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| {{#Wiki_filter:1 Indian Point License Renewal Inspection Exit Meeting June 18, 2008 2 Welcome & Opening Remarks Sam Collins Regional Administrator, NRC Region I Richard Conte Chief Engineering Branch 1, DRS 3 Introductions | | {{#Wiki_filter:Indian Point License Renewal Inspection Exit Meeting June 18, 2008 1 |
| *NRC meeting representatives:
| | Welcome & Opening Remarks Sam Collins Regional Administrator, NRC Region I Richard Conte Chief Engineering Branch 1, DRS 2 |
| -S. Collins, Regional Administrator
| |
| -D. Roberts, Deputy Director, DRS, Region 1
| |
| -R. Conte, Chief, Engineering Branch 1, DRS, Region I
| |
| -R. Franovich , Chief, License Renewal Branch B, NRR
| |
| -G. Meyer, Sr. Reactor Inspector/Team Leader, DRS, Region I
| |
| *Entergy meeting representatives:
| |
| -F. Dacimo , Vice President, License Renewal, IPEC
| |
| -G. Young, Manager, License Renewal, Entergy
| |
| -J. Curry, Sr. Project Manager, License Renewal, IPEC
| |
| -M. Stroud, Manager, Business Development, Entergy
| |
| -A. Cox, Manager, Project Management, Entergy 4 Agenda*License Renewal Process & Status
| |
| *Exit Meeting with Entergy
| |
| *Break*Public Questions to NRC 5 LICENSE RENEWAL PROCESS & STATUS Richard Conte, Team Manager ACRS *and Hearings Safety Evaluation Review Onsite Inspection 71002 Safety Review Environmental Review License Renewal Application Submitted To NRC Site Environmental Review* Independent review by Advisory Committee on Reactor Safeguard s (ACRS) is mandatory License Renewal Process Plant enters Period of Extended Operation Onsite Inspection 71003 Follow-up inspection (if needed)
| |
| Yes No License Not Renewed Continue Current Licensing Basis to Expiration Application accepted by NRC Staff?
| |
| NRC Decision regarding Issuance of Renewed License License renewed 7 Key Dates*April 23 / May 3 / June 21, 2007
| |
| -Entergy submits application for IP Units 2 & 3
| |
| *July 25, 2007
| |
| -Application accepted by NRC
| |
| *January 28
| |
| -February 14, 2008
| |
| -Planned onsite inspection
| |
| *April 30, 2008
| |
| -Entergy reports Unit 2 Station Blackout (SBO)
| |
| Diesel installed and operational 8 Key Dates*Tentative Dates for NRC Decision:
| |
| -July 2009 (No Hearing)
| |
| -April 2010 (Hearing)
| |
| *License Expiration Dates:
| |
| -IP2: Sep. 28, 2013
| |
| -IP3: Dec. 12, 2015
| |
| -Note: IP1 is in safe storage status not subject to license renewal 9 Environmental Review
| |
| *Environmental review in progress
| |
| -Planned site reviews completed by NRC staff
| |
| *Review Entergy responses
| |
| *September 2008
| |
| -Tentative schedule for draft Supplemental Environmental Impact Statement (SEIS)
| |
| *October 2008
| |
| -Tentative public meeting on draft SEIS 10 Safety Review
| |
| *Safety review is in progress
| |
| -Planned site reviews completed by NRC Staff
| |
| *Inspection completed
| |
| -Major effort completed February 2008
| |
| -Follow-up weeks March 30 and June 2, 2008
| |
| *June 18, 2008
| |
| -Public Inspection Exit
| |
| *September 2008
| |
| -Initial Safety Evaluation Report (SER) 11 INSPECTION EXIT MEETING Glenn Meyer, Team Leader License Renewal Inspection O bjective -to verify the in
| |
| -plant aspects of scoping, material condition, aging management program development, and documentation, supporting the license renewal application.
