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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 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 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 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 ML0933507402009-01-0505 January 2009 Request for Information Regarding the Tritium Producing Burnable Absorber Rods (Tac No. ME2775) Project stage: RAI 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:Environmental Assessment
MONTHYEARML20087M0082020-04-24024 April 2020 Staff Assessment of Flooding Focused Evaluation (EPID L-2019-JLD-0011) (Public) ML18332A0142019-02-0606 February 2019 Environmental Assessment and Finding of No Significant Impact Related to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, ML16138A0202016-06-23023 June 2016 Environmental Assessment and Finding of No Significant Impact Related to License Amendment Request to Revise Technical Specification 4.2.1, Fuel Assemblies ML12192A6072011-06-22022 June 2011 TVA 2011 Environmental Assessment ML12199A1782010-03-31031 March 2010 TVA 2010 John Sevier Fossil Plant EA ML0935801862010-01-14014 January 2010 Environmental Assesment and Finding of No Significant Impact (TAC Nos. ME20601 and ME2602) ML0935801822010-01-14014 January 2010 Environmental Assessment and Finding of No Significant Impact ML12192A3682009-12-0909 December 2009 Tennessee Department of Health Public Health Assessment 2009 ML0815000302008-06-20020 June 2008 Environmental Assessment and Findings of No Significant Impact for Extension of Construction Permit (Tac No. MD8389) ML0531803512005-12-19019 December 2005 Environment Assessment, EP Scheduler Exemption (TAC Mc 8592) ML12170A1742005-04-30030 April 2005 Replacement of Steam Generators 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 2020-04-24
[Table view] Category:Finding of No Significant Impact
MONTHYEARML0935801862010-01-14014 January 2010 Environmental Assesment and Finding of No Significant Impact (TAC Nos. ME20601 and ME2602) ML0935801822010-01-14014 January 2010 Environmental Assessment and Finding of No Significant Impact ML0815000302008-06-20020 June 2008 Environmental Assessment and Findings of No Significant Impact for Extension of Construction Permit (Tac No. MD8389) ML0531803512005-12-19019 December 2005 Environment Assessment, EP Scheduler Exemption (TAC Mc 8592) 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 2010-01-14
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
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Text
August 20, 2002 Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR INCORE IRRADIATION SERVICES FOR THE U.S. DEPARTMENT OF ENERGYS TRITIUM PRODUCTION PROGRAM (TAC NO. MB1884)
Dear Mr. Scalice:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment of August 20, 2001, as supplemented by letters of October 29, November 14, November 21, December 7, December 19, 2001, and January 14, February 19, February 21, May 21, May 23, and July 30, 2002. The proposed amendment would allow Watts Bar Nuclear Plant, Unit 1, to insert up to 2304 tritium-producing burnable absorber rods into the reactor core each fuel cycle. The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
L. Mark Padovan, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Environmental Assessment cc w/encl: See next page
ML022320905
- See previous concurrence OFFICE PDII-2/PM PDII-2/PM PDII-2/LA RLEP/ES /SC
NAME MPadovan MPadovan BClayton BZalcman for JHeck KJabbour for RHernan JTappert DATE 8/20/02 8/20/02 8/20/02 8/16/02 8/19/02 8/20/02 7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. NPF-90 held by the Tennessee Valley Authority (TVA or the licensee) for operation of the Watts Bar Nuclear Plant (WBN), Unit 1, located in Rhea County, Tennessee. Therefore, as required by Title 10, Code of Federal Regulations (10 CFR), Section 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would change WBNs Technical Specifications to allow TVA to irradiate up to 2304 tritium-producing burnable absorber rods (TPBARs) in WBNs reactor core.
Irradiating the TPBARs in the reactor core supports the U.S. Department of Energy (DOE) in maintaining the nations tritium inventory. TVA will insert the TPBARs into positions in the reactor core where conventional burnable poison rods would normally be (poison rods contain boron which reacts with neutrons making them unavailable for interacting with uranium atoms, thereby slowing fission and heat generation). TPBARs are not reactor fuel and do not generate thermal energy for generating electrical energy.
TPBARs use lithium rather than boron. Neutron irradiation in the reactor core converts
2 the lithium in the TPBARs into tritium. After one operating cycle, TVA would remove the fuel assemblies containing TPBARs from the WBN core and put them into the spent fuel pool. TVA would, after several weeks (based on plant schedules rather than decay considerations),
remove the irradiated TPBARs from the fuel assemblies and consolidate them into shipping casks for DOE to transport to its tritium extraction facility at its Savannah River Site.
