BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations
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| ML24057A307 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/29/2024 |
| From: | Constellation Energy Generation |
| To: | NRC/RGN-III |
| Shared Package | |
| ML24057A301 | List: |
| References | |
| BW240007 BW-MISC-062, Rev 0 | |
| Download: ML24057A307 (1) | |
Similar Documents at Braidwood | |
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Category:Calculation
MONTHYEARBW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024
[Table view]Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML19269C0942019-09-24024 September 2019 54017-CALC-01, Braidwood Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML19269C0982019-09-24024 September 2019 54018-CALC-01, Byron Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML19121A4642019-05-0101 May 2019 CY-BR-170-301, Revision 10, Offsite Dose Calculation Manual. RS-15-236, Areva Calculation 32-9244434-000, Revision 0, Byron and Braidwood RVCH Nozzle As-Left J-Groove Analysis.2015-07-29029 July 2015 Areva Calculation 32-9244434-000, Revision 0, Byron and Braidwood RVCH Nozzle As-Left J-Groove Analysis. RS-15-236, Areva Calculation 32-9244389-000, Revision 0, Byron/Braidwood RVCH Nozzle Idtb Repair Weld Anomaly.2015-07-29029 July 2015 Areva Calculation 32-9244389-000, Revision 0, Byron/Braidwood RVCH Nozzle Idtb Repair Weld Anomaly. ML15259A0502015-07-29029 July 2015 Areva Calculation 32-9244389-000, Revision 0, Byron/Braidwood RVCH Nozzle Idtb Repair Weld Anomaly. ML14120A0402014-02-14014 February 2014 Attachment 4, Braidwood Station, Units 1 and 2 - Calculation 19-AN-29, Revision 002B, Second-Level Undervoltage Relay Setpoint ZS-2014-0100, Offsite Dose Calculation Manual2013-12-31031 December 2013 Offsite Dose Calculation Manual ML14132A3102013-07-31031 July 2013 CY-BR-170-301, Revision 8, Offsite Dose Calculation Manual (ODCM) ML13134A0482013-04-30030 April 2013 CY-BR-170-301, Rev. 7, Offsite Dose Calculation Manual. ML12130A1992012-04-26026 April 2012 Offsite Dose Calculation Manual (Odcm), CY-BR-170-301, Rev. 6 ML11122A1102011-04-29029 April 2011 CY-BR-170-301, Revision 5, Offsite Dose Calculation Manual (Odcm). RS-10-051, Submittal of Decommissioning Funding Assurance Calculations2010-03-10010 March 2010 Submittal of Decommissioning Funding Assurance Calculations ML0929301352009-10-0909 October 2009 Attachment 2, Braidwood Station, Unit 1, Lug Stress Calculation for 1MS06007S ML0511203392004-12-31031 December 2004 Offsite Dose Calculation Manual for 2004 ML0600401022004-11-30030 November 2004 Rev. 1 to BYR04-049 & BRW-04-0043-M, Re-Analysis of Locked Rotor Accident (LRA) Using Alternative Source Terms. ML0600401002004-11-30030 November 2004 Rev. 1 to BYR04-048 & BRW-04-0042-M, Re-Analysis of Steam Generator Tube Rupture Accident Using Alternative Source Terms. ML0600400852004-11-30030 November 2004 Design Analysis BYR04-050, BRW-04-0044-M, Revision 1 (CC-AA-309-1001, Revision 1), Calculation of Alternative Source Term Onsite and Offsite Atmospheric Dispersion Coefficient. ML0600400492004-11-30030 November 2004 Rev. 1 to BYR04-045 & BRW-04-0039-M, Re-Analysis of Control Rod Ejection Accident (Crea) Using Alternative Source Terms. ML0600401052004-11-29029 November 2004 Rev. 1 to BYR04-047 & BRW-04-0041-M, Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms. ML0600401012004-11-29029 November 2004 Rev. 1 to BYR04-046 & BRW-04-0040-M, Re-Analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms. ML0706002112003-01-17017 January 2003 GE # Index 9-3, Rev. 1; an ASME Section Viii Evaluation of Oc Drywell for Without Sand Case Part 1 Stress Analysis, 2/91 ML0609605552001-01-31031 January 2001 Revision 5 of Table 11a (Continued) Teen Inhalation Dose Factors 2024-02-29 Category:Meeting Briefing Package/Handouts MONTHYEARML24100A7672024-04-11011 April 2024
[Table view]Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations 2024-04-09 Category:Report MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024
[Table view]License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed BW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024 EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24094A2702024-04-0303 April 2024 MDMP Deviation Form ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-12-0707 December 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16250A5182016-04-30030 April 2016 Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds ML16014A1882016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015 Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application 2024-05-28 Category:Technical MONTHYEARBW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024
[Table view]EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-12-0707 December 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) ML16250A5182016-04-30030 April 2016 Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015 Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology RS-14-064, Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report2014-03-31031 March 2014 Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report RS-14-064, Section 5 - Summary of Regulatory Commitments2014-03-31031 March 2014 Section 5 - Summary of Regulatory Commitments ML14091A0062014-03-31031 March 2014 Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report RS-14-082, ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report2014-02-27027 February 2014 ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report ML14119A3772014-02-13013 February 2014 Enclosure 1 to RS-14-034 - Update Transmittal 2 (Annex B) Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic RS-12-159, Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 12014-02-13013 February 2014 Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 1 ML13338A6242013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Braidwood Station, Units 1 and 2, TAC Nos.: MF0895 and MF0896 ML11206B1802011-07-20020 July 2011 ARS1-11-01372 - Braidwood Water Sample Results ML12083A1232011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). RS-12-023, WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5).2011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). ML1117900382011-06-23023 June 2011 Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1117900422011-06-21021 June 2011 Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1110902792011-04-15015 April 2011 ARS1-10-02678, Revised Laboratory Analysis Report. ML0925202652009-09-0404 September 2009 Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) ML0918110302009-06-30030 June 2009 Startup Report for the Installation of Areva Np, Inc. Advanced Mark-BW(A) Fuel Assemblies in Braidwood Unit 1 Cycle 15 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML17255A8412008-06-30030 June 2008 Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted2008-06-30030 June 2008 Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. 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