|
|---|
Category:Slides and Viewgraphs
MONTHYEARML23031A2532022-12-0707 December 2022
NRC Presentation at New York State Decommissioning Oversight Board on December 7, 2022 in Cortlandt, New York (Dockets 50-003, 247, 286)
ML21217A1992021-08-18018 August 2021
Virtual Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 08/15/2021 PSDAR Public Webinar Meeting
ML21207A0262021-07-29029 July 2021
Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting
ML21214A1402021-07-29029 July 2021
Updated Indian Point Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting
ML21036A0382021-02-0808 February 2021
Pre-submittal Meeting Presentation (02/08/2021) Relief Request No. IP3-ISI-RR-16
ML20269A1722020-09-30030 September 2020
Presentation Material for 9/30/2020 Pre-Submittal Meeting Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Onsite Exercise Requirements
ML20269A3452020-09-28028 September 2020
Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides
ML20265A2842020-09-22022 September 2020
Annual Assessment Meeting - Webinar Presentation
NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020
Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane
ML19289A0042019-10-17017 October 2019
Presentation Material for 10/17/19 Pre-Submittal Meeting Entergy to Holtec Proposed License Transfer Application
ML19269B6832019-10-0202 October 2019
NEIMA Section 108 Public Meeting Slides - Indian Point - October 2, 2019
ML19198A2392019-07-17017 July 2019
Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary
ML18107A3342018-04-10010 April 2018
Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides
ML18075A1232018-03-20020 March 2018
Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations
ML17200C9272017-07-0606 July 2017
07/26/2017 Entergy Presentation Slides for Public Meeting Regarding Spent Fuel Pool Management Project, New Criticality Analysis
ML17171A1982017-06-20020 June 2017
Presentations by Members of the Public - Indian Point Annual Assessment Meeting
ML17171A1872017-06-14014 June 2017
NRC Staff Presentation - Baffle-Former Bolt Inspections at Indian Point
ML17171A1922017-06-14014 June 2017
NRC Staff Presentation - Power Reactor Decommissioning Program
ML17160A1952017-06-12012 June 2017
Meeting Slides for Pre-Submittal Meeting with Entergy Regarding the Plan for Decommissioning Licensing Actions
ML16182A0672016-06-30030 June 2016
6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - NRC Presentation Slides
ML16182A1022016-06-30030 June 2016
6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Presentations from the Public
ML16166A2812016-06-0606 June 2016
Media Briefing Slides June 6, 2016
IR 05000247/20130112014-04-29029 April 2014
IR 05000247-13-011 & 05000286-13-011, and Notice of Violation, Indian Point Energy Center Units 2 & 3, and Office of Investigations Report No. 1-2012-036
ML12361A1552012-12-26026 December 2012
Summary of Entergy Drop-In on December 19, 2012
ML12130A1312012-05-0909 May 2012
Annual Assessment Posterboard Slides 2012
ML1116801732011-06-17017 June 2011
Annual Assessment Meeting - Written Statements from the Public
ML1116721212011-06-16016 June 2011
Annual Assessment Meeting Slides
ML1112502382011-05-0909 May 2011
Summary of Category 1 Public Meeting with Entergy on the Transfer of Spent Fuel from Unit 3 to Unit 2 at Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. ME1671, ME1672, and L24299)
ML1011303462010-04-22022 April 2010
Annual Assessment Meeting Slides - Entergy Presentation
ML1011303362010-04-22022 April 2010
Annual Assessment Meeting - NRC Slides
ML0926400612009-09-24024 September 2009
Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02
ML0926401682009-08-28028 August 2009
Diffusion Models
ML0913906312009-06-0404 June 2009
ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides
ML0914700162009-05-26026 May 2009
NRC Slides for Indian Point Units 2 & 3, Annual Assessment Meeting
ML0914700132009-05-26026 May 2009
Meeting Slides, Plant Performance Review Indian Point Energy Center, Entergy NRC Annual Assessment Meeting
ML0913804362009-04-15015 April 2009
Meeting Slides, Teleperm Xs Permissions and Operating Modes
ML11083A0542009-03-0606 March 2009
Lr Hearing - Slides from ACRS Subcommittee Meeting on March 4, 2009
ML11083A0252009-03-0303 March 2009
Lr Hearing - Latest Slides
ML11077A0332009-02-24024 February 2009