The proposed action is in accordance with the licensees application of August 20, 2001, as supplemented by letters of October 29, November 14, November 21, December 7, December 19, 2001, and January 14, February 19, February 21, May 21, May 23, and July 30, 2002.
The Need for the Proposed Action:
The proposed action would allow WBN to provide irradiation services for DOE to maintain the nations tritium supply as prescribed by Public Law (PL) 106-65. Section 3134 of PL 106-65 directs the Secretary of Energy to produce new tritium at TVAs Watts Bar power plant.
Environmental Impacts of the Proposed Action:
DOEs Environmental Impact Statement, DOE/EIS-0288, Final Environmental Impact Statement (EIS) for the Production of Tritium in a Commercial Light Water Reactor, dated March 1999, assessed the environmental impacts of producing tritium at WBN. TVA was a cooperating Federal agency in preparing this EIS and adopted the EIS in accordance with 40 CFR 1506.3(c) of the Council on Environmental Quality regulations. DOE also prepared a Tritium Production Core (TPC) Topical Report, NDP-98-181, Rev. 1, to address the safety and licensing issues associated with incorporating TPBARs in a reference pressurized-water reactor. The NRC used its Standard Review Plan (NUREG-0800) as the basis for evaluating the impact of the TPBARs on a reference plant. The NRC reviewed the TPC Topical Report
3 and issued a Safety Evaluation Report, NUREG-1672, in May 1999. NUREG-1672 identified 17 plant-specific interface issues that a licensee would have to address in support of a plant specific amendment to operate a tritium production core. TVAs application of August 20, 2001, and supplements, addressed these interface issues. NRC staff is reviewing TVAs amendment request and will issue a safety evaluation documenting its review.
- 1. Radiological Impact from Tritium Release to the Reactor Coolant System (RCS) Under Normal Plant Operations with 2304 TPBARs in the Core Tritium levels in the RCSs of large pressurized-water reactors have ranged as high as 4000 curies per year (Ci/yr) without exceeding regulatory limits. TVA estimated, as discussed in its May 23, 2002, letter, that the tritium level in the RCS at WBN would increase from about 1826 Ci/yr to 3170 Ci/yr with 2304 TPBARs in the reactor. This increased tritium level could increase overall occupational exposure, but NRC data summarized in NUREG-0713, "Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, dated 1995, indicate tritium exposure is not an important contributor to overall occupational exposure.
TVA stated that WBN does not expect this increased activity to affect normal RCS feed-and-bleed operation throughout the cycle, as discussed in its May 23, 2002, letter. The NRC staff finds no reason to disagree with TVAs conclusion. Thus, primary coolant discharge volumes should be similar to current volumes.
The staff concludes that the additional dose rate from operating WBN with 2304 TPBARs in the reactor will not have a significant impact on TVAs ability to control worker radiation doses and keep them well within regulatory limits using the controls and practices in WBNs existing Radiation Protection Program.
If increased RCS feed and bleed is required, it may be necessary to temporarily store the increased volume of tritiated liquid onsite, or to dilute the tritiated liquid to ensure that
4 10 CFR Part 20 discharge limits are met. WBN has sufficient storage tanks to accommodate this additional liquid waste.
- 2. Radiological Impact from Liquid Effluents Under Normal Plant Operations with 2304 TPBARs in the Core The WBN facility has waste-treatment systems designed to collect and process waste that may contain radioactive material. The tritium in liquid effluents from WBN is diluted to a relatively low concentration before it reaches even the most highly exposed members of the public. TVAs submittal of May 23, 2002, shows that the total additional dose to the maximally-exposed members of the public within 50 miles of WBN from tritium in liquid effluents is estimated to be 0.01 millirem per year (mrem/yr). This total dose, considering the minimal increase from tritium production, is less than 1.0 percent of the NRC 3-mrem/yr guideline for effluent exposure to the public. The staff concludes that the potential radiological impact on plant workers, members of the public, and the environment from operation with the TPC complies with all regulatory dose limits.
