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Category:Annual Operating Report
MONTHYEARWBL-24-021, Unit 2, Annual Radioactive Effluent Release Report2024-04-29029 April 2024 Unit 2, Annual Radioactive Effluent Release Report WBL-24-011, CFR 50.46 - Annual Report2024-03-21021 March 2024 CFR 50.46 - Annual Report WBL-23-013, 10 CFR 50.46 Annual Report for 20222023-03-29029 March 2023 10 CFR 50.46 Annual Report for 2022 WBL-22-008, 10 CFR 50.59 Summary Report2022-04-27027 April 2022 10 CFR 50.59 Summary Report WBL-22-012, Submittal of 10 CFR 50.46 - Annual Report for Watts Bar Nuclear Plant Units 1 and 22022-03-0202 March 2022 Submittal of 10 CFR 50.46 - Annual Report for Watts Bar Nuclear Plant Units 1 and 2 WBL-21-020, Annual Non-Radiological Environmental Operating Report - 20202021-04-20020 April 2021 Annual Non-Radiological Environmental Operating Report - 2020 WBL-21-009, 10 CFR 50.46 Annual Report for Watts Bar Nuclear Plant Units 1 and 22021-03-0404 March 2021 10 CFR 50.46 Annual Report for Watts Bar Nuclear Plant Units 1 and 2 WBL-20-007, 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant Units 1 and 22020-03-0505 March 2020 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant Units 1 and 2 L-19-019, Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 22019-03-0707 March 2019 Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 2 ML18115A0532018-04-25025 April 2018 Submittal of 10 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Watts Bar Nuclear Plant, Units 1 and 2, Independent Spent Fuel Storage Installation CNL-18-040, Transmittal of 10 CFR 50.46 - 30-Day and Annual Report2018-03-0707 March 2018 Transmittal of 10 CFR 50.46 - 30-Day and Annual Report ML17306A9892017-11-0202 November 2017 Submittal of 10 CFR 50.59 Summary of the Changes, Tests, and Experiments Implemented Report ML17067A0792017-03-0808 March 2017 Submittal of 10 CFR 50.46 - 30-Day and Annual Report CNL-16-057, Transmittal of l0 CFR 50.46 Annual Report2016-03-18018 March 2016 Transmittal of l0 CFR 50.46 Annual Report CNL-15-053, Combined 10 CFR 50.46 - 30-day and Annual Report of Changes and Errors to the Calculated Peak Cladding Temperature (PCT) for the Emergency Cooling Core System (ECCS) Evaluation Model2015-03-30030 March 2015 Combined 10 CFR 50.46 - 30-day and Annual Report of Changes and Errors to the Calculated Peak Cladding Temperature (PCT) for the Emergency Cooling Core System (ECCS) Evaluation Model ML14120A3212014-04-30030 April 2014 Annual Radioactive Effluent Release Report for 2013 ML14119A3322014-04-25025 April 2014 10 CFR 50.46 - Annual Report for 2013 CNL-14-035, CFR 50.46 30-Day Report of Changes & Errors to Calculated Peak Cladding Temperature2014-02-28028 February 2014 CFR 50.46 30-Day Report of Changes & Errors to Calculated Peak Cladding Temperature ML13140A0432013-05-15015 May 2013 Submittal of Annual Radiological Environmental Operating Report - 2012 ML13133A0032013-05-0808 May 2013 Annual Non-Radiological Environmental Operating Report - 2012 ML13120A0052013-04-25025 April 2013 10 CFR 50.46 - 30-Day Report and Annual Report for 2012 ML12137A8702012-05-15015 May 2012 Annual Radiological Environmental Operating Report - 2011 ML11126A1802011-04-28028 April 2011 2010 Annual Radioactive Effluent Release Report, Enclosure 1 ML1112505742011-04-27027 April 2011 Submittal of Annual Report of Changes or Errors Discovered in the Emergency Core Cooling System Evaluation Model for Year 2010 ML1109506832011-04-0101 April 2011 Submittal of Annual Insurance Status Report ML12221A3292010-12-31031 December 2010 City of Dayton Water Department - Annual Water Report Water Testing Performed in 2010 ML1036102792010-12-21021 December 2010 CFR 50.46 Annual Report for Model Year 2009 ML1013802962010-05-12012 May 2010 Annual Radiological Environmental Operating Report - 2009 ML0913902882009-04-30030 April 2009 Annual Radiological Environmental Operating Report ML0912603712008-12-31031 December 2008 Annual Radioactive Effluent Release Report ML0912603742008-01-15015 January 2008 Effluent and Waste Disposal Annual Report, Offsite Dose Calculation Manual ML0712803782007-05-0202 May 2007 Annual Radiological Environmental Operating Report for 2006 ML0712300822007-04-27027 April 2007 Enclosure 1, Watts Bar - 2006 Annual Radioactive Effluent Release Report for the Period January Through December 2006 ML0513803662005-04-30030 April 2005 Annual Environmental Radiological Operating Report ML0413902182004-05-14014 May 2004 Annual Radiological Environmental Operating Report - 2003 ML0413103712004-05-0505 May 2004 Unit 1 - 2003 Annual Nonradiological Environmental Operating Report (Aneor) ML0336000182003-12-18018 December 2003 Emergency Core Cooling System (ECCS) Evaluation Model Changes - 30 Day Report and Annual Report ML0314008112003-05-12012 May 2003 Annual Radiological Environmental Operating Report 2002 ML0214805002002-05-0808 May 2002 Annual Nonradiological Environmental Operating Report 2024-04-29
[Table view] Category:Letter
MONTHYEARML24219A0262024-08-12012 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 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 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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 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-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report 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) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML23319A2452024-01-29029 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) 2024-08-07
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 William R. Lagergren, Jr.
