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| | {{#Wiki_filter:Three Mile Island Chapter 18.0B&WCrossTrainingCourse 1 B&W Cross-Training Course R-326C OBJECTIVES1.Explain how a loss of feedwater resulted in a reactor trip and subsequent LOCA. 2.Describe the major radiation release paths which occurred at TMI-2. |
| | 3Describethedecayheatremovalmethods 3.Describe the decay heat removal methods used at TMI-2 during the transient. 4.Explain which parameters are used and how they indicate decay heat removal by natural circulation (or loss of natural |
| | |
| | circulation). |
| | 5.List the operational conditions which enhance natural circulation. Include which systems may be operated different from |
| | |
| | normal conditions. |
| | 6Listthesourcesofhydrogenandoxygen OBJECTIVES 6.List the sources of hydrogen and oxygen within the primary system and |
| | |
| | containment. 7.Determine which RCS parameters can be used as possible indications of boiling (steam formation) within the system. |
| | Appendix -Sequence of Events 4 |
| | Appendix -Sequence of Events 5 |
| | Appendix -Sequence of Events 6 |
| | Appendix -Sequence of Events 7 |
| | Appendix -Sequence of Events 8 |
| | Appendix -Sequence of Events 9 |
| | Appendix -Sequence of Events 10 Appendix -Sequence of Events 11 Appendix -Sequence of Events 12 Appendix -Sequence of Events 13 14Three Mile Island (Fig. 18-1) 15T=0 Minutes (Fig. 18-2) 16T=8 Minutes (Fig. 18-3) 17T=1 Hour (Fig. 18-4) 18T=2 Hours (Fig. 18-5) 19T=16 Hours (Fig. 18-6) 20TMI Radiation Release Path (Fig. 18-7)}} |
Revision as of 10:42, 4 August 2018
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Category:Training Manual
MONTHYEARML11221A3262011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML11221A3252011-07-0101 July 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML11216A2452008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events ML11216A0992008-07-0101 July 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events 2011-08-01
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24296B2132024-10-22022 October 2024 Slides for October 25, 2024, Meeting on Crane Clean Energy Center Regulatory Path to Restoring the Operating Reactor License Basis ML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning ML22301A1402022-10-28028 October 2022 1993 TMI Event - Jure Kutlesa, Security Specialist 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 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 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) ML20050H0232020-02-20020 February 2020 Presentation Slides for Meeting to Discuss Environmental Regulatory Approach to TMI-2 Decommissioning ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16070A1152016-03-11011 March 2016 Efforts to Improve Rulemaking Tracking and Reporting ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML14304A7832014-11-14014 November 2014 Public Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate ML14300A5452014-10-30030 October 2014 10/30/2014, Meeting Slide with NRC Regarding GL 2004-02 Close Out for Three Mile Island, Unit 1 ML13262A1492013-09-19019 September 2013 Enclosure 3- NRC Presentation Handout ML13262A1172013-08-28028 August 2013 Enclosure 4 - Scott Portzline Presentation ML12262A3352012-09-13013 September 2012 9.13.2012 TMI Alert Presentation Nreg 0654 Public Mtg ML12116A0482012-04-25025 April 2012 Aam ROP-12 Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1202501052012-01-25025 January 2012 Licensee Slides for 1/26/12 Meeting Three Mile Island, Unit 1 - Summary of Tube to Tube Wear Identified During T1R19 (Fall 2011) ML11221A3262011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML13197A0522011-04-19019 April 2011 FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 111 - Partial, Group Letter Bt. Part 5 of 7 ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007703672009-12-0707 December 2009 E-mail from J. White of USNRC to D. Screnci and J. Hawkins of USNRC, Regarding TMI NRC Slides.Ppt ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0910702242009-04-17017 April 2009 Riv Regional Administrator Presentation at Texas A&M University March 30, 2009, Three Mile Island - Impact on Safety Perspectives and Safety Belief ML0907508342009-03-16016 March 2009 Meeting Slides, Three Mile Island Annual Assessment Meeting 2008 Reactor Oversight Process ML11216A2452008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events ML0828805412008-10-14014 October 2008 Herbaceous Wetlands ML0826712092008-09-23023 September 2008 TMI Pre-Application Meeting - Control Rod Drive Control System Upgrade and Elimination of Axial Power Shaping Rods ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides ML0807906742008-03-19019 March 2008 Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program. ML0806700982008-03-0404 March 2008 License Renewal Process Overview Three Mile Island Unit 1 Public Meeting Handout 03/04/2008 ML0802501172008-01-15015 January 2008 1/15/2008 Slides from Drop-in Visit Exelon/Amergen ML0726404902007-08-14014 August 2007 TMI Intro ML0726404922007-08-14014 August 2007 TMI Tritium Update 08/07 - Slide Presentation ML0713701672007-04-30030 April 2007 Enclosure 2 (Slides) - 04/30/2007 Summary of Meeting with Amergen Energy Co., LLC, Regarding License Amendment Request Relating to the Insertion of New Area High Thermal Performance Fuel in the TMI-1 Reactor ML0710901582007-04-19019 April 2007 Aam Final Slides for Reactor Oversight Program 2006-07 Public Meeting 04/11/07 ML0726404942007-03-28028 March 2007 Unit 2 Accident - Presentation Slides ML0708513862007-03-26026 March 2007 Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 ML0716601022007-03-20020 March 2007 Slides to Counterparts Meeting with Exelon to Discuss Current and Planned Licensing Activities and Process - Correction 2024-02-13
[Table view] |
Text
Three Mile Island Chapter 18.0B&WCrossTrainingCourse 1 B&W Cross-Training Course R-326C OBJECTIVES1.Explain how a loss of feedwater resulted in a reactor trip and subsequent LOCA. 2.Describe the major radiation release paths which occurred at TMI-2.
3Describethedecayheatremovalmethods 3.Describe the decay heat removal methods used at TMI-2 during the transient. 4.Explain which parameters are used and how they indicate decay heat removal by natural circulation (or loss of natural
circulation).
5.List the operational conditions which enhance natural circulation. Include which systems may be operated different from
normal conditions.
6Listthesourcesofhydrogenandoxygen OBJECTIVES 6.List the sources of hydrogen and oxygen within the primary system and
containment. 7.Determine which RCS parameters can be used as possible indications of boiling (steam formation) within the system.
Appendix -Sequence of Events 4
Appendix -Sequence of Events 5
Appendix -Sequence of Events 6
Appendix -Sequence of Events 7
Appendix -Sequence of Events 8
Appendix -Sequence of Events 9
Appendix -Sequence of Events 10 Appendix -Sequence of Events 11 Appendix -Sequence of Events 12 Appendix -Sequence of Events 13 14Three Mile Island (Fig. 18-1) 15T=0 Minutes (Fig. 18-2) 16T=8 Minutes (Fig. 18-3) 17T=1 Hour (Fig. 18-4) 18T=2 Hours (Fig. 18-5) 19T=16 Hours (Fig. 18-6) 20TMI Radiation Release Path (Fig. 18-7)