- 3. Radiological Impact from Radioactive Gaseous Emissions Under Normal Plant Operations with 2304 TPBARs in the Core A portion of the tritium might be released to the atmosphere. The amount would depend on plant conditions and the manner in which TVA operates WBN. Individuals could be exposed to tritium in a variety of pathways if it was released to the atmosphere. These pathways include inhalation and skin absorption, as well as consumption of meat, vegetables and milk.
According to TVA, in its submittal of May 23, 2002, the calculated tritium dose to the most highly-exposed members of the public through all pathways would be about 63 percent of the NRC annual exposure guideline for airborne effluents.
5
- 4. Radiological Impact from Solid Radioactive Waste Under Normal Plant Operations with 2304 TPBARs in the Core Irradiation of TPBARs is expected to increase the number of curies and volume of solid radioactive waste, primarily because of disposal (offsite) of the associated base plates and thimble plugs, which become irradiated. The estimated increase in activity inventory is from approximately 1800 Ci/year to approximately 3500 Ci/yr. The estimated increase in volume is from 32,820 cubic feet/year to 32,853 cubic feet/year. The estimated resultant total worker dose resulting from handling the increased solid waste is approximately 1.1 percent of the dose assessment estimate of record. Offsite shipment and disposal would be in accordance with established agreements between TVA and DOE.
- 5. Radiological Impact to Workers in the Fuel Storage Area Under Normal Plant Operations with 2304 TPBARs in the Core The proposed amendment is not expected to significantly affect the doses to the workers in the fuel storage area. The TPBARs are designed to have minimal effect on plant operations, including refueling operations. Unirradiated TPBARs will produce no increase in exposure, occupational or public, because they are essentially non-radioactive. Possible increases in tritium airborne activity may increase dose to workers handling and consolidating radioactive TPBARs. However, TVA stated, in its submittal of May 23, 2002, that WBNs station dose assessment of record bounds the expected increase.
- 6. Non-Radiological Impact with 2304 TPBARs in the Core The proposal does not affect non-radiological plant effluents. The proposal does not result in any significant changes to land use or water use. It also does not result in any significant changes to the quantity or quality of effluents, and no effects on endangered or threatened species or on their habitat are expected. Therefore, no changes in, or different types of, non-radiological environmental impacts are expected as a result of the amendment.
6
- 7. Radiological Impact from Postulated Accidents with 2304 TPBARs in the Core TVAs submittal of May 23, 2002, discussed the effects of TPBARs on the possible consequences of the following postulated accidents discussed in WBNs Updated Final Safety Analysis Report (UFSAR):
- design basis loss-of-coolant accident (LOCA)
- main steamline failure outside of containment
- loss of normal alternating current power to plant auxiliaries
- waste gas decay tank failure
- failure of small lines carrying primary coolant outside containment Discussions of the postulated accidents with the greatest radiological consequences appear below.
- a. Fuel-Handling Accident This accident is defined as dropping a spent fuel assembly containing irradiated TPBARs resulting in rupture of the cladding on all the fuel rods. TVAs calculations conservatively assumed that 24 TPBARs (the maximum possible number) are in the dropped spent fuel assembly and that they all rupture and transfer their tritium to the spent fuel pool.
Releasing this activity to the (1) control room boundary, (2) Exclusion Area Boundary over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and (3) Low Population Zone over 30 days results in the doses to the thyroid, skin (beta),
whole body (gamma), and Total Effective Dose Equivalent (TEDE), as defined in 10 CFR Part 20, that are small percentages of regulatory limits.
- b. LOCA This accident is defined as losing reactor coolant at a rate in excess of the capability of
7 the reactor coolant makeup system. LOCAs could occur from breaks in pipes in the reactor coolant pressure boundary up to and including a break equivalent in size to the double-ended rupture of the largest pipe in the RCS. TVA conservatively assumed that the entire tritium content of the 2304 TPBARs is released into containment during a postulated LOCA.
Releasing this activity to the (1) control room boundary, (2) Exclusion Area Boundary over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and (3) Low Population Zone over 30 days results in doses to the thyroid, skin (beta),
whole body (gamma), and TEDE that are small percentages of regulatory limits.
