Letter Sequence RAI |
|---|
|
|
MONTHYEARML0630602512003-10-15015 October 2003
WB1-DWD-015A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1.
Project stage: Other
ML0629105222003-11-0505 November 2003
WB1-DWD-024A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1.
Project stage: Other
ML0629105132004-08-24024 August 2004
TVAW001-RPT-001, Rev. 0, Report on Watts Bar, Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues.
Project stage: Other
ML0515205802005-06-0303 June 2005
Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors
Project stage: RAI
ML0603704802006-02-10010 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
Project stage: RAI
ML0603800822006-02-10010 February 2006
RAI, Response to GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors
Project stage: RAI
ML0610203132006-04-11011 April 2006
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0610402192006-04-11011 April 2006
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0610101802006-05-10010 May 2006
Request for Additional Info the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modification
Project stage: Acceptance Review
ML0621204722006-07-0303 July 2006
Watts Bar Nuclear Plant (WBN) Unit 1 - Generic Letter 2004-02 - Request for Additional Information Regarding the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modifications
Project stage: Request
ML0629105082006-07-0303 July 2006
Generic Letter 2004-02 - Request for Additional Information Regarding NRC Staff Audit on Containment Sump Modifications
Project stage: Request
ML0621800772006-08-11011 August 2006
Proprietary Letter, Request for Withholding Information from Public Disclosure, Containment Sump Modifications
Project stage: Withholding Request Acceptance
ML0636204112006-12-21021 December 2006
Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Supplemental Response
Project stage: Supplement
ML0721501092007-08-0101 August 2007
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0727604492007-10-0202 October 2007
Watts Bar Nuclear Plant (WBN) Unit 1, Generic Letter 2004-02, Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0733703172007-11-28028 November 2007
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) - Notice of Completion
Project stage: Other
ML0733801522007-12-0606 December 2007
Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Extension Request Evaluation
Project stage: Other
ML0806402052008-02-29029 February 2008
Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors (PWR) - Notice of Completion
Project stage: Supplement
ML0811201592008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5343-S01, Rev. 0, Attachment D, Page 374 of 575 Through Calculation No. PCI-5343-S02, Rev 0, Attachment B, Page 100 of 631
Project stage: Supplement
ML0810905032008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachments a and B, Page 384 of 680
Project stage: Supplement
ML0810905022008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Figure 4.25 - Case 3 Through Calculation PCI-5464-S01, Page 107
Project stage: Supplement
ML0810905002008-03-31031 March 2008
Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Notice of Completion
Project stage: Supplement
ML0810905012008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Pages E1-1 Through Figure 4.24 - Case 3
Project stage: Supplement
ML0810905082008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S02, Rev. 0, Attachment B Page 101 Through End
Project stage: Supplement
ML0810905052008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachment B, Page 385 Through 680
Project stage: Supplement
ML0832308232008-11-25025 November 2008
Request for Additional Information Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors (Tac Nos. MC4717 and MC4718)
Project stage: RAI
ML0833700332008-12-0303 December 2008
Request for Additional Information Regarding Generic Letter 2004-02. Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors (Tac No. MC4730)
Project stage: RAI
ML0905408572009-02-23023 February 2009
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0907208692009-02-25025 February 2009
Calculation, ALION-CAL-TVA-2739-03, Rev. 4, Watts Bar Reactor Building GSI-191 Debris Generation Calculation.
