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| | number = ML15226A466 | | | number = ML15226A466 |
| | issue date = 08/14/2015 | | | issue date = 08/14/2015 |
| | title = 2015/08/14 NRR E-mail Capture - Request for Additional Information Regarding Tritium Production License Amendment (TAC No. MF6050) | | | title = NRR E-mail Capture - Request for Additional Information Regarding Tritium Production License Amendment |
| | author name = Dion J | | | author name = Dion J |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
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| | page count = 4 | | | page count = 4 |
| | project = TAC:MF6050 | | | project = TAC:MF6050 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Dion, JeanneSent:Friday, August 14, 2015 12:19 PMTo:Szabo, Clinton William; Arent, Gordon <garent@tva.gov> (garent@tva.gov); rhbryan@tva.govCc:Krepel, Scott; Jackson, Christopher; Quichocho, JessieSubject:Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050)Attachments:FINAL WBN tritium LAR SRXB RAIs.docxGentlemen, By letter dated March 31, 2015, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications to increase the maximum number of tritium producing burnable absorber rods and to delete outdated information related to the tritium production program at Watts Bar Nuclear Plant (WBN) Unit 1 (ADAMS Accession No. ML15098A446). These changes would revise TS 4.2.1," Fuel Assemblies", TS 3.5.1 "Accumulators," Surveillance Requirement (SR) 3.5.1.4, TS 3.5.4, "Refueling Water Storage Tank," and SR 3.5.4. TVA supplemented this request with letters dated in May and June 2015 (ADAMS Accession Nos. ML15147A611 and ML15169B117). | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Dion, Jeanne Sent: Friday, August 14, 2015 12:19 PM To: Szabo, Clinton William; Arent, Gordon <garent@tva.gov> (garent@tva.gov); |
| | rhbryan@tva.gov Cc: Krepel, Scott; Jackson, Christopher; Quichocho, Jessie |
| | |
| | ==Subject:== |
| | Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050) |
| | Attachments: FINAL WBN tritium LAR SRXB RAIs.docx Gentlemen, By letter dated March 31, 2015, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications to increase the maximum number of tritium producing burnable absorber rods and to delete outdated information related to the tritium production program at Watts Bar Nuclear Plant (WBN) Unit 1 (ADAMS Accession No. ML15098A446). These changes would revise TS 4.2.1, Fuel Assemblies, TS 3.5.1 Accumulators, Surveillance Requirement (SR) 3.5.1.4, TS 3.5.4, Refueling Water Storage Tank, and SR 3.5.4. TVA supplemented this request with letters dated in May and June 2015 (ADAMS Accession Nos. ML15147A611 and ML15169B117). |
| The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is attached to this e-mail. The proposed questions were provided to your staff on August 5, 2015, and TVA has agreed to provide a response to this information before September 14, 2015. | | The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is attached to this e-mail. The proposed questions were provided to your staff on August 5, 2015, and TVA has agreed to provide a response to this information before September 14, 2015. |
| Please contact me if you have any concerns with this request. | | Please contact me if you have any concerns with this request. |
| Jeanne Dion Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-1349 | | Jeanne Dion Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-1349 1 |
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| Hearing Identifier: NRR_PMDA Email Number: 2299 Mail Envelope Properties (6dd5b2399d5d44ba865b7880a841a324) | | Hearing Identifier: NRR_PMDA Email Number: 2299 Mail Envelope Properties (6dd5b2399d5d44ba865b7880a841a324) |
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| ==Subject:== | | ==Subject:== |
| Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050) Sent Date: 8/14/2015 12:19:17 PM Received Date: 8/14/2015 12:19:00 PM From: Dion, Jeanne Created By: Jeanne.Dion@nrc.gov Recipients: "Krepel, Scott" <Scott.Krepel@nrc.gov> Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov> Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> Tracking Status: None "Szabo, Clinton William" <cwszabo@tva.gov> Tracking Status: None "Arent, Gordon <garent@tva.gov> (garent@tva.gov)" <garent@tva.gov> Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov> Tracking Status: None Post Office: HQPWMSMRS08.nrc.gov Files Size Date & Time MESSAGE 1329 8/14/2015 12:19:00 PM FINAL WBN tritium LAR SRXB RAIs.docx 21750 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050) |
