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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. | | {{#Wiki_filter:Three Mile Island Chapter 18.0 B&W Cross-Training Cross Training Course R-326C 1 |
| 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
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| circulation).
| | OBJECTIVES |
| 5.List the operational conditions which enhance natural circulation. Include which systems may be operated different from
| | : 1. 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. |
| | 3 Describe the decay heat removal methods 3. |
| | 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). |
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| normal conditions. | | OBJECTIVES |
| 6Listthesourcesofhydrogenandoxygen OBJECTIVES 6.List the sources of hydrogen and oxygen within the primary system and
| | : 5. List the operational conditions which enhance natural circulation. Include which systems may be operated different from normal conditions. |
| | 6 List the sources of hydrogen and oxygen 6. |
| | within the primary system and containment. |
| | : 7. Determine which RCS parameters can be used as possible indications of boiling (steam formation) within the system. |
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| 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 4 | | |
| Appendix -Sequence of Events 5 | | Appendix - Sequence of Events 5 |
| Appendix -Sequence of Events 6 | | |
| Appendix -Sequence of Events 7 | | Appendix - Sequence of Events 6 |
| Appendix -Sequence of Events 8 | | |
| Appendix -Sequence of Events 9 | | Appendix - Sequence of Events 7 |
| 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)}} | | |
| | Appendix - Sequence of Events 8 |
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| | Appendix - Sequence of Events 9 |
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| | Appendix - Sequence of Events 10 |
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| | Appendix - Sequence of Events 11 |
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| | Appendix - Sequence of Events 12 |
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| | Appendix - Sequence of Events 13 |
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| | Three Mile Island (Fig. 18-1) 14 T=0 Minutes (Fig. 18-2) 15 T=8 Minutes (Fig. 18-3) 16 T=1 Hour (Fig. 18-4) 17 T=2 Hours (Fig. 18-5) 18 T=16 Hours (Fig. 18-6) 19 TMI Radiation Release Path (Fig. 18-7) 20}} |
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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 18.0 B&W Cross-Training Cross Training Course R-326C 1
OBJECTIVES
- 1. 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.
3 Describe the decay heat removal methods 3.
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).
OBJECTIVES
- 5. List the operational conditions which enhance natural circulation. Include which systems may be operated different from normal conditions.
6 List the sources of hydrogen and oxygen 6.
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
Three Mile Island (Fig. 18-1) 14 T=0 Minutes (Fig. 18-2) 15 T=8 Minutes (Fig. 18-3) 16 T=1 Hour (Fig. 18-4) 17 T=2 Hours (Fig. 18-5) 18 T=16 Hours (Fig. 18-6) 19 TMI Radiation Release Path (Fig. 18-7) 20