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MONTHYEARML0335803722003-11-20020 November 2003 and 11/20/2003 Slides, Braidwood Unit 2 Refuel 10 Fall 2003 Stream Generator Inspection Results Summary Project stage: Other ML0335800562004-01-15015 January 2004 and 11/20/2003 Summary of Conference Call with Exelon Nuclear Regarding the 2003 Steam Generator Inspections at Braidwood Unit 2 Project stage: Other 2003-11-20
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Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 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 NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides 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 ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs 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 ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections 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 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 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 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 ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML15135A4262015-05-19019 May 2015 EOC Public Meeting Slides ML15104A4932015-04-14014 April 2015 Preliminary Site-Specific Results of the Environmental Review for Braidwood Station License Renewal ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14177A6412014-06-23023 June 2014 UHS Pre-submittal Meeting Presentation ML13249A1892013-09-0404 September 2013 ILRT Extension LAR Pre-submittal Meeting Slides ML13224A2882013-08-12012 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting Licensee Presentation ML13224A2922013-08-0808 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting NRC Presentation ML13107A0532013-04-23023 April 2013 Pre-Submittal Meeting MSIV Actuators Slides ML12227A5172012-08-14014 August 2012 Licensee End-of-Cycle Public Meeting Slides ML12227A5332012-08-14014 August 2012 NRC End-of-Cycle Slide Presentation 2024-01-08
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Braidwood Unit 2 Refuel 10 Fall 2003 Steam Generator Inspection Results Summary November 20, 2003 1
Braidwood I Seabrook Indication Comparison Item Braidwood 2 1 Seabrook Notes Tubing Material Alloy 6001T Alloy 6001T
~u~ing~~Size 0750 OD X0.043 t 0.688 OD x 0.040 t Tubing Manufacturer W-Blairsville W-Blairsville Same process, except dimensions Date of Tubing Manufacture February-April 1980 Apnl-July 1980 Contiguous manufacturing schedules Operating Temperature 610.4°F 616.5°F First Incidence of ODSCC 12.68 EFPY 9.71 EFPY First reported incidence Indication Parameters R21C50-03H R5C62-04H All parameters apply for a single indication Max Bobbin Volts 0.34 0.91 Max +Point Volts 0.41 1.24 Max Length 0.73 in. 0.73 in.
Max Depth from NDE 47% (Volt Based) 66% (Volt Based) Destructi~eexam showed max depth 99 5%
PDA 335 386 Pressure Prediction (137.37 ksi) 7830 psi 6948 psi Tested to 6480 psi w/o burst (137.37 ksi)
- 1) Lengths are based on zero depth beginning to zero depth ending.
- 2) Seabrook pressures were scaled from an Sy+Su of 148.4 ksi at 650°Fto the 137.37 ksi value used for Braidwood 2.
The latter being the average in the Westinghouse database.
2
Preheater Region Feedwater Area where backing bars found 3
Refuel 10 Final Results
- 1 ODSCC at TSP 2 Preventative No Degradation (Low Row Screened as High Residual Stress)
- 2 AVB Wear 3 Plugged and Stabilized due to secondary side foreign object (Bushing)
- SG B (39 Tubes Plugged) 13 Plugged and Stabilized due to failed fit-up bars on secondary side 22 Plugged and Stabilized as a contingency in case in- place fit-up bars were to fail 4 Plugged and Stabilized due to weld slag on secondary side
- 2 ODSCC at TSP 1 Preventative No Degradation (Low Row Screened as High Residual Stress)
- 7 AVB Wear
- 1 AVB Wear
- Total Tubes Plugged to Date = 180 0.98% 4