| REQUEST FOR ADDITIONAL INFORMATION TENNESSEE VALLEY AUTHORITY FOR WATTS BAR NUCLEAR PLANT, UNIT 1 PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) 1. As part of the review of the license amendment approved for loading of 2,304 tritium producing burnable absorber rods (TPBARs) in 2002, TVA indicated that they planned to use TPBARs in key peripheral locations to suppress power. The intent of doing so was to ensure that the vessel fluence remains bounded by the projected value used in the design basis evaluation for 10 CFR 50.61 compliance. Please confirm that the expected vessel fluence for cores with 1,792 TPBARs will continue to be less than the value assumed in the design basis pressurized thermal shock evaluation for Watts Bar Unit 1. 2. The post-Loss of Coolant Accident (LOCA) subcriticality assessment was performed using revised assumptions for leaching of lithium from the core due to TPBAR failures. A series of Pacific Northwest National Laboratory (PNNL) tests are used as justification for the new assumptions. However, little information is provided about the PNNL tests other than the experiment durations and the temperature at which the tests were conducted. Provide the following information: a. A description of the test conditions, including ambient fluid conditions, fluid flow, installation configuration for the TPBAR, and mechanical loads. b. The pellet leach rates observed during the tests. c. The projected maximum temperature for the TPBARs during post-LOCA conditions. d. Technical justification for the applicability of the test results to the post-LOCA environment that would be experienced by the TPBARs, including fluid flow/turbulence, mechanical vibrations, thermal contraction/expansion, and coolant chemistry. 3. In order to eliminate all unborated dilution sources, TVA has committed to replacing check valves on the lower compartment supply lines for the Component Cooling Water (CCW) System and Essential Raw Cooling Water (ERCW) System, as well as replacing the upper compartment cooler cooling coils. Chapter 9 of the UFSAR indicates that one of the CCW return lines has the same vulnerability; that is, the potential exists for backflow into the containment via check valve 1-CKV-70-698. Explain how backflow is precluded from occurring through this flow path, or incorporate this potential dilution source in the post-LOCA subcriticality assessment. 4. The LAR states that the RWST, ice mass, and accumulator fluid masses are assumed to be at a minimum value, while the Reactor Coolant System (RCS) fluid mass is assumed to be at a maximum. The intent is to conservatively select the fluid masses that will result in minimizing the boron concentration of the resulting mixture. For the hot leg switchover (HLSO) assessment, the sump boron concentration for all cases is lower than the minimum boron concentration for the ice mass (1,800 ppm). Therefore, assuming the minimum ice mass fluid mass is appropriate. However, for the long term assessments, this is not true. As a result, the ice mass would represent a boron dilution source and the maximum available fluid mass should be assumed. Provide an updated long term assessment that utilizes an appropriately conservative ice fluid mass. | | Sent Date: 8/14/2015 12:19:17 PM Received Date: 8/14/2015 12:19:00 PM From: Dion, Jeanne Created By: Jeanne.Dion@nrc.gov Recipients: |
| }} | | "Krepel, Scott" <Scott.Krepel@nrc.gov> |
| | Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov> |
| | Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> |
| | Tracking Status: None "Szabo, Clinton William" <cwszabo@tva.gov> |
| | Tracking Status: None "Arent, Gordon <garent@tva.gov> (garent@tva.gov)" <garent@tva.gov> |
| | Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov> |
| | Tracking Status: None Post Office: HQPWMSMRS08.nrc.gov Files Size Date & Time MESSAGE 1329 8/14/2015 12:19:00 PM FINAL WBN tritium LAR SRXB RAIs.docx 21750 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION TENNESSEE VALLEY AUTHORITY FOR WATTS BAR NUCLEAR PLANT, UNIT 1 PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050) |
| | : 1. As part of the review of the license amendment approved for loading of 2,304 tritium producing burnable absorber rods (TPBARs) in 2002, TVA indicated that they planned to use TPBARs in key peripheral locations to suppress power. The intent of doing so was to ensure that the vessel fluence remains bounded by the projected value used in the design basis evaluation for 10 CFR 50.61 compliance. Please confirm that the expected vessel fluence for cores with 1,792 TPBARs will continue to be less than the value assumed in the design basis pressurized thermal shock evaluation for Watts Bar Unit 1. |
| | : 2. The post-Loss of Coolant Accident (LOCA) subcriticality assessment was performed using revised assumptions for leaching of lithium from the core due to TPBAR failures. |
