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Category:Daily Event Report
MONTHYEARML1007805052009-12-23023 December 2009 Executive Team Daily Brief ML1007805442009-12-0202 December 2009 Executive Team Daily Brief ML1007805412009-11-27027 November 2009 Executive Team Daily Brief ML1007805402009-11-25025 November 2009 Executive Team Daily Brief ML1007805062009-11-24024 November 2009 Executive Team Daily Brief 2009-12-23
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning 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 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 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 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 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 ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML15238B6272015-08-26026 August 2015 Case Study Overview 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 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) ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML11090A0872011-04-0505 April 2011 Fire (a)(4) Tabletop Pilot Method and Results ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007805052009-12-23023 December 2009 Executive Team Daily Brief ML1007805442009-12-0202 December 2009 Executive Team Daily Brief ML1007805412009-11-27027 November 2009 Executive Team Daily Brief ML1007805402009-11-25025 November 2009 Executive Team Daily Brief ML1007805062009-11-24024 November 2009 Executive Team Daily Brief ML0929406112009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Proposed Control Rod Drive Control System License Amendment Request ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes 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 ML0906302662009-02-24024 February 2009 02/24/2009 Three Mile Island Nuclear Station, Unit 1, Dseis Meeting Presentation Slides Preliminary Results of the Three Mile Island Nuclear Station, Unit 1 License Renewal Environmental Review. ML0906302652009-02-24024 February 2009 Dseis Meeting Handouts 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. ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments 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 ML0735507162007-12-21021 December 2007 TMI Refueling Outage Performance Summary 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 2024-02-13
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79 FQR-2 ? ýtSA LY EXECUTIVE TEAM DAILY BRIEF
......... ......... Tuesday, November 24, 2009 Outside of Scope 1
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- From the TMI Project Manager:
- Apparent cause of the event was a change in the containment ventilation lineup in conjunction with some open RCS piping penetrations.
- Approximately 175 personnel were working in containment.
- 145 personnel could not pass the gamma sensitive personnel contamination monitoring (17 personnel had external contamination and were decontaminated; 19 were originally determined to have some measureable internal contamination, the licensee believes only 7 personnel indicate a dose greater than 10 millirem as (presented below).
Time/Date > 10mr 10,20mr 20-30mr 30-40mr maximum 1700/11/22 19 16 2 1 38.4 millirem 1600/11/23 7 5 2 0 25.7 millirem Environmental Dose Calculation:
Base on evaluation of flow rates and air samples collected, the licensee has calculated that the release on 11/21 resulted in a dose of 0.7% of annual limit of 15 mrem per year and 1.5% of the quarterly limit of 7.5 mrem per year. The total estimated dose to date from airborne releases at TMI is 0.138 mrem.
Current status of "A" SG The "A" SG is in the process of being downended (-12 hour evolution). It has been fully re-encapsulated to ensure that there is no external contamination present when it exits containment. The "A" SG could exit containment tomorrow.
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References:
NRC News Electronic Newsletters Nuclear Newstand NRC News Releases EEEB Grid Report:
Grid Report
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- 1) EN 45514 - TMI - RADIATION RELEASE IN CONTAINMENT ASSOCIATED WITH STEAM GENERATOR REMOVAL Note: Lots of media attention to this event since it occurred at TMI.
Approximately 4 PM Saturday 11/21 TMI had an event involving loss of contamination control inside -1 4
FPRQEE1 6 1/2.U E-LY containment. At the time the reactor was defueled with a hole cut in the containment wall to support the ongoing once through steam generators (OTSG) replacement outage. The licensee is not sure at this time what activity inside containment led to the problem. Their investigation is focusing on two activities (1) "A"piping loop decontamination activities or (2) some work on a drain line on the B" SG.
At the time of the event 175 workers were inside containment. Of these workers 144 people were selected for detailed monitoring based on nasal smears and alarming the portal monitor readings while exiting containment. Of the 144, about 20 people have potentially received doses greater than 10 mR.
The highest dose to a worker was between 30 and 40 mR. No site worker left the site with external contamination. Airborne contamination levels inside containment have been restored to pre-event levels and cleanup of containment surfaces is in progress. The tarp that was covering the containment opening was contaminated on its inside surface and has been replaced.
At the time of the event there was a slight positive pressure in containment. This condition has been corrected and there is now a slight negative pressure in containment, The licensee has performed a release calculation for the period of time where the containment was at positive pressure and determined the maximum release was 0.04 mr. The quarterly limit for a release allowed by their ODCM is 7.5 mr.
Therefore, this release is less than 1% of the quarterly limit.
The "A"OTSG, which was in the process of being lifted when this event occurred, is still hanging vertically inside containment. Itis being deconned/encapsulated and the licensee hopes to down-end it today onto the transfer mechanism that will eventually move it out through the OTSG opening. The downending process will end up with part of the SG poking out the hole in the containment wall.
This event has generated a significant amount of media interest. Regional OPA and state liason officers have responded to inquiries from multiple radio, print media and TV stations. They performed a press release at TMI at 2 pm on Sunday, November 22.
The PA governor's office was previously notified and they understand that this is a low level event. They have some concerns about notification timeliness. The state was notified about 9:30 pm on Saturday (event time was 4 pm). Based on the PA state notification, an event report was filed with the HOO (event number 45514). This event was far below levels that would warrant an unusual event declaration.
TMI still has not determined the root cause for the event.
The Region dispatched a HP inspector and the HP inspection branch chief to the site on Sunday. In addition, the Resident inspector and one other inspector responded to the site for additional coverage. A Manual Chapter 0309 evaluation was conducted and it was determined that no reactive inspection is warranted at this time. The Region is closely following the licensee's response and will be evaluating their root cause determination once it is issued. (Send to TRGs for Containment: Jerome BettleEP: Jeffrey Temple, Health Physics: Steven Garry. Human Performance: Michael Boqqi, Dose Assessment, Mark Blumberg and Public Affairs; Scott Burnell, assicined to Mike Brown),
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- 1) EN 45514 -TM Unit 11 - RADIATION RELEASE IN CONTAINMENT ASSOCIATED WITH STEAM
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