Project stage: Other
ML0907208682009-03-0303 March 2009
Response to Request for Additional Information Regarding Generic Letter 2004-02,.Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Response to RAI
ML0926502602009-09-29029 September 2009
RAI, Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0936502182009-12-23023 December 2009
GL 2004-02 Final RAI Responses Due Date
Project stage: RAI
ML1000601162010-01-0707 January 2010
Change of Response Date Regarding Request for Additional Information for Generic Letter 2004-02 Potential Impact of Debris Blockage During Design-Basis Accidents at Pressurized
Project stage: RAI
ML1015905562010-06-0909 June 2010
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
ML1016600442010-06-17017 June 2010
Summary of Conference Call with TVA on Proposed Response to Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML1107000312011-04-15015 April 2011
Notice of Meeting with Tennessee Valley Authority to Discuss Responses to NRC Requests for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pre
Project stage: RAI
ML11152A1702011-05-12012 May 2011
05/12/2011-Meeting Slides from Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02
Project stage: Response to RAI
ML11154A0932011-06-28028 June 2011
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
ML11152A1632011-06-28028 June 2011
Summary of Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML11230B2502011-11-0303 November 2011
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
CNL-14-114, Resolution of Generic Safety Issue (GSI)-1912014-06-27027 June 2014
Resolution of Generic Safety Issue (GSI)-191
Project stage: Request
ML14283A5132014-11-17017 November 2014
NRC Staff Review Documentation Provided by TVA for the Sequoyah Nuclear Plant, Units 1 and 2 Concerning Resolution of GL2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Wate
Project stage: Approval
ML14283A5262014-11-17017 November 2014
Closeout of GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor
Project stage: Other
CNL-15-009, Resolution of Generic Safety Issue 1912015-04-17017 April 2015
Resolution of Generic Safety Issue 191
Project stage: Request
ML15191A1832015-09-17017 September 2015
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
CNL-15-252, License Amendment Request and Request for Deviation from 10 CFR 50, Appendix R in Support of Closure of Generic Safety Issue 191 (WBN-TS-16-01)2016-02-23023 February 2016
License Amendment Request and Request for Deviation from 10 CFR 50, Appendix R in Support of Closure of Generic Safety Issue 191 (WBN-TS-16-01)
Project stage: Request
2008-03-31
[Table View] |
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Category:Meeting Summary
MONTHYEARML24008A1592024-01-18018 January 2024
Summary of December 13, 2023, Meeting with Tennessee Valley Authority Regarding a Proposed Change to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML23304A0682023-11-0606 November 2023
Summary of October 24, 2023, Public Mtg W/Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, and Sequoyah Nuclear Plant, Units 1 and 2 to Revise Function 5, Turbine Trip and F
ML23265A1512023-09-28028 September 2023
Summary of September 12, 2023, Partially Closed Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request
ML23198A3102023-07-20020 July 2023
July 10, 2023, Summary of Public Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2
ML23142A2132023-05-22022 May 2023
Public Meeting Summary - 2022 Annual Assessment Meetings for Browns Ferry, Sequoyah and Watts Bar Nuclear Plants
ML23068A1532023-03-16016 March 2023
Summary of February 22, 2023, Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request to Increase Allowable Number of Tritium Producing Burnable Absorber Rods at Watts Bar Nuclear Plant, Units 1 and 2
ML23055A4562023-03-0909 March 2023
Summary of February 15, 2023, Public Meeting with Tennessee Valley Authority Regarding Proposed Expedited License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2
ML22329A1382022-12-0505 December 2022
Summary of Meeting with Tennessee Valley Authority Related to Planned Alternative Request WBN-2-ISI-01 for Watts Bar Nuclear Plant, Unit 2
ML22312A3522022-12-0101 December 2022
Revised - Summary of Regulatory Audit for Alternative Request RV-02
ML22207B8302022-07-28028 July 2022
Summary of July 20, 2022, Observation Public Meeting with the Tennessee Valley Authority to Discuss Planned Alternative Request RP-12 to ASME OM Code Testing for the 1B-B Centrifugal Charging Pump at Sequoyah Nuclear Plant, Unit 1
ML22168A1642022-06-27027 June 2022
Summary of June 9, 2022, Meeting with TVA Regarding a Proposed License Amendment Request Related to Low Temperature Overpressure System and Cold Overpressure Mitigation System for Sequoyah and Watts Bar Nuclear Plants
ML22109A0042022-04-20020 April 2022
Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Alternative Request Related to Testing of the Motor-Driven Auxiliary Feedwater Pumps at Sequoyah and Watts Bar Nuclear Plants
ML22104A2252022-04-20020 April 2022
Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Exemption Request for Watts Bar Nuclear Plant, Unit 2
ML22108A1842022-04-18018 April 2022
TVA 2021 Annual Assessment Public Meeting Summary