| | A series of Pacific Northwest National Laboratory (PNNL) tests are used as justification for the new assumptions. However, little information is provided about the PNNL tests other than the experiment durations and the temperature at which the tests were conducted. Provide the following information: |
| | : a. A description of the test conditions, including ambient fluid conditions, fluid flow, installation configuration for the TPBAR, and mechanical loads. |
| | : b. The pellet leach rates observed during the tests. |
| | : c. The projected maximum temperature for the TPBARs during post-LOCA conditions. |
| | : d. Technical justification for the applicability of the test results to the post-LOCA environment that would be experienced by the TPBARs, including fluid flow/turbulence, mechanical vibrations, thermal contraction/expansion, and coolant chemistry. |
| | : 3. In order to eliminate all unborated dilution sources, TVA has committed to replacing check valves on the lower compartment supply lines for the Component Cooling Water (CCW) System and Essential Raw Cooling Water (ERCW) System, as well as replacing the upper compartment cooler cooling coils. Chapter 9 of the UFSAR indicates that one of the CCW return lines has the same vulnerability; that is, the potential exists for backflow into the containment via check valve 1-CKV-70-698. Explain how backflow is |
| | |
| | precluded from occurring through this flow path, or incorporate this potential dilution source in the post-LOCA subcriticality assessment. |
| | : 4. The LAR states that the RWST, ice mass, and accumulator fluid masses are assumed to be at a minimum value, while the Reactor Coolant System (RCS) fluid mass is assumed to be at a maximum. The intent is to conservatively select the fluid masses that will result in minimizing the boron concentration of the resulting mixture. For the hot leg switchover (HLSO) assessment, the sump boron concentration for all cases is lower than the minimum boron concentration for the ice mass (1,800 ppm). Therefore, assuming the minimum ice mass fluid mass is appropriate. However, for the long term assessments, this is not true. As a result, the ice mass would represent a boron dilution source and the maximum available fluid mass should be assumed. Provide an updated long term assessment that utilizes an appropriately conservative ice fluid mass.}} |
Letter Sequence RAI |
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MONTHYEARCNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) Project stage: Request CNL-15-077, Correction to Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03)2015-04-28028 April 2015 Correction to Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) Project stage: Request ML15121A8262015-05-0101 May 2015 Annual Radioactive Effluent Release Report - 2014 Project stage: Request ML15127A2502015-05-14014 May 2015 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Application to Increase Tritium Production Absorbing Rods Project stage: Acceptance Review CNL-15-092, Response to NRC Request to Supplement the Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03)2015-05-27027 May 2015 Response to NRC Request to Supplement the Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) Project stage: Supplement CNL-15-093, Response to NRC Request to Supplement Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Radiological Protection and Radiological Consequences2015-06-15015 June 2015 Response to NRC Request to Supplement Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Radiological Protection and Radiological Consequences Project stage: Supplement CNL-15-104, Submittal of Revision 106, Appendix C to Central Emergency Control Center, Radiological Emergency Plan2015-06-15015 June 2015 Submittal of Revision 106, Appendix C to Central Emergency Control Center, Radiological Emergency Plan Project stage: Request ML15173A0972015-06-26026 June 2015 Acceptance Review Results for Requested License Amendment to Increase Tpbar Production Project stage: Acceptance Review ML15173A1142015-06-26026 June 2015 Letter for Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing Project stage: Other ML15173A1162015-06-26026 June 2015 FRN for Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing Project stage: Other ML15225A3772015-08-12012 August 2015 Tennessee Valley Authority Presentation to NRC on Tpbar LAR 8-12-15 Project stage: Other ML15226A4662015-08-14014 August 2015 NRR E-mail Capture - Request for Additional Information Regarding Tritium Production License Amendment Project stage: RAI ML15236A3152015-08-24024 August 2015 NRR E-mail Capture - Watts Bar Unit 1- Draft RAIs- Tpbars Amendment MF6050 Project stage: Draft Other ML15238A5782015-08-25025 August 2015 NRR E-mail Capture - Watts Bar 1- Final Rad Protection RAIs for MF6050 Project stage: RAI