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MONTHYEARML1013401882010-06-0808 June 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Areva Fuel Mechanical Design Report Project stage: Withholding Request Acceptance ML1013802442010-06-0808 June 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Thermal-Hydraulic Design Report Project stage: Withholding Request Acceptance ML1025202302010-09-24024 September 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, GE14 Fuel Thermal Mechanical Information Project stage: Withholding Request Acceptance ML1025203012010-11-0404 November 2010 Letter Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Unit 1 Cycle 9 Reload Safety Analysis for 105% Original Licensed Thermal Power Project stage: Withholding Request Acceptance ML1101805852011-01-24024 January 2011 Request for Additonal Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Other ML1105900542011-02-23023 February 2011 Response to NRC Request for Additional Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Response to RAI ML11095A0732011-03-28028 March 2011 Request for Additional Information Regarding a Request to Transition to Areva Fuel Project stage: RAI ML11136A1872011-04-26026 April 2011 NRR E-mail Capture - Audit Results Summary Report Supporting TAC ME3775 - BF1 Areva Fuel Transition and Related BF2/3 Request Project stage: Other ML11137A1992011-05-12012 May 2011 Response to NRC Request for Additional Information Regarding to Transition to Areva Fuel Project stage: Response to RAI ML11159A0412011-06-0707 June 2011 NRR E-mail Capture - Audit Results Summary Report Supporting TAC ME3775 - BF1 Areva Fuel Transition and Related BF2/3 Request Project stage: Other ML11234A0042011-08-23023 August 2011 Request for Additional Information Regarding Technical Specification TS-473, Areva Fuel Transition Project stage: RAI ML11286A1072011-10-0707 October 2011 Response to NRC Request for Additional Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Response to RAI ML12018A3762012-01-23023 January 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12083A0012012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML1208300592012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775) (TS-473) Project stage: Withholding Request Acceptance ML12083A0032012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12083A0142012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (GEH-Harrison) (TAC No. ME3775) (TS-473) Project stage: Withholding Request Acceptance ML12100A1032012-04-11011 April 2012 Audit Report Regarding Tennessee Valley Authority Browns Ferry, Unit 1 Areva Fuel Transition Emergency Core Cooling System Evaluation Model Application (TAC No. ME3775) (Np) Project stage: Other ML12108A2482012-04-17017 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12114A0042012-04-18018 April 2012 Supplement to License Amendment Request to Transition to Areva Fuel Project stage: Supplement ML12129A1492012-07-0303 July 2012 Issuance of Amendment Regarding the Transition to Areva Fuel (TAC No. ME3775) (TS-473) Project stage: Approval ML13010A0162013-01-0404 January 2013 CFR 50.46 30-Day Report Project stage: Other 2011-05-12
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 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 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 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 ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:Technical Specifications
MONTHYEARML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20190A1052020-08-11011 August 2020 Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe ML16330A1582017-01-17017 January 2017 Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality ML16028A4142016-04-26026 April 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15317A4782016-02-0909 February 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15344A3212016-01-0707 January 2016 Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits ML15321A4722015-12-23023 December 2015 Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation ML15287A2132015-12-16016 December 2015 Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits ML15324A2472015-12-14014 December 2015 Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control ML15287A3712015-12-0404 December 2015 Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029) ML15212A7962015-10-28028 October 2015 Issuance of Amendments to Transition to Fire Protection Program NFPA-805 ML15251A5402015-09-29029 September 2015 Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0 CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. ML15065A0492015-06-0202 June 2015 Issuance of Amendment Revising Pressure and Temperature Limit Curves CNL-15-070, Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-4852015-05-29029 May 2015 Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-485 CNL-15-019, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501) CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) CNL-15-033, License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use2015-02-12012 February 2015 License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use CNL-14-156, Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules2014-09-18018 September 2014 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules NL-14-081, Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Fer2014-05-16016 May 2014 Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferr CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry2014-05-16016 May 2014 Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-148, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-126, Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-4852013-11-22022 November 2013 Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-485 ML13199A2212013-08-30030 August 2013 Issuance of Amendments Re. Deletion of References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25% Extension of Surveillance Intervals ML13092A3932013-03-27027 March 2013 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) (Technical Specification Change TS-480) ML13070A3072013-02-28028 February 2013 Technical Specification Change TS-478 - Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, & 3, & Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 Xm Fuel ML11189A2172012-07-30030 July 2012 Issuance of Amendments Regarding Request to Add Technical Specification 3.7.3, Control Room Emergency Ventilation System, Action to Address Two Crev Subsystems Inoperable ML12114A0042012-04-18018 April 2012 Supplement to License Amendment Request to Transition to Areva Fuel ML1011601532010-04-16016 April 2010 Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request ML0923700452009-11-19019 November 2009 Issuance of Amendments Regarding Technical Specification Improvement to Adopt Technical Specification Task Force (TSTF) TSTF-476, Revision 1 ML0931001212009-10-31031 October 2009 Attachment 19, Browns Ferry Unit 1 -Technical Specification Change 467, ANP-2638NP, Revision 2, Applicability of Areva Np BWR Methods to Extend Power Uprate Conditions ML0931402652009-10-31031 October 2009 Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis Report 2023-01-25
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Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 April 18, 2012 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Supplement to License Amendment Request to Transition to AREVA Fuel
References:
- 1. Letter from TVA to NRC, "Technical Specification Change TS-473, AREVA Fuel Transition," dated April 16, 2010
- 2. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Unit 1 -
Request for Additional Information Regarding Technical Specification TS-473, AREVA Fuel Transition," dated August 23, 2011
- 3. Letter from TVA to NRC, "Response to NRC Request for Additional Information Regarding Amendment Request to Transition to AREVA Fuel," dated October 7, 2011 On April 16, 2010, the Tennessee Valley Authority (TVA) submitted Technical Specification (TS) change TS-473 to request the Nuclear Regulatory Commission's (NRC) approval of a license amendment request to add the AREVA NP analysis methodologies to the list of approved methods to be used in determining the core operating limits in the Core Operating Limits Report (COLR). Additional TS changes were also requested to reflect the AREVA NP specific methods for monitoring and enforcing of the thermal limits.
