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MONTHYEARML0603703472006-02-0909 February 2006 RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0603704272006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors (TAC MC4692 & MC4693) Project stage: RAI ML0608904212006-03-0101 March 2006 Final Safety Evaluation Report Related to the License Renewal of Brunswick Steam Electric, Units 1 and 2 Project stage: Approval ML0733103812007-11-21021 November 2007 Notification of Potential Part 21 Report Welding of Safety Related Components Project stage: Request ML0734604102007-12-0707 December 2007 Request for Extension of Completion Dates for Corrective Actions Required by NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Project stage: Request ML0736102262007-12-28028 December 2007 Notice of Meeting with Duke Power Company to Discuss the Relief Request Dated 10/26/2006 That Proposes the Use of Polyethylene Material in Nuclear Safety-Related Piping Applications Project stage: Meeting ML0807301312008-02-28028 February 2008 Response to Request for Additional Information on GL-04-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI ML0806505592008-02-29029 February 2008 Response to Request for Additional Information on GL-04-002 Project stage: Response to RAI ML0812804882008-04-30030 April 2008 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0812700912008-04-30030 April 2008 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0830803502008-11-18018 November 2008 Request for Additional Information (RAI) Regarding Supplemental Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Project stage: RAI ML0830803732008-11-21021 November 2008 RAI, Supplemental Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: RAI ML0921101202009-07-28028 July 2009 Update on the Status of the November 21, 2008 Request for Additional Information (RAI) and Additional Testing Pursuant to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation Project stage: Request ML0921605972009-07-28028 July 2009 Update on Status of 11/18/08 Request for Additional Information & Additional Testing Pursuant to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Request ML0922908922009-08-18018 August 2009 Notice of Conference Call with Duke Energy Carolinas, LLC (Duke), Regarding Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) and McGuire Nuclear Station Units 1 and 2 Project stage: Other ML0927304602009-10-0707 October 2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02. Meeting Handouts Project stage: Request ML0926700202009-10-0707 October 2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02 Project stage: Other ML1012604632010-05-0707 May 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke) to Discuss Dukes Responses to Generic Letter 2004-02 at Catawba 1 and 2 and McGuire 1 and 2 Project stage: Other ML1028701002010-09-30030 September 2010 Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water.. Project stage: Draft Response to RAI ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, Project stage: Other ML1030810242010-11-10010 November 2010 Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693) Project stage: Meeting ML13141A4032013-05-0808 May 2013 Closure Options for Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter Project stage: Other ML13231A1132013-07-31031 July 2013 Closure Option 1 Response to In-Vessel Downstream Effects Request for Additional Information for Generic Safety Issue (GSI) 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution Project stage: Request ML13213A2842013-07-31031 July 2013 Closure Option 1 Response to In-Vessel Downstream Effects Request for Additional Information for Generic Safety Issue (GSI) 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance............. Project stage: Request ML13345B3482013-12-31031 December 2013 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML14090A4442014-04-24024 April 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz Project stage: Request 2009-10-07
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Duke BRUCE H HAMILTON Ener Vice President PcEWIry McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy. corn July 28, 2009 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke)
McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Update on the Status of the November 18, 2008 Request for Additional Information (RAI) and Additional Testing for McGuire Units 1 and 2 Pursuant to NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" Pursuant to the November 18, 2008 RAI letter from the Nuclear Regulatory Commission (NRC) and the February 16, 2009 response from Duke, Duke is providing an update on its RAI response plan and confirmatory conventional debris head loss testing (subsequently referred to herein as "testing") progress.
Since February 2009, McGuire has continued to make progress on development of responses to the RAI questions using insights from teleconferences with the NRC. A teleconference was held on May 20, 2009 to discuss testing protocols.
A second teleconference was held on June 17, 2009 to discuss chemical effects.
The testing at Wyle Laboratories was completed on June 25, 2009. This testing incorporated the guidance of the document titled "NRC Staff Review Guidance Regarding Generic Letter 2004-02 Closure in the Area of Strainer Head Loss and Vortexing" dated March 2008, as well as, lessons learned from earlier testing and inputs from the NRC. The results from this testing are being finalized and will be incorporated into the RAI responses presently under development.
This testing modeled the current bounding fiber insulation configuration, assuming a 7D jacketed fiber Zone of Influence (ZOI) value as reported in the GL 2004-02 supplemental responses dated February 28, 2008 and April 30, 2008.
McGuire recognizes that some regulatory uncertainty remains in invoking the wWW. duke-energy. comr
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U. S. Nuclear Regulatory Commission July 28, 2009 Page 2 findings of WCAP-16710-P, "Jet Impingement Testing to Determine the ZOI of Min-K and NUKON Insulation for Wolf Creek and Callaway Nuclear Operating Plants." McGuire continues to participate with the industry in resolving these regulatory uncertainties. The RAI questions concerning this issue and others will be discussed with the NRC as described below.
On June 23, 2009, the NRC conducted a public meeting to provide the status and path forward on Generic Safety Issue (GSI) 191. Duke will follow the process of conducting telecoms with the NRC, as discussed in the June 2 3 rd meeting, prior to submitting the responses to the RAIs. Duke is currently working with the NRC Project Manager to plan these series of telecoms, including a follow-up to the June 17, 2009 teleconference associated with the subject of chemical effects.
Questions regarding this update should be directed to P. T. Vu at (980) 875-4302.
Very truly yours, Bruce H. Hamilton xc:
L. A. Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission 61 Forsyth Street,. S.W., Suite 23T85 Atlanta, GA 30303-8931 J. H. Thompson (addressee only)
NRC Project Manager (MNS & CNS)
U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 08G9A Rockville, MD 20852-2738 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station