Site Vice President, Watts Bar Nuclear Plant December 18, 2003 U.S. Nuclear Regulatory Commission 10 CFR 50.46 ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - EMERGENCY CORE COOLING SYSTEM (ECCS) EVALUATION MODEL CHANGES - 30 DAY REPORT AND ANNUAL REPORT
References:
(1) TVA letter to NRC, February 21, 2003, "WBN Unit 1 - ECCS Evaluation Model Changes - 30 Day Report" (2) Westinghouse letter to TVA (WAT-D-11195), November 11, 2003, "Watts Bar Nuclear Plant Units 1 & 2, 10 CFR 50.46 Mid-Year Notification and Reporting for 2003," (Received November 18, 2003).
The purpose of this letter is notify the NRC of change or errors discovered in the WBN ECCS evaluation models for peak cladding temperature (PCT) in accordance with 10 CFR 50.46, and actions TVA is taking to address a change of more than 500 F in calculated PCT. This report includes model changes or errors since TVA's last report (Reference 1), and is intended to satisfy both the 30-day and annual reporting requirements of 10 CFR 50.46. As reported by Westinghouse in Reference 2, this change to WBN's ECCS evaluation model affects only the small break LOCA (SBLOCA) analysis, and is described in Enclosure 1.
The PCT margin allocations resulting from this change are summarized in Enclosure 2.
Pr-led m cd paper
U. S. Nuclear Regulatory Commission Page 2 December 18, 2003 As shown in Enclosure 2, the inclusion of this 350 F penalty results in a PCT of 1185 0 F (1305OF less 120OF Temporary SI Leakage to PRT which expired at the end of Cycle 5). This 1185 0 F PCT is considerably less than the 22000 F regulatory limit and is also below the previously evaluated and reported temporary PCT of 12700 F discussed in Reference 1.
This PCT assessment for SBLOCA, when combined with previously reported margin allocations of 240 F (Enclosure 2, Items A, B, and E.1), exceeds the threshold defined in 10 CFR 50.46(a)(3)(i) for a change of more than 500 F in calculated PCT. Therefore, TVA is reporting this change within the 30-day time period specified in 10 CFR 50.46. In accordance with 10 CFR 50.46(a)(3)(ii), TVA is required to provide a proposed schedule for providing a reanalysis or taking other actions needed to show compliance with 50.46 requirements for the changes or errors discussed above. A revised analysis is now in progress as part of the WBN replacement steam generator project. This analysis will be completed and become effective in support of the WBN Refueling Outage following Cycle 7 when the steam generators are replaced, currently scheduled for Fall 2006.
Accordingly, since the current model has significant margin to regulatory limits on peak clad temperature, WBN proposes that the staff accept the replacement generator analysis and schedule as meeting the requirement to provide a date for a replacement analysis.
Enclosure 3 lists the commitment for this submittal. If you have any questions about this change, please contact Paul Pace at (423) 365-1824.
