Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML052490347, ML052500298, ML052850352, ML061010180, ML062910513, ML062910522, ML063060251, ML073370317, ML073380152, ML090720869, ML101590556, ML11154A093, ML11230B250, ML14283A526, ML15191A183
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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
ML0506804622005-03-0707 March 2005
Request Biocide/Corrosion Treatment Plan Approval, NPDES Permit No. TN0026450
Project stage: Request
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
ML0520800652005-07-21021 July 2005
And Watts Bar Nuclear Plant - NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - RAI, Supplemental Information
Project stage: Supplement
ML0524903472005-09-0101 September 2005
NRC Generic Letter 2004-02; Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors - Second Response
Project stage: Other
ML0525002982005-09-0101 September 2005
NRC Generic Ltr (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) - Second Response
Project stage: Other
ML0528503522005-09-30030 September 2005
Outage Start Date Change Related to Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR)
Project stage: Other
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
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
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: Other
ML0629105082006-07-0303 July 2006
Generic Letter 2004-02 - Request for Additional Information Regarding NRC Staff Audit on Containment Sump Modifications
Project stage: Request
ML0621204722006-07-0303 July 2006
Generic Letter 2004-02 - Request for Additional Information Regarding the Nuclear Regulatory Commission Staff Audit on the 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
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
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
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
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
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
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
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
ML1104003842011-02-0707 February 2011
Enclosure 1, Hydrothermal Effects on the Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir
Project stage: Request
ML1104003832011-02-0707 February 2011
Submittal of Hydrothermal Effects on Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauge Reservoir, Report
Project stage: Request
ML11152A1702011-05-12012 May 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
ML11137A1222011-05-13013 May 2011
Annual Radiological Environmental Operating Report - 2010
Project stage: Request
ML11143A0832011-05-19019 May 2011
Response to Request for Additional Information on Intake Pumping Station Water Velocity
Project stage: Response to RAI
ML11152A1602011-05-26026 May 2011
Response to Request for Information from Public Meeting on May 11, 2011
Project stage: Request
ML1115303282011-06-0202 June 2011
Completion of Temporary Instruction (Ti) 184, Availability and Readiness Inspection of Severe Accident Mitigation Guidelines (Samgs) at Region II Facilities - Revision
Project stage: Request
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
ML11154A0932011-06-28028 June 2011
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
ML11215A0992011-07-28028 July 2011
NPDES Permit No. TN0020168, TVA - Watts Bar Nuclear Plant, Spring City, Rhea County, Tennessee
Project stage: Request
2008-11-25
[Table View] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City. Tennessee 37381-2000 JUL 2 1 2005 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority )
50-328 50-390 SEQUOYAH NUCLEAR PLANT (SQN) AND WATTS BAR NUCLEAR PLANT (WBN) - NUCLEAR REGULATORY COMMISSION (NRC) GENERIC LETTER (GL) 2004-02: POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS (PWR) - REQUEST FOR ADDITIONAL INFORMATION (RAI)
(TAC NOS. MC4717, MC4718, AND MC4730)
The purpose of this letter is to provide supplemental information to TVA's 90-day response to GL 2004-02.
By letter dated March 7, 2005, TVA provided the 90-day response to NRC GL 2004-02 for WBN Unit 1 and SQN Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
By letter dated June 3, 2005, NRC requested additional information based on their review of industry 90-day responses as follows:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1, 2005, but did not discuss the evaluation of chemical effects. Although the GL did not specifically request that the evaluation of chemical effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical effects and verify whetheryour September 1, 2005, response will include such an evaluation.
Prrted 0-ead pape.
U. S. Nuclear Regulatory Commission Page 2 JUL 21 2005 In response to the RAI, TVA will include a discussion of how final sump operating margin will be used to bound chemical effects in the containment sump analysis and any planned sump modifications forWBN Unit 1 and SQN Units 1 & 2 in our September 1, 2005, GL 2004-02 response.
There are no regulatory commitments contain in this letter. Please direct any questions to Rob Brown at (423) 751-7228.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21st dayof July 2005.
Sincerely, PauL Pace Manager, Sequoyah/Watts Bar Licensing and Industry Affairs cc: Douglas V. Pickett, Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 08G9a) 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379-3624 NRC Senior Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381-2000