ML22048B7852022-03-0202 March 2022
Summary of February 16, 2022, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a Request for an Alternative to Requirements for Addressing Pressure Isolation Valve Leakage
ML22042B3262022-02-14014 February 2022
Summary of February 8, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed License Amendment Request to Revise the Allowable Value for Trip of Turbine-Driven Main Feedwater Pump at Watts Bar Nuclear Plant, Unit 1
ML22025A3112022-02-0909 February 2022
Summary of January 19, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed Schedule for Development of a License Amendment Request for Increased Tritium Production
ML21349A3642022-01-0404 January 2022
Summary of December 14, 2021, Teleconference with Tennessee Valley Authority Regarding a Proposed Change to the Capsule Withdrawal Schedule for Watts Bar Nuclear Plant, Unit 2
ML21313A3482021-11-18018 November 2021
Summary of Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a License Amendment Request Regarding Seismic and Fire Probabilistic Risk Assessment (PRA) Modifications to 10 CFR 50.69
ML21279A0902021-11-0303 November 2021
Summary of Conference Calls Regarding the Fall 2021, Mid-Cycle Steam Generator Tube Inspections
ML21291A0092021-11-0303 November 2021
Tennessee Valley Authority Fleet - Summary of October 13, 2021, Teleconference with Tennessee Valley Authority to Discuss Planned License Amendment Requests Related to the Emergency Action Level Scheme
ML21265A5142021-10-12012 October 2021
Summary of September 15, 2021, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a License Amendment Request Regarding Elimination of the High Negative Flux Rate Trip
ML21245A4252021-09-15015 September 2021
Summary of August 19, 2021, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request Related to the Watts Bar Nuclear Plant, Units 1 and 2
ML21253A0872021-09-15015 September 2021
Summary of August 19, 2021, Partially Closed Meeting with Tennessee Valley Authority to Discuss Mid-Cycle Outage Contingencies for Watts Bar Nuclear Plant, Unit 2
ML21218A1472021-08-11011 August 2021
August 5, 2021 N-769 Relief Pre-Submittal Meeting Summary
ML21165A1482021-06-30030 June 2021
Summary of Closed Meeting with Tennessee Valley Authority to Discuss Planned Requests for Exemption from Certain Requirements of 10 CFR Part 37
ML21152A1252021-06-0202 June 2021
Summary of Verbal Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump
ML21137A0022021-05-17017 May 2021
Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plants, Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391, Meeting Number 20210392
ML21120A2192021-05-0404 May 2021
April 28,2021, Summary of Meeting with Tennessee Valley Authority Related to a Planned License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, to Remove from Technical Specifications Redundant Units of Measurement for Control
ML21112A3262021-04-30030 April 2021
Summary of April 21, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2
ML21099A2072021-04-13013 April 2021
Summary of April 7, 2021, Meeting with Tennessee Valley Authority Related to a Planned Relief Request from ASME Code Testing Requirements
ML21067A2132021-03-23023 March 2021
Summary of March 2, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned Alternative Request
ML21060B0532021-03-0303 March 2021
Summary of February 11, 2021, Meeting with Tennessee Valley Authority Related to a Planned License Amendment Request for Watts Bar Nuclear Plant, Unit 2, to Apply a Temperature Adjusted Steam Generator Tube Flaw Growth Rate Methodology
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Summary of November 17, 2020, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request for Technical Specification 5.9.9, Steam Generator Tube Inspection Report
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2024-01-18
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 17, 2010 Tennessee Valley Authority (TVA)
FACILITY: Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1
SUBJECT:
SUMMARY
OF JUNE 10,2010, CONFERENCE CALL WITH TVA ON THEIR PROPOSED RESPONSE TO A REOUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 2004-02 (TAC NOS. MC4717, MC4718, AND MC4730)
On June 10, 2010, a Category 1 public conference call was held among the Nuclear Regulatory Commission (NRC) staff and representatives of Tennessee Valley Authority (TVA or the licensee) and TVA's contractors, AREVA, PCI and Alden Research Laboratory. A list of call participants is provided as Enclosure 1. The purpose of the call was to discuss TVA's proposed responses to the NRC staff's requests for additional information (RAls) dated October 14, 2009, for Sequoyah Nuclear Plant (SON), Units 1 and 2, and September 29, 2009, for Watts Bar Nuclear Plant (WBN), Unit 1 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML092780335 and ML092650260 respectively). The NRC's RAI letters were in response to TVA's submittals for NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," for SON, Units 1 and 2, and WBN, Unit 1. The NRC staff has been conducting calls with all licensees who are responding to RAls on GL 2004-02 with the intent of providing NRC guidance in order to reduce the need for additional rounds of RAls.
