Letter Sequence RAI |
|---|
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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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055S-0001 June 28, 2011 LICENSEE:
Tennessee Valley Authority (TVA)
FACILITY:
Sequoyah Nuclear Plant, Units. 1 and 2, and Watts Bar Nuclear Plant, Unit 1
SUBJECT:
SUMMARY
OF MAY 12,2011, MEETING WITH TVA ON THEIR PROPOSED RESPONSE TO A REOUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 2004-02 (TAC NOS. MC4717, MC4718, AND MC4730)
On May 12, 2011, a Category 1 public meeting was held between representatives of Tennessee Valley Authority (TVA, or the licensee) and the Nuclear Regulatory Commission (NRC) staff, at the request of the licensee. The purpose of the meeting was to discuss the small break loss-of-coolant accident (SBLOCA) water level calculations, the containment sump strainer structural integrity calculations, and the schedule for TVA's final 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). Enclosure 1 contains a list of attendees. The licensee presented slides that may be accessed from NRC's ADAMS through Accession No. ML11152A170.
The NRC's RAlletters were in response to TVA's submittals for NRC Generic Letter 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 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 including the test plans and its results with the licensee and its contractors on June 10, 2010, June 17, 2010, July 1,2010, August 17, 2010, and September 20,2010.
The details of the discussion are provided in enclosure 2.
The licensee will provide its final RAI responses for SON, Units 1 and 2 in 2 to 3 weeks in a letter to the NRC.
- 2 Members of the public were not in attendance and no Public Meeting Feedback forms were received.
Please direct any inquiries to me at 301-415-1564 or by email to siva.lingam@nrc.gov.
~\\f'~
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 Attendees
- 2. Meeting Discussion cc w/encls: Distribution via Listserv
MAY 12,2011 LIST OF ATTENDEES U. S. NUCLEAR REGULATORY COMMISSION (NRC)
WITH TENNESSEE VALLEY AUTHORITY (TVA)
REGARDING GENERIC LETTER 2004-02 REQUEST FOR ADDITIONAL INFORMATION DRAFT RESPONSES NRC Ralph Architzel Stewart Bailey Siva Lingam Stephen Smith TVA Chris Carey Jeffrey Hanevich Benjamin Kennedy Robert Kirkpatrick Rod Krich David Lafever Kara Stacy Kelli Yates
May 12, 2011 MEETING DISCUSSION U. S. NUCLEAR REGULATORY COMMISSION WITH TENNESSEE VALLEY AUTHORITY REGARDING GENERIC LETTER 2004-02 WATER LEVEL AND STRUCTURAL INTEGRITY CALCULATIONS The meeting to discuss the subject issues was originally scheduled on October 28,2010, and was cancelled by Tennessee Valley authority (TVA, or the licensee) due to incomplete engineering calculations.
On May 12, 2011, the licensee presented information regarding their sump level calculations for Sequoyah Nuclear Plant (SON), Units 1 and 2, and Watts Bar Nuclear Plant (WBN), Unit 1. The Nuclear Regulatory Commission (NRC) staff had expressed concern that if the strainers were not fully submerged that the potential for additional failure modes during recirculation would have to be considered. The licensee stated that the original sump level calculations were performed very conservatively with the sole intent of validating that vortex formation would not occur at the Emergency Core Cooling System inlet piping. The original sump level calculations did not evaluate the sump level with respect to the height of the new strainers. The licensee removed some of the excessive conservatism from the calculation and determined that the SON, Units 1 and 2 strainers would be fully submerged before excessive head loss could occur across the strainer and the WBN, Unit 1 strainers would be fully submerged prior to recirculation. The NRC staff agreed that the methodology being used by the licensee would be acceptable to show adequate strainer submergence.
The licensee discussed the replacement of problematic insulating material at WBN, Unit 1. The licensee had previously conducted strainer head loss testing that showed that head losses would be acceptable if the problematic material is removed. The NRC staff agreed that removal of the problematic material would result in acceptable head loss for the strainer.
The licensee also provided information regarding the structural qualification of the WBN, Unit 1 strainers. The original head loss test results showed that the differential pressure across the strainer was greater than the calculated allowable load. The licensee is performing activities to reduce the clean strainer head loss, reduce debris head loss (by removal of problematic material discussed above), and reevaluate the allowable strainer structural limits. The !\\IRC staff indicated that the licensee actions appeared to be adequate to address the issue, however, a detailed technical review of the structural qualification would be required by the !\\IRC structural engineer.
The NRC staff stated that the licensee is taking appropriate actions to address the issues discussed at the meeting and that the licensee methodologies are appropriate. However, the NRC staff will have to review the licensee's final submittal prior to making its ultimate determination on closeout of the issues.
- 2 Members of the public were not in attendance and no Public Meeting Feedback forms were received.
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 l\\Iuclear Reactor Regulation Docket l\\Ios. 50-327, 50-328, and 50-390
Enclosures:
- 1. List of Attendees
- 2. Meeting Discussion cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrLABClayton RidsNrrPMSequoyah RidsNrrOd RidsRgn2MailCenter RidsNrrPMWattsBar1 RidsN rrDssSsib S. Smith, NRR R. Architzel, NRR RidsOgcRp Resource CSteger, NRR RidsAcrsAcnw _MailCTR Resource W. Jessup, NRR SBush-Goddard, EDO Rgn II PACKAGE ACCESSION NO. ML11152A171 MEETING NOTICE ACCESSION NO. ML110700031 MEETING
SUMMARY
ACCESSION NO. ML11152A163 SLIDES PRESENTATION ACCESSION NO ML11152A170 OFFICE DORULPL2-2/PM DORULPL2-2/LA DSS/SSIB/BC NAME SLingam CSoia SBailey DATE 06/02/11 06/02/11 06/14/11 OFFICE DORULPL2-2/BC DORULPL2-2/PM NAME
SLingam DATE 06/28/11 111 OFFICIAL RECORD COpy
