lawrence J. Weber 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 (DCCNP 1&2) -NRC STAFF COMMENTS ON LICENSEE'S SUPPLEMENTAL RESPONSES TO GENERIC LETTER 2004-02 (TAC NOS. MC4679 AND MC4680)
Dear Mr. Weber:
By letters dated February 29, 2008; August 29, 2008; and May 26, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML080770394, ML082520025, and ML101540527); Indiana Michigan Power Company (I&M) submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design-Basis Accidents at Pressurized-Water Reactors," for DCCNP 1&2. The Nuclear Regulatory Commission (NRC) staff has reviewed I&M's submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the NRC's "Content Guide for Generic Letter 2004-02 Supplemental Responses" (ADAMS Accession No. ML073110389). The review process also included a separate review of I&M's submittals informed by input from the subject matter experts that focused on whether I&M has demonstrated overall that I&M's corrective actions for GL 2004-02 are adequate.
The NRC staff has no further questions for DCCNP 1&2 at this time regarding completion of corrective actions for GL 2004-02. This conclusion is based on the NRC staff's evaluation of I&M's submittals, with emphasis on I&M's response to an NRC staff request for additional information dated June 18, 2009 (ADAMS Accession No. ML091490421).
As you may be aware, the NRC staff has not yet issued a final safety evaluation (SE) on WCAP 16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." The NRC staff has reviewed the GL 2004-02 submittals for DCCNP 1&2 and determined that I&M currently intends to rely on the conclusions reached in WCAP-16793-NP. Assuming disposition of WCAP-16793-NP results in NRC staff issuance of an SE, the NRC intends to send a letter requesting that I&M confirm whether it still intends to rely on the conclusions reached in WCAP-16793-NP for DCCNP 1&2. In addition, the letter will likely request a response within 60 days describing: (1) the means I&M used to determine the amount of debris that bypasses the emergency core cooling system strainer; (2) the fiber loading expected per fuel assembly for the cold-leg and hot-leg break scenarios based on information available as of the date of the letter; (3) the available head loss margins with bases for the cold-leg and hot-leg break scenarios using the WCAP-16793-NP acceptance criteria; and (4) I&M's planned actions for DCCNP 1&2 should it exceed an acceptance criterion.
L. J. Weber -2 The NRC staff will notify I&M of the expected timeline for any needed actions at the time the SE is issued, or will notify I&M of expectations for additional licensee actions should a SE not be issued. We are not requesting any information from I&M on this subject at this time.
If you have any further questions on this matter, please contact me at 301-415-1451.
~x Peter S. Tam, 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
ML101960128 OFFICE NRRlLPL3-1/PM NRRlLPL3-1/LA NRRlSSIB/BC NRRlLPL3-1/BC NAME PTam THarris for BTully MScott RPascarelli DATE 07/16/10 07/16/10 07/26/10 07/27/10