The NRC's RAls requested the licensee to be prepared to discuss its proposed responses with the NRC staff prior to formal submittal. The licensee provided draft responses on June 3, 2010 (ADAMS Accession No. ML101590409) to the NRC staff's RAls and the NRC staff discussed each proposed response in detail with the licensee and its contractors. Enclosure 2 summarizes the discussion of each proposed response.
The licensee will provide its final RAI responses in a letter to the NRC. Please direct any inquiries to me at 301-415-1564, or by email to siva.lingam@nrc.gov.
~ p. ~t----
Siva P. Lingam, Project Manager Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, and 50-390
Enclosures:
- 1. List of Participants
- 2. Summary of the Conference Call cc w/encls: Distribution via Listserv
List of Participants U.S. Nuclear Regulatory Commission (NRC) JUNE10. 2010 Conference Call with Tennessee Valley Authority (TVA),
AREVA, PCI. and Alden Research Laboratory Regarding Generic Letter 2004-02 Request For Additional Information Draft Responses NRC Michael Scott John Lehning Stephen Smith Matthew Yoder Siva Lingam TVA Rod Cook Kevin Casey Doug Pollock Benjamin Kennedy Cynthia Maples-Abidi David Lafever Mark Ray Kenneth Spates AREVA Donald LeFrancois Erik Eller Daniel McKenzie Brian Dannaker PCI Chris Kudla Alden Research Laboratory Ludwig Haber Enclosure 1
Summary of the Conference Call U.S. Nuclear Regulatory Commission JUNE10, 2010 Conference Call with Tennessee Valley Authority, AREVA, PCI, and Alden Research Laboratory Regarding Generic Letter 2004-02 Request For Additional Information (RAn Draft Responses Sequoyah Nuclear Plant (SON), Units 1 and 2:
RAI1A: The licensee will clarify second bullet under draft to match test protocol wording that protocol will generally eliminate settling. With that change, this response will be acceptable.
RAI1B: The licensee will change reference in second bullet to NUREG/CR-6808. With that change, this response will be acceptable.
RAI1C: The licensee will state that fines will not be mechanically separated from small pieces of fibrous debris. With that change, this response will be acceptable.
RAI1D: Response acceptable as is.
RAI1E: Response acceptable as is.
RAI1F: Nuclear Regulatory Commission (NRC) staff does not accept previous testing as basis for nontransportability of miscellaneous debris. The licensee will state it plans to credit nontransportability of miscellaneous debris through additional transport testing with individual types of debris to determine whether incipient transport occurs. The licensee will state that the test velocity will be representative of the flow steam velocities at which the miscellaneous debris would transport to the strainer (e. g., based on plant computational fluid dynamics simulation). With the above changes, the response is acceptable.
RAI1G: The licensee will add discussion of additional vortex suppression features downstream of strainer and upstream of intake. To address flashing, the licensee will compare strainer head loss against subcooling margin.
RAI4: The licensee will remove reference to 1/8" fiber additions. With this change, this response will be acceptable.
RAI5: Response acceptable as is.
RAI6: Response acceptable contingent on acceptable response to RAI 1G.
RAI9: Response acceptable as is.
Enclosure 2
-2 Watts Bar Nuclear Plant (WBN), Unit 1:
RAI1: The licensee will state zone of influence for Min-K and 3M fire barrier is per NRC staff safety evaluation on Nuclear Energy Institute 04-07, 28.60. The licensee will add this to the response, which will then be acceptable.
RAI3: Fibrous Debris Preparation and introduction with respect to Prototypical Sizing The licensee will make same change as for SON, Units 1 and 2 response to RAI1B.
Flume Velocity and turbulence - Response acceptable as is.
Near-Field settling - Response acceptable as is.
Debris addition to the Test flume - The licensee will make same change as for SON, Units 1 and 2 response to RAI1 B.
