Letter Sequence Request |
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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, 1101 Market Street, Chattanooga, Tennessee 37402 September 30, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating Licenses Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 Watts Bar Nuclear Plant, Unit 2 Construction Permit No. CPPR-92 NRC Docket No. 50-391
Subject:
Second Progress Update on Improved Flood Mitigation System Project
References:
- 1. Letter from TVA to NRC, "Commitment to Install Improved Flood Mitigation Systems," dated April 16, 2013
- 2. Letter from TVA to NRC, "Progress Update on Improved Flood Mitigation System Project," dated July 1, 2013 By letter dated April 16, 2013, the Tennessee Valley Authority (TVA) committed to install improved flood mitigation systems at the Sequoyah Nuclear Power Plant (SQN), Units 1 and 2, and the Watts Bar Nuclear Plant (WBN), Units 1 and 2 (Reference 1). TVA committed to complete implementation of the improved flood mitigation systems at SQN and WBN by December 31, 2016. TVA also committed to provide periodic written updates regarding progress of the project. During a public meeting on June 27, 2013, TVA briefed the NRC regarding the status of the improved flood mitigation project and provided the first progress update on July 1, 2013 (Reference 2). TVA also committed in the first progress update (Reference 2), to develop a set of major tasks through TVA's engineering design and project controls processes and to discuss these major tasks as part of the periodic written progress updates.
The purpose of this letter is to provide the second written progress update regarding progress of the improved flood mitigation system project consistent with Commitment 2 in of the Reference 1 letter and Commitment 1 in Enclosure 1 of the Reference 2 letter.
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 September 30, 2013 During the June 27, 2013, public meeting and in the first update (Reference 2), TVA advised the NRC that engineering design and project controls for the project are being developed consistent with TVA's existing design and project management procedures. The Project Status Schedule, provided in Table 1 on page 3 of this letter lists the major tasks associated with-the design and project controls developed to implement the flood mitigation system.
Table 1 will be used to provide the overall status of the improved flood mitigation system project each quarter. The status of the Table 1 tasks from July 1, 2013 to September 20, 2013, is provided below.
" Task 2, Develop Project Plan, and Task 3, Perform Conceptual Design Phase, scheduled completion is revised from September 30, 2013, to October 30, 2013.
The following actions have been completed:
- a. Joint project team formed
- b. Project Charter developed and comments are being resolved
- c. Cost estimate and schedule has been developed for the Conceptual Design Phase
- d. Project approval package for the Conceptual Design Phase has been prepared
- e. The Project Approval Board (PAB) has granted authorization to fund the Conceptual Design Phase A plan is being developed for Tasks 2 and 3 to maintain the scheduled completion of Task 4.
Task 4, Perform Preliminary Design Phase, has begun. For Task 4, the following actions have been completed:
- a. Design Criteria have been approved and issued for SQN and are under review for WBN
- b. Statement of work for the Preliminary Engineering Phase is drafted and is expected to be released to the prospective bidders in October 2013
- c. Procurement strategy has been developed for the Final Engineering and Implementation Phase - Firm Fixed Price Design, Build, and Test The following Task 4 actions are scheduled to be completed between September 21, 2013 and February 27, 2014:
- a. Develop 10% Design Package
- b. Vendor Selection for Design/Build Contract
- c. Detailed Cost and Schedule development
- d. Risk identification and risk mitigation planning
- e. Project Plans (Project Management, Communication, and Risk Management)
National Environmental Policy Act (NEPA) screening
U.S. Nuclear Regulatory Commission Page 3 September 30, 2013 TVA noted in the June 27, 2013, public meeting and in Reference 2, that since issuance of the April 16, 2013 letter, potential design alternatives had emerged for a number of elements of the overall flood mitigation system design as described in Enclosure 1 of Reference 1. To date, progress in the following design areas has been made:
- 1. The SQN FLEX Equipment Storage Building is being designed to include the flood mode equipment.
- 2. For the flood mode equipment, dedicated diesel generators will be procured and installed in lieu of using the FLEX 3 MW diesels for power.
TABLE 1 PROJECT STATUS SCHEDULE (updates shown in bold type)
Scheduled Scheduled Task Start Finish Status
U.S. Nuclear Regulatory Commission Page 4 September 30, 2013 TVA will provide the third quarterly written progress update of the improved flood mitigation system project by December 31, 2013, consistent with Commitment 2 in Enclosure 2 of TVA's letter to NRC dated April 16, 2013.
There are no new regulatory commitments contained in this letter.
If you have questions regarding this update, please contact Kevin Casey at (423) 751-8523.
- Res
- ully, J
.Shea ice President, Nuclear Licensing cc:
NRC Regional Administrator - Region II NRR Director - NRC Headquarters NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager - Sequoyah Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant, Unit I NRR Project Manager - Watts Bar Nuclear Plant, Unit 2