Lr Hearing - Draft Slides
ML0823107202008-08-0808 August 2008
IP ANS Public Meeting - August 8, 2008; NRC Slides
ML0823107362008-08-0808 August 2008
IPEC ANS Public Meeting - Entergy Slides
ML0819303272008-07-11011 July 2008
NRC Annual Performance Assessment of Indian Point, Units 2 & 3, Reactor Oversight Program, Meeting Slides
ML0819605452008-07-0202 July 2008
Entergy End of Cycle Plant Performance Review Slides, 7/2/08
ML0818404872008-07-0202 July 2008
NRC/DRS/EB1 Slides for Indian Point License Renewal Exit Meeting, June 18, 2008
ML0904102282008-07-0101 July 2008
2 SBO DG PM003.png; Develop Annual PM for Sbo/App R DG Swgr/Sfmrs Space Heaters
ML0821305302008-06-18018 June 2008
License Renewal, Slides
ML0904102082008-06-0505 June 2008
2 SBO DG PM001.png; Develop PM for Sbo/App R DG Battery
ML0905401612008-05-31031 May 2008
NRC Slides for Public Meeting, Assessment: Indian Point Contaminated Groundwater
ML0905401622008-05-31031 May 2008
NRC Government to Government Meeting Slides - NRC Assessment: Indian Point Contaminated Groundwater
ML0814804812008-05-27027 May 2008
NRC Graphics - Indian Point
2022-12-07
[Table view] |
Text
Media Briefing on Recent Issues at Indian Point Nuclear Plant U.S. Nuclear Regulatory Commission June 6, 2016 1
2 NRC PARTICIPANTS David Lew, NRC Region I Deputy Administrator Neil Sheehan, NRC Public Affairs Officer, Region I Jack McHale, Chief of the Vessels & Internals Integrity Branch, NRCs Office of Nuclear Reactor Regulation Jim Noggle, Branch Chief in the Region I Division of Reactor Safety responsible for radiological safety inspections Mike McCoppin, Chief of the Radiation Protection and Accident Consequences Branch in NRCs Office of New Reactors 3
Degradation of Baffle-former Bolts 4
Degradation of Bolts (contd.)
5
Degradation of Bolts (contd.)
6
Degradation of Bolts (contd.)
7
Summary of Bolt Degradation The degraded bolts were identified through required inspections.
Unit 2 is safe to restart based on bolt replacements and supporting analyses.
There are no immediate safety concerns with the current operation of Unit 3.
8
Indian Point Groundwater Contamination 9
Indian Point Groundwater Contamination (Contd.)
10
Indian Point Groundwater Contamination (Contd.)
11
Health risks of tritium From the EPA fact sheet on tritium:
As with all ionizing radiation, exposure to tritium increases the risk of developing cancer. However, because it emits very low energy radiation and leaves the body relatively quickly, for a given amount of activity ingested, tritium is one of the least dangerous radionuclides.
12
NRC Regulations on liquid radioactive releases Nuclear power plant liquid and gaseous releases to the environment are required to be planned, monitored and documented NRC regulations (10 CFR Part 20 and 10 CFR Part 50) place limits on these releases to ensure safety standards are being met, such as NRC ALARA limits and EPA drinking-water standards On an annual basis, NRC guidelines require that the release of radioactive liquids from a nuclear power plant not result in a radiation dose of greater than 3 millirems to any individual in an unrestricted area 13
Indian Point Groundwater Contamination Summary No health and safety significance Promptly detected and investigated Building drains and pumping system improvements are underway 14
Installation of Pipeline 15
Thresholds for Damage Overpressure Consequence 1 psi Glass shatters 2-6 psi Serious structural damage to houses 6-9 psi Severe damage to reinforced concrete structures 10 psi Destruction of Buildings
- No safety-related structure necessary to safely shutdown IPEC exposed to >1 psi Thermal Heat Flux (KW/m2) Consequence 2 Pain within 60 sec 5 Tolerable to escaping personnel 12.6 Plastic melts 31.5 Building Damage
- Max heat flux at SOCA boundary found to be about 1/2 of that which melts plastic
Installation of Pipeline (Contd.)
17
Installation of Pipeline (Contd.)
18
Summary of Pipeline Installation Independent and diverse analysis (NRC, Entergy, DOT) demonstrate no safety impacts.
Actual explosions confirmed NRC analysis is conservative.
Plant equipment needed to shut down would remain available during a pipeline explosion.
19
20 Additional information/questions Contact Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at Neil.Sheehan@NRC.GOV 21
Thank you for your participation 22