Head Loss Termination Criteria - NRC staff emphasized that any extrapolation of test results should bound data. If an exponential extrapolation is used, it should be validated as appropriate with emphasis on trend over last part of test. The licensee stated this is consistent with their plans. With the changes noted above, the response will be acceptable.
RAI4: The licensee will provide additional information on vortex suppression features appropriately consistent with response to Sequoyah RAI 1G and will address flashing in the same manner as for Sequoyah response to RAI 1G.
RAI8: NRC staff found this response still not adequate since it does not address shrinkage of reactor coolant system inventory. NRC staff noted that this issue could be resolved by explicitly accounting for the effect in the calculation or demonstrating that existing conservatisms in the minimum level calculation would bound this effect. The licensee stated they would evaluate path forward for this and provide a revised response.
The licensee believes this issue has been addressed for Sequoyah Nuclear Plant in prior submittals, but will verify and inform NRC staff of path forward.
-3 Comments on the Test Plan for SON, Units 1 and 2, and WBN, Unit 1 Note after Item 36, page E3-4. The licensee will generalize expected behavior as stated in the note.
NRC staff stated position that 1/16" batches are appropriate for doing these tests since thin bed formation point cannot readily be predicted. The licensee stated that test protocol would be revised for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1 to show 1/16" batches.
Follow-up Action Follow-up call will be held on June 17,2010. During that call, the licensee will provide expected submittal date for revised draft responses to SON, Units 1 and 2 RAI1 G, and WBN, Unit 1 RAls 4 and 8. Also, during the call, NRC staff will provide any additional feedback on the test plan.
LICENSEE: Tennessee Valley Authority (TVA)
FACILITY: Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1
SUBJECT:
SUMMARY
OF JUNE 10,2010, CONFERENCE CALL WITH TVA ON THEIR PROPOSED RESPONSE TO A REQUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 2004-02 (TAC NOS. MC4717, MC4718, AND MC4730)
On June 10,2010, a Category 1 public conference call was held among the Nuclear Regulatory Commission (NRC) staff and representatives of Tennessee Valley Authority (TVA or the licensee) and TVA's contractors, AREVA, PCI and Alden Research Laboratory. A list of call participants is provided as Enclosure 1. The purpose of the call was to discuss TVA's proposed responses to the NRC staff's requests for additional information (RAls) dated October 14, 2009, for Sequoyah Nuclear Plant (SQN), Units 1 and 2, and September 29, 2009, for Watts Bar Nuclear Plant (WBN), Unit 1 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML092780335 and ML092650260 respectively). The NRC's RAI letters were in response to TVA's submittals for NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," for SQN, Units 1 and 2, and WBN, Unit 1. The NRC staff has been conducting calls with all licensees who are responding to RAls on GL 2004-02 with the intent of providing NRC guidance in order to reduce the need for additional rounds of RAls.
The NRC's RAls requested the licensee to be prepared to discuss its proposed responses with the NRC staff prior to formal submittal. The licensee provided draft responses on June 3, 2010 (ADAMS Accession No. ML101590409) to the NRC staff's RAls and the NRC staff discussed each proposed response in detail with the licensee and its contractors. Enclosure 2 summarizes the discussion of each proposed response.
The licensee will provide its final RAI responses in a letter to the NRC. Please direct any inquiries to me at 301-415-1564, or by email to siva.lingam@nrc.gov.
IRA!
Siva P. Lingam, Project Manager Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, and 50-390
Enclosures:
- 1. List of Participants
- 2. Summary of the Conference Call cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 R1F RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrLABClayton RidsNrrPMSequoyah RidsNrrOd RidsRgn2MailCenter RidsNrrPMWattsBar1 RidsNrrDssSsib J. Lehning, NRR S. Smith, NRR M. Yoder, NRR P. Klein, NRR RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource CSteger, NRR DDiaz-Toro, EDO Reg" ADAMS ACCESSION NO'.. ML101660044 OFFICE LPL2-2/PM LPL2-2/LA DSS/SSIB/BC LPL2-2/BC NAME SLinqam CSoia (BClayton for) MScott (SSmith for) DBroaddus (SBailey for)
DATE 06/15/10 06/15/10 06/15/10 06/17/10 OFFICIAL RECORD COpy