On August 23, 2011, TVA received a Request for Additional Information (RAI) letter from the NRC (Reference 2) containing seven questions related to TS Change TS-473.
The NRC expressed concerns regarding the application of the AREVA methodology as it relates to the most limiting Loss of Coolant Accident (LOCA) Analysis. In order to Printed on,reoydled paper iy
U.S. Nuclear Regulatory Commission Page 2 April 18, 2012 resolve this concern, AREVA made changes to the EXEM BWR-2000 ECCS Evaluation Model. This change also required an update to the LOCA Break Spectrum Analysis provided in the Reference 1 submittal. This updated LOCA analysis report was provided in an RAI response dated October 7, 2011.
During a telephone call with the Browns Ferry Nuclear Plant (BFN) Project Manager on March 28, 2012, the NRC indicated that the technical review has concluded that the new analysis should be processed as a BFN Unit 1 Specific Methodology.
In order to incorporate the Unit 1 specific approval, item 16 of the TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR), will be revised to reference the NRC Approved Safety Evaluation. Reference 11 of TS Bases 3.2.1, AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR), will also be revised to incorporate the reference to the NRC Safety Evaluation described above. Additionally, based on feedback from the NRC technical reviewer, all of the methodology references in TS 5.6.5 are required to have a revision number and revision dates in the TS. This position was documented in a letter from the NRC to the TS Task Force, dated August 4, 2011. The enclosure to this letter provides the supplement in the form of revised proposed TS and TS Bases pages. Attachments 1 through 4 of this enclosure replace the respective pages from Attachments 1 through 4 of the enclosure to the Reference 1 letter.
TVA has determined that the supplemental information provided by this letter does not affect the evaluation of significant hazards considerations associated with the proposed TS changes provided in the Reference 1 letter. The proposed TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).. Additionally, in accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and the enclosures to the Alabama Department of Public Health.
There are no new regulatory commitments in this submittal.
Please direct any questions concerning this matter to Tom Hess at (423) 751-3487.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 18th day of April 2012 Corporate Nuclear Licensing
U.S. Nuclear Regulatory Commission Page 3 April 18, 2012 Manager, Corporate Nuclear Licensing
Enclosure:
Browns Ferry Nuclear Plant (BFN), Unit 1, Supplement to Technical Specifications (TS) Change 473 cc (Enclosure):
NRC Regional Administrator- Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health
ENCLOSURE Browns Ferry Nuclear Plant Unit 1 Supplement to Technical Specifications Change 473
Attachment 1 Browns Ferry Nuclear Plant Unit 1 Supplement to Technical Specifications Change 473 Proposed Technical Specifications Page - Markups
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 (Deleted).
5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(1) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; apd (4))(.-The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM)
Upscale, for Specification 3.3.1.1; and (5) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: .NEDE-24011 P A, "General El*ectrc Standard Application f r RoPcto,,-,r Fuel," (lat+t approvov orsion fr BN*).
- 1. NEDE-24011-P-A, Revision 16, General Electric Standard Application for Reactor Fuel, October 2007.
- 2. XN-NF-81-58(P)(A) Revision 2 and Supplements I and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
(continued)
BFN-UNIT 1 5.0-24 Amendment No. 234, 239, 252,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 3. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
- 4. EMF-85-74(P) Revision 0 Supplement I(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
- 5. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
- 6. XN-NF-80-19(P)(A) Volume I and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
- 7. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
- 8. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURNB2, Siemens Power Corporation, October 1999.