CNL-15-172, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Reactor Systems Branch2015-09-14014 September 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Reactor Systems Branch Project stage: Response to RAI ML15225A3752015-09-17017 September 2015 August 12, 2015 - Summary of Public Meeting Regarding Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Increase Tritium Production Project stage: Meeting CNL-15-192, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch2015-09-25025 September 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch Project stage: Response to RAI ML15278A0482015-10-0202 October 2015 NRR E-mail Capture - Tpbar RAIs Part 3b- Arcb Project stage: RAI ML15286A0012015-10-0909 October 2015 NRR E-mail Capture - Regulatory Audit Plan - TVA License Amendment Request Regarding Tritium Producing Burnable Absorber Rods - CAC No. MF6050 Project stage: Other CNL-15-232, Attachment 1, CE-15-588-NP-Attachment, Rev. 1 and Attachment 3, CE-15-611-NP-Attachment Regarding Proposed Response to NRC RAIs Nos. 1, 2, 3, and 4 Regarding LAR for Increasing the Maximum Number of Tpbars in Watts Bar, Unit 1. (Non-Propr2015-11-30030 November 2015 Attachment 1, CE-15-588-NP-Attachment, Rev. 1 and Attachment 3, CE-15-611-NP-Attachment Regarding Proposed Response to NRC RAIs Nos. 1, 2, 3, and 4 Regarding LAR for Increasing the Maximum Number of Tpbars in Watts Bar, Unit 1. (Non-Proprie Project stage: Response to RAI CNL-15-216, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch2015-12-22022 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch Project stage: Response to RAI CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory Project stage: Supplement CNL-16-030, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Supplement to Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch2016-02-22022 February 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Supplement to Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch Project stage: Supplement 2015-05-27
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Category:E-Mail
MONTHYEARML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24215A3152024-07-24024 July 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-276-A, Revision 2 TS 3.8.1, AC Sources ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24157A3152024-06-0303 June 2024 2024 Sequoyah Commercial Grade Dedication Inspection Information Request ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24156A0062024-05-22022 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Recapture Low-Power Testing Time ML24130A0132024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.11 for MCR Chiller Completion Time ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24082A0662024-04-17017 April 2024 Email to Stuart Rymer on Exemption Decision for Watts Bar ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24082A0682024-04-10010 April 2024 Email to Stuart Rymer Re_ Availability of EA-FONSI for Watts Bar ML24100A8392024-04-0909 April 2024 Response from State of Tn Regarding Review of Environmental Assessment for Watts Bar Exemption Request ML24100A8402024-04-0808 April 2024 Email to State of Tn Requesting Review of Environmental Assessment for Watts Bar Exemption Request ML24071A0982024-03-0707 March 2024 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate ML24058A0962024-02-26026 February 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant License Amendment Request to Revise UFSAR for Hydrologic Analysis ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24033A0562024-02-0101 February 2024 NRR E-mail Capture - Correction Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-427-A, Revision 2 Regarding Degraded Barriers ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans 2024-09-10
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Text
NRR-PMDAPEm Resource From: Dion, Jeanne Sent: Friday, August 14, 2015 12:19 PM To: Szabo, Clinton William; Arent, Gordon <garent@tva.gov> (garent@tva.gov);
rhbryan@tva.gov Cc: Krepel, Scott; Jackson, Christopher; Quichocho, Jessie
Subject:
Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050)
Attachments: FINAL WBN tritium LAR SRXB RAIs.docx Gentlemen, By letter dated March 31, 2015, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications to increase the maximum number of tritium producing burnable absorber rods and to delete outdated information related to the tritium production program at Watts Bar Nuclear Plant (WBN) Unit 1 (ADAMS Accession No. ML15098A446). These changes would revise TS 4.2.1, Fuel Assemblies, TS 3.5.1 Accumulators, Surveillance Requirement (SR) 3.5.1.4, TS 3.5.4, Refueling Water Storage Tank, and SR 3.5.4. TVA supplemented this request with letters dated in May and June 2015 (ADAMS Accession Nos. ML15147A611 and ML15169B117).