Sincerely, W. R. Lagergr Enclosures
\cc: See page 3
U. S. Nuclear Regulatory Commission Page 3 December 18, 2003 cc (Enclosures):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, 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
ENCLOSURE 1 DESCRIPTION OF CHANGES WHICH AFFECT WBN'S EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL(S) AND ITS CALCULATION OF PEAK CLADDING TEMPERATURE NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections
Background
NOTRUMP was updated to resolve some inconsistencies in several drift flux models as well as the nodal bubble rise / droplet fall models. In summary, these changes include: Bubble rise and droplet fall model calculations were made consistent with flow link calculations. Corrections were made to limits employed in the vertical counter-current flooding models. Checking logic was added to correct situations where drift flux model inconsistencies could result (i.e., prevent no liquid from an all vapor node and no vapor from all liquid node.) Also, a more rigorous version of the Yea Drift Flux Model was implemented since the previous version of this model was incorrectly restricted to a 50% void fraction limit. This represents a closely-related group of Non-Discretionary Changes in accordance with WCAP Section 4.1.2 of WCAP 13451.
Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect Representative plant calculations using the NOTRUMP code demonstrate that the implementation of these corrections leads to a bounding 350 F increase of the calculated PCT for 10 CFR 50.46 purposes. As shown in the attached summary sheet, the inclusion of this penalty results in a PCT of 1185 0 F (1305OF less 120OF Temporary SI Leakage to PRT which expired at the end of Cycle 5).
This 11850 F PCT is considerably less than the 22000 F regulatory limit and is also below the previously evaluated temporary PCT of 12700 F discussed in Reference 1.
References
- 1. TVA letter to NRC, February 21, 2003, "WBN Unit 1 - ECCS Evaluation Model Changes - 30 Day Report"
- 2. Westinghouse letter to TVA (WAT-D-11195), November 11, 2003, "Watts Bar Nuclear Plant Units 1 & 2, 10 CFR 50.46 Mid-Year Notification and Reporting for 2003" El-1
ENCLOSURE 2
SUMMARY
OF PEAK CLADDING TEMPERATURE MARGIN ALLOCATIONS RESULTING FROM CHANGES TO THE EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL
Attachment 2 - PCT Rackups Our ref: WAT-D-I 1195 November 11, 2003 Westinghouse LOCA Peak Clad Temperature Summary for Small Break Plant Name: Watts Bar Unit I Utility Name: Tennessee Valley Authority Revision Date: 10/14/03 Analysis Information EM: NOTRUMP Analysis Date: 11/1/96 Limiting Break Size: 4 inch FQ: 2.5 FdH: 1.65 Fuel: Vantage + SGTP (%): 10 Notes: Mixed Core - Vantage + / Performance +
Clad Temp (F) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1126 1,2 MARGIN ALLOCATIONS (Delta PCT)
A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS I NOTRUMP Mixture Level Tracking / Region Depletion Errors 13 4 B. PLANNED PLANT CHANGE EVALUATIONS I Annular Blankets 10 3 C. 2003 PERMANENT ECCS MODEL ASSESSMENTS I . NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections 35 6 D. TEMPORARY ECCS MODEL ISSUES*
I None 0 E. OTHER I Tavg Uncertainty of 6 'F 2 Temporary Si Leakage to PRT 120 5 (a)
LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1305
- It is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to I CFR 50.46 reporting requirements.
References:
I WAT-D-10337, "Tennessee Valley Authority, Watts Bar Nuclear Plant, Final Safety Evaluation to Support Technical Specification Changes," March 5, 1997.
2 . WAT-D- 10356, Tennessee Valley Authority, Watts Bar Nuclear Plant Units I & 2, Final Report and Safety Evaluation for the 10/. SGTP Program," June 2, 1997.
3 WAT-D-10618, Tennessee Valley Authority, Wats Bar Nuclear Plant Unit 1, 10 CFR 50.46Annual Notification and Reporting for 1998," March 5,1999.
4 . WAT-D-10810, "Tennessee Valley Authority, Watts Bar Nuclear Plant Unit I, 10 CFR 50.46 Appendix K (BART/BASH/NOTRUMP) Evaluation Model Mid-Year Notification and Reporting for 2000." June 30, 2000.
5 WAT-D-1 1100, "Tennessee Valily Authority, Watts Bar Nuclear Plant Unit l, Evaluation of Ternporary SI Leakage to PRT," January 15, 2003.
6 WAT-D- 1195, "10 CFR 50.46 Mid-YearNotification and Reporting for2003," October2003.
Notes:
(a) PCT assessment for reduced SI flow due to SI leakage to PRT is applicable until the end of Cycle 5.
A BNFL Group company
ENCLOSURE 3 LIST OF COMMITMENTS TVA will perform a revised SBLOCA analysis as part of the WBN replacement steam generator project. This analysis will be completed and become effective in support of the WBN Refueling Outage following Cycle 7 when the steam generators are replaced, currently scheduled for Fall 2006.