- 9. XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
(continued)
BFN-UNIT 1 5.0-24a Amendment No. 234, 2-9, 2,52,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 10.XN-NF-84-105(P)(A) Volume 1 and Volume I Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
11.ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
12.ANF-913(P)(A) Volume 1 Revision I and Volume I Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
- 13. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
- 14. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 15. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
- 16. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated [insert SE approval date], 2012
- 17. EMF-2292(P)(A) Revision 0, ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
(continued)
BFN-UNIT 1 5.0-24b Amendment No. 2-34, 2-39, 252,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 18. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
- 19. BAW-1 0255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
(continued)
BFN-UNIT 1 5.0-24c Amendment No. 2-4, 249, 2-2,
Attachment 2 Browns Ferry Nuclear Plant Unit 1 Supplement to Technical Specifications Change 473 Proposed Technical Specifications Bases Pages - Markups
APLHGR B 3.2.1 BASES SURVEILLANCE SR 3.2.1.1 (continued)
REQUIREMENTS operation. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowance after THERMAL POWER
> 25% RTP is achieved is acceptable given the large inherent margin to operating limits at low power levels.
REFERENCES 1. NEDE-24011-P-A-1-3, Revision 16, "General Electric Standard Application for Reactor Fuel," October 2007August 1996.
- 2. FSAR, Chapter 3.
- 3. FSAR, Chapter 14.
- 4. FSAR, Appendix N.
- 5. NEDC-32484P, "Browns Ferry Nuclear Plant Units 1, 2, and 3, SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,"
Revision 2, December 1997.
- 6. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
- 7. NEDC-32433P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Units 1,2, and 3," April 1995.
- 8. NEDO-30130-A, "Steady State Nuclear Methods," May 1985.
- 9. NEDO-24154, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," October 1978.
- 10. NEDO-24236, "Browns Ferry Nuclear Plant Units 1,2, and 3, Single-Loop Operation," May 1981.
- 11. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation [insertSE approvaldate], 2012.
(continued)
BFN-UNIT 1 B 3.2-5 R-easiem 40 Amendment No. 236,
Attachment 3 Browns Ferry Nuclear Plant Unit 1 Supplement to Technical Specifications Change 473 Proposed Technical Specifications Pages - Retyped
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6A4 (Deleted).
5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(1) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; (4) The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM) Upscale, for Specification 3.3.1.1; and (5) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, Revision 16, General Electric Standard Application for Reactor Fuel, October 2007.
- 2. XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
(continued)
BFN-UNIT 1 5.0-24 Amendment No. 2,34, 2-39, 252,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 3. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
- 4. EMF-85-74(P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
- 5. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
- 6. XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.
- 7. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
- 8. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURNB2, Siemens Power Corporation, October 1999.
- 9. XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
(continued)
BFN-UNIT 1 5.0-24a Amendment No. 2-4, 2-9, 2,52,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 10.XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
11.ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
12.ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
- 13. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
- 14. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 15. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
- 16. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated [insert SE approval date], 2012
- 17. EMF-2292(P)(A) Revision 0, ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
(continued)
BFN-UNIT 1 5.0-24b Amendment No. 2-34, 2-3, 2-2,
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 18. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
- 19. BAW-1 0255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
(continued)
BFN-UNIT 1 5.0-24c Amendment No. 2-,4, 2-3, 2-52,
Attachment 4 Browns Ferry Nuclear Plant Unit 1 Supplement to Technical Specifications Change 473 Proposed Technical Specifications Bases Pages - Retyped
APLHGR B 3.2.1 BASES SURVEILLANCE SR 3.2.1.1 (continued)
REQUIREMENTS operation. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowance after THERMAL POWER
_>25% RTP is achieved is acceptable given the large inherent margin to operating limits at low power levels.
REFERENCES 1. NEDE-24011-P-A, Revision 16, "General Electric Standard Application for Reactor Fuel," October 2007.
- 2. FSAR, Chapter 3.
- 3. FSAR, Chapter 14.
- 4. FSAR, Appendix N.
- 5. NEDC-32484P, "Browns Ferry Nuclear Plant Units 1, 2, and 3, SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,"
Revision 2, December 1997.
- 6. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
- 7. NEDC-32433P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Units 1, 2, and 3," April 1995.
- 8. NEDO-30130-A, "Steady State Nuclear Methods," May 1985.
- 9. NEDO-24154, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," October 1978.
- 10. NEDO-24236, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Single-Loop Operation," May 1981.
- 11. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation [insert SE approvaldate], 2012.
(continued)
BFN-UNIT 1 B 3.2-5 Re 4G Amendment No. 2-36,