- 8. Post-LOCA Hydrogen Generation Inside Containment TVAs submittal of August 20, 2001, stated that TPBARs could release additional hydrogen to the containment following a large-break LOCA (LBLOCA). WBN has emergency operating procedures in place to start a hydrogen recombiner train when the containment volumetric percentage of hydrogen reaches 3 percent. Previous analysis for a conventional (non-TPBAR) core in the WBN UFSAR indicated that for an LBLOCA, with no recombiners started, the containment hydrogen concentration reached 3.75 percent 4 days following event initiation. With additional hydrogen from the TPBARs, TVAs analysis indicated that the containment hydrogen concentration would only slightly increase 2 days following event initiation. If one recombiner train is started 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after event initiation for the TPBAR core, the peak containment hydrogen concentration is limited to less than 4 percent for up to 6 days.
Having up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to place a recombiner train in service to maintain the containment hydrogen concentration below 4 percent is adequate in satisfying NRC Regulatory Guide 1.7.
Accordingly, reactor operation with the TPBARs will not be a significant contributor to the post-LOCA hydrogen inventory, and will not have a significant impact on the total hydrogen concentration within the containment when compared to the values associated with the non-TPBAR core. The maximum containment hydrogen concentration can be maintained at less than the lower flammability limit of 4.0-volume-percent, with one recombiner train started at a
8 3-percent hydrogen concentration approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an LBLOCA.
Summary The Commission has completed its evaluation of the proposed action. The proposed action will not significantly increase the probability or consequences of accidents, no changes are being made in the types of effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential non-radiological impacts, the proposed action does not have a potential to affect historic sites. It does not affect non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no significant change in current environmental impacts. However, because there are no significant environmental impacts associated with this action, and because PL 106-65 directs that DOE produce tritium at WBN or the Sequoyah Nuclear Plant, this is not considered a viable option.
Alternative Use of Resources:
DOE evaluated the action, including completing construction of one or both of the Bellefonte Nuclear Plant Units and construction of an accelerator facility at the Savannah River site and concluded that the proposed alternative has the least environmental impact of the options considered. The NRC has no reason to disagree with DOEs decision.
Agencies and Persons Consulted:
On August 15, 2002, the staff consulted with the Tennessee State official, Debra Schults of the Tennessee Bureau of Radiological Health, regarding the environmental impact of
9 the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated August 20, 2001, as supplemented by letters dated October 29, November 14, November 21, December 7, December 19, 2001, and January 14, February 19, February 21, May 21, May 23, and July 30, 2002. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 20th day of August 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Mark Padovan, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Mr. J. A. Scalice Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Karl W. Singer, Senior Vice President Mr. Larry S. Bryant, Manager Nuclear Operations Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Spring City, TN 37381 Chattanooga, TN 37402-2801 Senior Resident Inspector Mr. James E. Maddox, Watts Bar Nuclear Plant Acting Vice President, U.S. Nuclear Regulatory Commission Engineering & Technical 1260 Nuclear Plant Road Tennessee Valley Authority Spring City, TN 37381 6A Lookout Place 1101 Market Street Rhea County Executive Chattanooga, TN 37402-2801 375 Church Street Suite 215 Mr. William R. Lagergren, Dayton, TN 37321 Site Vice President Watts Bar Nuclear Plant County Executive Tennessee Valley Authority Meigs County Courthouse P.O. Box 2000 Decatur, TN 37322 Spring City, TN 37381 Mr. Lawrence E. Nanney, Director General Counsel Division of Radiological Health Tennessee Valley Authority Dept. of Environment & Conservation ET 11A Third Floor, L and C Annex 400 West Summit Hill Drive 401 Church Street Knoxville, TN 37902 Nashville, TN 37243-1532 Mr. Robert J. Adney, General Manager Ms. Ann Harris Nuclear Assurance 341 Swing Loop Road Tennessee Valley Authority Rockwood, Tennessee 37854 6A Lookout Place 1101 Market Street Dr. Gary Drinkard Chattanooga, TN 37402-2801 340 Drinkard Dr.
Spring City, TN 37381 Mr. Mark J. Burzynski, Manager Nuclear Licensing Ms. Vickie G. Davis Tennessee Valley Authority TDEC-DOE Oversight Division 4X Blue Ridge 761 Emory Valley Road 1101 Market Street Oak Ridge, TN 37830-7072 Chattanooga, TN 37402-2801 Heinz Mueller [5 copies]
Mr. Paul L. Pace, Manager Environmental Review Coordinator Licensing and Industry Affairs US EPA Region 4 Watts Bar Nuclear Plant 61 Forsyth Street, SW.
Tennessee Valley Authority Atlanta, Georgia 30303-3104 P.O. Box 2000 Spring City, TN 37381