Letter Sequence Response to RAI |
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MONTHYEARML0204507012002-02-11011 February 2002 Unit - Request for Additional Information Re Tritium Production Program Interface Issue 7 Project stage: RAI ML0205800822002-02-19019 February 2002 Response to Request for Additional Information Re Tritium Production - Holtec Analysis. Submits New non-proprietary Version (Revision 3) of Holtec International Report HI-2012620 Project stage: Response to RAI ML0205806122002-02-21021 February 2002 License Amendment, FSAR Change for Revised Spent Fuel Cooling Analysis Methodology - TAC Nos. MB1807 and MB1884 Project stage: Other ML0205800052002-02-21021 February 2002 Responses to RAI Regarding Tritium Producing Burnable Absorber Rods (TPBARS) Project stage: Response to RAI ML0205804302002-02-21021 February 2002 Tennessee Valley Authority Response to NRC Request for Additional Information Re Tritium Producing Burnable Absorber Rods (TPBARS) at Watts Bar Nuclear Plant Project stage: Response to RAI ML0210003612002-04-0505 April 2002 Response to Request for Additional Information Re Tritium Production - Interface Issue Number 2 - Procurement and Fabrication Issues Project stage: Response to RAI ML0211905572002-04-25025 April 2002 Second Request for Additional Information Tritium Production Program Interface Issue 7 Project stage: RAI ML0212806302002-05-0808 May 2002 Request for Additional Information Re Tritium Production Program Interface Issue 5 Project stage: RAI ML0214401522002-05-21021 May 2002 Request for Additional Information Regarding Tritium Production - Interface Issue Number 7 Light Load Handling Systems Project stage: Request ML0214401422002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 7 - Light Load Handling Systems Project stage: Request ML0214401352002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 5 - Control Room Habitability Systems Project stage: Request ML0214901392002-05-23023 May 2002 Response to Request for Additional Information Re Radiological Impact Project stage: Response to RAI ML0221004492002-07-29029 July 2002 Request for Additional Information Tritium Production Program Project stage: RAI ML0221401972002-07-30030 July 2002 Tritium Production -- Post-LOCA Hot Leg Emergency Core Cooling System (ECCS) Recirculation Time -- Supplemental Information Project stage: Supplement ML0222601522002-08-0909 August 2002 Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0831800942002-08-0909 August 2002 Plants - Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0223209052002-08-20020 August 2002 Environmental Assessment and Finding of No Significant Impact for Incore Irradiation Services for the U. S. Department of Energy'S Tritium Production Program Project stage: Other ML0225409252002-09-23023 September 2002 Amendment No. 40, Irridiate Up to 2304 Tritium-Producing Burnable Absorber Rods in the Reactor Core Project stage: Acceptance Review ML0227502952002-09-23023 September 2002 Technical Specification Pages for Amendment No. 40, Irradiated Up to 2304 Tritium Producing Burnable Absborber Rods in the Reactor Core Project stage: Other ML0802203782008-01-18018 January 2008 Tech Spec Pages for Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Other ML0735205462008-01-18018 January 2008 Issuance of License Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML0821800942008-07-31031 July 2008 WCAP-16932-NP, Rev. 1, Control Rod Insertion Following a Cold Leg LOCA for Watts Bar Unit 1. Project stage: Request ML0821800932008-08-0101 August 2008 Watt'S Bar, Unit 1, Technical Specifications Change - Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Request ML0827502132008-10-0606 October 2008 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 (Tac No. MD9396) Project stage: Withholding Request Acceptance ML0828314472008-10-14014 October 2008 Request for Additional Information Regarding Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of -Coolant Accident (Tac MD9396) Project stage: RAI ML0829401702008-10-28028 October 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0830401042008-11-0707 November 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0833601912008-11-25025 November 2008 Response to Request for Additional Information Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of-Coolant Accident Project stage: Response to RAI ML0834303042008-12-0909 December 2008 Potential Schedule Impact Regarding Revision of Technical Specifications, Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Other ML0835101022008-12-19019 December 2008 Withdrawal of Questions Number 6 from Letter Dated October 28, 2008, Regarding Proposed Amendment to Revise Technical Specifications for Boron Requirements for the Cold Leg Accumulations and Refueling Water Storage Tank Project stage: Withdrawal ML0902202552008-12-31031 December 2008 Response to Request for Additional Information Emergency Core Cooling System Boron Requirements Project stage: Response to RAI ML0900900442008-12-31031 December 2008 Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle Project stage: Other ML0900600402009-01-26026 January 2009 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 Project stage: Withholding Request Acceptance ML0909205062009-05-0404 May 2009 Issuance of Amendment Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML1004703202010-02-0909 February 2010 Clarification Regarding the Number of Tritium Producing Burnable Absorber Rods in Operating Cycle 10 and Program Update Project stage: Other CNL-14-053, Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core2014-04-0808 April 2014 Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core Project stage: Other ML15030A5082015-01-30030 January 2015 Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System Project stage: Other 2008-10-14
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
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Tennessee Valley Authoutty. Post Office Box 2000. St56ng Oty, Tennessee 37381-2000 FEB 21 ?P-?
