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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
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
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
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
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
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
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
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 7, 2009 LICENSEE:
DUKE ENERGY CAROLONAS, LLC (DUKE)
FACILITIES: CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA) AND MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE)
SUB~IECT:
SUMMARY
OF SEPTEMBER 1, 2009, CONFERENCE CALL WITH DUKE REGARDING RESPONSES TO GENERIC LEDER (GL) 2004-02 (TAC NOS.
MC4674, MC4675, MC4692 AND MC4693)
On September 1, 2009, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss Duke's most recent responses Requests for Additional Information (RAls) to GL 2004-02 for Catawba and McGuire. A list of attendees is provided in the Enclosure. The licensee's handouts are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML092730460.
The licensee described the latest response to GL 2004-02 for McGuire (ADAMS Accession No. ML092160597) in response to RAls sent by letter dated November 18, 2008 (ADAMS Accession No. ML083080350) and the latest response to GL 2004-02 for Catawba (ADAMS Accession No. ML092110120) in response to RAls sent by letter dated November 21, 2008 (ADAMS Accession No. ML083080373). The NRC staff discussed each RAI question with Duke.
The NRC staff and the licensee discussed the licensee's planned actions to address each RAI for Catawba sent by letter dated November 21, 2008 (ADAMS Accession No. ML083080373),
and each RAI for McGuire sent by letter dated November 18, 2008 (ADAMS Accession No. ML083080350). At the conclusion of the meeting, the NRC staff and the licensee agreed that the status of the RAls is as follows:
McGuire RAls 1, 2, 5, and 6; Catawba RAls 2, 3, and 5: These issues (zone of influence reductions) are being addressed generically by the Pressurized-Water Reactor Owners Group (PWROG). However, the licensee stated that it plans to retest strainer performance for Catawba without reference to the PWROG work and will do so for McGuire, as well, based on a future plant condition after planned removal of certain insulation from the containment. These issues will be discussed after the outlook for generic resolution is clearer and the tests are complete. The NRC staff noted that the choice not to reference the PWROG work, but rather to rely on more conservative, NRC staff-approved guidance, is a clear success path to resolution of remaining issues regarding the licensee's debris generation evaluation practices.
McGuire RAI 11, Catawba RAI 9: These issues are being addressed generically (erosion testing). The NRC staff noted that the licensee could consider several possible options for resolving this issue, including proposing a higher erosion percentage or demonstrating that strainer performance is not sensitive to the erosion percentage assumed.
Duke
- 2 McGuire RAI 31, Catawba RAI 29: These issues are being addressed generically by the PWROG (in-vessel downstream effects). The licensee stated that their evaluations show their plants to be bounded by the draft WCAP-16793, even if a substantially lower acceptance criterion is ultimately determined to be appropriate.
McGuire RAls 15-17 and 21, Catawba RAls 14-16 and 19: Licensee agreed to provide videos and photos the week of September 7; NRC staff will provide feedback to the licensee on them after review.
McGuire RAI 32, Catawba RAI 30: Licensee agreed to provide integrated head loss testing protocol for future planned testing to NRC staff for review and feedback. Date to be determined, but likely October 2009.
Regarding the other RAI responses, the NRC staff stated that the licensee's path forward appeared to be adequate (in some cases, limited additional information was needed beyond that provided in the draft responses provided to the NRC staff).
Members of the public were not in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1119, or jon.thompson@nrc.gov.
Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369, 50-370, 50-413 and 50-414
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATTENDEES SEPTEMBER 1, 2009, MEETING WITH DUKE CAROLINAS, LLC (DUKE)
CONFERENCE CALL TO DISCUSS LICENSEE RESPONSES TO GL 2004-02 WITH THE Duke K. Ashe M. Branham M. Brigman RHart T. Jackson R Lytton S. Manning J. Nolin P. Roberson G. Robison A. Tuckman U.S. NUCLEAR REGULATORY COMMISSION (NRC)
NRC J. Thompson M. Scott S. Smith P. Klein R Torres M. Yoder E. Wong C.Hott Enclosure
ML092670020 OFFICE DORULPL2-1/PM DORULPL2-1/LA DORULPL2-1/(A)BC DORULPL2-1/PM NAME JThompson MO'Brien JStang JThompson DATE 10/1/09 09/29/09 10/6109 10/7/09
