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
November 25, 2008 Mr. William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 C REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4717 AND MC4718)
By letter dated February 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080640205), Tennessee Valley Authority (the licensee) submitted a supplemental response to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, for the Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensees submittals.
The process involved detailed review by a team of approximately 10 subject matter experts, with a focus on the review areas described in the NRCs Revised Content Guide for Generic Letter 2004-02 Supplemental Responses (ADAMS Accession No. ML073110389). Based on these reviews, the staff has determined that additional information is needed in order to conclude there is reasonable assurance that GL 2004-02 has been satisfactorily addressed for Sequoyah. The enclosed document describes these requests for additional information (RAIs).
The NRC requests that the licensee respond to these RAIs within 90 days of the date of this letter. However, the NRC would like to receive only one response letter for all RAIs with exceptions stated below. If the licensee concludes that more than 90 days are required to respond to the RAIs, the licensee should request additional time, including a basis for why the extension is needed.
If the licensee concludes, based on its review of the RAIs, that additional corrective actions are needed for GL 2004-02, the licensee should request additional time to complete such corrective actions as needed. Criteria for such extension requests are contained in the NRC policy issue paper, SECY-06-0078, Status of Resolution of GSI [Generic Safety Issue]-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance, (ADAMS Accession No. ML053620174), and examples of previous requests and approvals can be found on the NRCs sump performance website, located at: http://www.nrc.gov/reactors/operating/ops-experience/pwr-sump-performance.html.
Any extension request should also include results of contingency planning that will result in near-term identification and implementation of any and all modifications needed to fully address GL 2004-02. The NRC strongly suggests that the licensee discuss such plans with the staff before formally transmitting an extension request.
The exception to the above response timeline is RAI 7 in the enclosure. The NRC staff considers in-vessel downstream effects to not be fully addressed at Sequoyah, as well as at other pressurized-water reactors. The licensee's submittal refers to the draft Westinghouse topical report, WCAP-16793-NP, Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid. At this time, the NRC staff has not issued a final safety evaluation (SE) for WCAP-16793-NP.
The licensee may demonstrate that in-vessel downstream effects issues are resolved for Sequoyah, by showing that the licensees plant conditions are bounded by the final WCAP-16793-NP and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE. The licensee may also resolve RAI 7 by demonstrating, without reference to WCAP-16793-NP or the NRC staff SE, that in-vessel downstream effects have been addressed at Sequoyah. The specific issues raised in RAI 7 should be addressed regardless of the approach the licensee chooses to take.
The licensee should report how it has addressed the in-vessel downstream effects issue and the associated RAI referenced above within 90 days of issuance of the final NRC staff SE on WCAP-16793-NP. The NRC staff is currently developing a regulatory issue summary to inform licensees of the staffs expectations and plans regarding resolution of this remaining aspect of GSI-191.
If you have any questions, please contact me at 301-415-3974.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
ML083230823 OFFICE LPLII-2/PM LPLII-2/PM LPLII-2/LA DSS/SSIB/BC (A)
NAME TOrf BMoroney CSola DHarrison DATE 11/20/08 11/20/08 11/20/08 11/20/08 OFFICE DE/EMCB/BC DCI/CSGB/BC LPLII-2/BC NAME KManoly AHiser TBoyce DATE 11/19/08 11/20/08 11/25/08
Enclosure REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 SUPPLEMENTAL RESPONSE DATED 02/29/2008 TO GENERIC LETTER (GL) 2004-02
- 1. Provide the test protocol used for head loss testing and a justification that shows the following aspects of the testing were conservative or prototypical:
A. Addition of debris to the test flume prior to the starting of the recirculation pump.
B. Concentration of debris in the test flume with respect to agglomeration and settling.
C. The fibrous debris preparation and introduction with respect to prototypical sizing (transport and bed formation).
D. Flume velocity and turbulence.
E. Any near-field settling that occurred during the test.
F. Test scaling including debris amounts and strainer flow velocity.
G. How partial submergence of the strainer affects the scaling of flow and debris amounts.
- 2. Provide information that shows the applicability of the Performance Contracting Inc., clean strainer head loss correlation to pressurized-water reactor (PWR) strainers.
- 3. Clearly state the design inputs for the head loss testing and calculation and provide the basis for these inputs.
- 4. Provide the basis for the statement that a thin bed (1/8) inch of fiber cannot form on the strainer considering the design basis loading (200 pound latent debris) and design basis strainer size (1000 square feet).
- 5. Provide an evaluation of the performance of the strainer under partially submerged conditions.
- 6. Provide an evaluation that shows that flashing across or within the strainer will not occur.
- 7. The NRC staff considers in-vessel downstream effects to not be fully addressed at Sequoyah Nuclear Plant (SQN), as well as at other PWRs. The licensees submittal for SQN refers to the draft Westinghouse topical report, WCAP-16793-NP. The NRC staff has not issued a final safety evaluation (SE) for WCAP-16793-NP. The licensee may demonstrate that in-vessel downstream effects issues are resolved for SQN by showing that the plant conditions are bounded by the final WCAP-16793-NP and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE. The licensee may also resolve this item by demonstrating without reference to WCAP-16793-NP or the staff SE that in-vessel downstream effects have been addressed at SQN. In any event, the licensee should report how it has addressed the in-vessel downstream effects issue within 90 days of issuance of the final NRC staff SE on WCAP-16793-NP. The NRC staff is developing a regulatory issue summary to inform the industry of the staff's expectations and plans regarding resolution of this remaining aspect of NRCs GSI-191.
- 8. The 2004 Edition of the American Society of Mechanical Engineers (ASME) Code is not currently endorsed by the Code of Federal Regulations. Please provide justification and/or re-evaluation for discrepancies, if any, between the applicable portions of the 2004 Edition of the ASME Code that were used in the sump structural analysis and the respective Code Editions that are currently endorsed by the NRC in Title 10 of the Code of Federal Regulations, Section 50.55a, Codes and standards.