10 CFR 50.9 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No.50-390 Tennessee Valley Authority
SUBJECT:
WATTS BAR NUCLEAR PLANT - RESPONSES TO RAI REGARDING TRITIUM PRODUCING BURNABLE ABSORBER RODS (TPBARS) (TAC NO. MB1884)
The purpose of this letter is to provide TVA's response to NRC's request for additional information sent by email dated January 28, 2002. NRC's request was subsequently provided in a letter dated February 11, 2002. The enclosure provides both the questions asked and the responses to those questions.
U.S. Nuclear Regulatory Commission Page 2 FnB 21IN There are no regulatory commitments made by this letter. If you have any questions about this letter, please contact me at (423) 365-1824.
P. L. 'Pace Manager, Site Licensing and Industry Affairs Enclosure cc: See page 3 Subscribed and sworn to before me on this 24l- day of 2ý,W ;o..
Notary Eubfic My Commission expires _0-
U.S. Nuclear Regulatory Commission Page 3 FEB 2 1 2002 PLP:RAS Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. L. Mark Padovan, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 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 R. J. Adney, LP 6A-C D. K. Baker, BR 3H-C J. E. Baker, WTC G-WBN L. S. Bryant, MOB 2R-WBN M. J. Burzynski, BR 4X-C C. C. Cross, LP 6A-C M. H. Dunn, ET 10A-K P. W. Harris, ADM IV-WBN J. C. Kammeyer, EQB lA-WBN NSRB Support, LP SM-C L. V. Parscale, ADM IB-WBN J. R. Rupert, LP 6A-C J. A. Scalice, LP GA-C K. W. Singer, LP 6A-C R. J. Vander Grift, EQB 2W-WBN J. A. West, MOB 2R-WBN Sequoyah Licensing Files, OPS 4C-SQN EDMS, WT 3B-K S:/site lic/shared/lrouse/submit/Response to Tritium RAI emailed dated l-28-2002.doc
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS NUCLEAR PLANT (WBN)
UNIT 1 DOCKET NO. 50-390 RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
- 1. In Part B.III.6.A.2 of Tennessee Valley Authority's August 20, 2001, submittal, TVA states that damage to more than 24 tritium producing burnable absorber rods contained in a consolidation canister is precluded for all credible impact scenarios. What is the basis for this?
TVA Response:
An analysis completed by Pacific Northwest National Laboratories (PNNL) has demonstrated that no TPBAR cladding failures are expected to occur during an impact event. The evaluation of TPBAR cladding stress is based on a canister loaded with TPBARs traveling at forty feet per minute (FPM) impacting onto a rigid surface. Forty FPM is based on a maximum uncontrolled lowering hook speed of the Spent Fuel Pool hoist. TPBAR stresses resulting from feasible impact events (e.g. canister impact with a fuel rack, weir gate, pool wall, Consolidation Fixture, etc.) are bounded by the rigid surface impact evaluations. The canister and handling system design and configuration limit the impact forces on the canister.
- 2. The licensee states that an analysis was not performed for a fuel assembly falling onto a loaded consolidation canister, therefore administrative and/or design features will be in place to preclude damage. What are the specific administrative and /or design features, and when will these be implemented?
TVA Response:
Implementation of TVA's tritium program will result in the following administrative controls:
Existing fuel storage cells will be designated as consolidation canister storage locations. These consolidation storage locations will be located on the outside row near one corner of the fuel pool away from any fuel movement path. At WBN, these locations will be restricted from any other use while the TPBARs are contained in the spent fuel pool. Fuel storage cells immediately adjacent to the designated canister storage locations may E-1
remain empty or may contain new fuel or spent fuel assemblies. In any event, fuel movement procedure controls put into place as a result of the tritium program will prevent movement directly over the canisters.
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