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is attached to this e-mail. The proposed questions were provided to your staff on August 5, 2015, and TVA has agreed to provide a response to this information before September 14, 2015.
Please contact me if you have any concerns with this request.
Jeanne Dion Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-1349 1
Hearing Identifier: NRR_PMDA Email Number: 2299 Mail Envelope Properties (6dd5b2399d5d44ba865b7880a841a324)
Subject:
Request for Additional Information Regarding Tritium production License Amendment (TAC No. MF6050)
Sent Date: 8/14/2015 12:19:17 PM Received Date: 8/14/2015 12:19:00 PM From: Dion, Jeanne Created By: Jeanne.Dion@nrc.gov Recipients:
"Krepel, Scott" <Scott.Krepel@nrc.gov>
Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov>
Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov>
Tracking Status: None "Szabo, Clinton William" <cwszabo@tva.gov>
Tracking Status: None "Arent, Gordon <garent@tva.gov> (garent@tva.gov)" <garent@tva.gov>
Tracking Status: None "rhbryan@tva.gov" <rhbryan@tva.gov>
Tracking Status: None Post Office: HQPWMSMRS08.nrc.gov Files Size Date & Time MESSAGE 1329 8/14/2015 12:19:00 PM FINAL WBN tritium LAR SRXB RAIs.docx 21750 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION TENNESSEE VALLEY AUTHORITY FOR WATTS BAR NUCLEAR PLANT, UNIT 1 PROPOSED CHANGES TO INCREASE THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS PER CYCLE DOCKET NUMBER 50-390 (TAC NO. MF6050)
- 1. As part of the review of the license amendment approved for loading of 2,304 tritium producing burnable absorber rods (TPBARs) in 2002, TVA indicated that they planned to use TPBARs in key peripheral locations to suppress power. The intent of doing so was to ensure that the vessel fluence remains bounded by the projected value used in the design basis evaluation for 10 CFR 50.61 compliance. Please confirm that the expected vessel fluence for cores with 1,792 TPBARs will continue to be less than the value assumed in the design basis pressurized thermal shock evaluation for Watts Bar Unit 1.
- 2. The post-Loss of Coolant Accident (LOCA) subcriticality assessment was performed using revised assumptions for leaching of lithium from the core due to TPBAR failures.
A series of Pacific Northwest National Laboratory (PNNL) tests are used as justification for the new assumptions. However, little information is provided about the PNNL tests other than the experiment durations and the temperature at which the tests were conducted. Provide the following information:
- a. A description of the test conditions, including ambient fluid conditions, fluid flow, installation configuration for the TPBAR, and mechanical loads.
- b. The pellet leach rates observed during the tests.
- c. The projected maximum temperature for the TPBARs during post-LOCA conditions.
- d. Technical justification for the applicability of the test results to the post-LOCA environment that would be experienced by the TPBARs, including fluid flow/turbulence, mechanical vibrations, thermal contraction/expansion, and coolant chemistry.
- 3. In order to eliminate all unborated dilution sources, TVA has committed to replacing check valves on the lower compartment supply lines for the Component Cooling Water (CCW) System and Essential Raw Cooling Water (ERCW) System, as well as replacing the upper compartment cooler cooling coils. Chapter 9 of the UFSAR indicates that one of the CCW return lines has the same vulnerability; that is, the potential exists for backflow into the containment via check valve 1-CKV-70-698. Explain how backflow is
precluded from occurring through this flow path, or incorporate this potential dilution source in the post-LOCA subcriticality assessment.
- 4. The LAR states that the RWST, ice mass, and accumulator fluid masses are assumed to be at a minimum value, while the Reactor Coolant System (RCS) fluid mass is assumed to be at a maximum. The intent is to conservatively select the fluid masses that will result in minimizing the boron concentration of the resulting mixture. For the hot leg switchover (HLSO) assessment, the sump boron concentration for all cases is lower than the minimum boron concentration for the ice mass (1,800 ppm). Therefore, assuming the minimum ice mass fluid mass is appropriate. However, for the long term assessments, this is not true. As a result, the ice mass would represent a boron dilution source and the maximum available fluid mass should be assumed. Provide an updated long term assessment that utilizes an appropriately conservative ice fluid mass.