| |
| 13 Scope of Inspection
| |
| *NRC team -approximately 1,500 hours to date (8 inspectors)
| |
| *Reviewed:-Effects of non
| |
| -safety structures & components on safety related equipment-Aging Management Programs (AMP)
| |
| *Implementation checks for existing programs
| |
| *Feasibility of implementation for modified or new programs
| |
| -Documentation is auditable, retrievable and supports the application
| |
| *Methods:-Walkdowns in plant areas
| |
| -Reviews of procedures & records
| |
| -Interviews 14 Overall Results of the Inspection
| |
| *Observations will be documented in the following areas:-Scoping of non
| |
| -safety systems
| |
| -Existing and Modified/New Aging Management Programs*These observations will be used to;
| |
| -Provide for Headquarters consideration on its safety evaluation
| |
| -Be incorporated into the licensing corrective action process 15 Observations Resulting in Application Revision
| |
| *Structural Monitoring Program
| |
| -IP3 service water pump fiberglass baffling not included
| |
| *Selective Leaching Program for certain alloys and various water environments
| |
| -Sampling technique unclear
| |
| *Diesel Fuel Monitoring Program
| |
| -Inappropriate testing for wall thickness of IP3 fuel storage tanks
| |
| -Deficient procedures for IP2 sample location and process-Procedures omitted fuel tank for IP2 security diesel generator 16 Observations Resulting in Application Revision
| |
| *Water Chemistry
| |
| -Closed Cooling Program
| |
| -Testing for pH and glycol not specified
| |
| *Bolted Cable Connections Monitoring Program
| |
| -Inspection methods inconsistent with NRC draft guidance*Metal Enclosed Bus (MEB) Monitoring Program
| |
| -Unclear acceptance criteria for internal inspections
| |
| *Lubricating Oil Program
| |
| -Reactor Coolant Pump (RCP) motor coolers not included 17 Other Observations For Applicant Review
| |
| *Material conditions not in corrective action program-Boric acid leaks
| |
| -Concrete-Fire protection equipment
| |
| *Containment visual indications
| |
| -Additional measurements are being considered to supplement visual observations of exposed rebar 18 Other Observations For Applicant Review
| |
| *Operating experience review on MEB
| |
| -Basis documentation did not include inoperable bus example in 2004
| |
| *IP2 Instrument air heat exchangers
| |
| -Not included in heat exchanger monitoring program
| |
| *Cable separation material
| |
| -Transite material used in some locations not identified in aging management review 19 Follow-up Inspection Observations
| |
| *Containment Internal Inspection
| |
| -Inspectors confirmed acceptable material condition*Manhole Inspection
| |
| -Water found
| |
| -pumped out
| |
| -cables used with water submergence being reviewed by Headquarters
| |
| *Station Blackout (SBO) Diesel Inspection
| |
| -SBO was included in the current licensing basis to supplement the LRA
| |
| -For purposes of license renewal, scoping and screening was consistent with LRA
| |
| -Current operation issues addressed by ROP Summary of observation results*The effects of non
| |
| -safety structures &
| |
| components on safety related equipment are adequately addressed with few
| |
|
| |
|
| exceptions noted.
| | ===Introductions=== |
| *AMPs can be implemented with few exceptions noted. | | * NRC meeting representatives: |
| *Documentation is auditable, retrievable and supports the application
| | - S. Collins, Regional Administrator |
| -no exceptions noted. | | - D. Roberts, Deputy Director, DRS, Region 1 |
| 21 Entergy Response 22 NRC Summary 23 Additional Information
| | - R. Conte, Chief, Engineering Branch 1, DRS, Region I |
| *NRC Homepage
| | - R. Franovich, Chief, License Renewal Branch B, NRR |
| -www.nrc.gov | | - G. Meyer, Sr. Reactor Inspector/Team Leader, DRS, Region I |
| *Indian Point 2 Current Performance Summary
| | * Entergy meeting representatives: |
| -www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip2_chart.html | | - F. Dacimo, Vice President, License Renewal, IPEC |
| *Indian Point 3 Current Performance Summary
| | - G. Young, Manager, License Renewal, Entergy |
| -www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip3_chart.html | | - J. Curry, Sr. Project Manager, License Renewal, IPEC |
| *Indian Point "Specific Plant of Interest" Page | | - M. Stroud, Manager, Business Development, Entergy |
| -www.nrc.gov/reactors/plant | | - A. Cox, Manager, Project Management, Entergy 3 |
| -specific-items/indian | | Agenda |
| -point-issues.html | | * License Renewal Process & Status |
| *Indian Point License Renewal Review Status
| | * Exit Meeting with Entergy |
| -www.nrc.gov/reactors/operating/licensing/renewal/applications/in dian-point.html 24 BREAK Meeting Facilitator Richard Barkley, PE Nuclear & Environmental Engineer | | * Break |
| -Technical Communications Assistant for Region I Meeting Ground Rules
| | * Public Questions to NRC 4 |
| *Please be respectful of the speaker | |
| -only one speaker at a time.
| |
| *To be fair to the other questioners, please limit your remarks to about 5 minutes (There are many people who want to speak).*The moderator will alternate between elected officials and the public at the start | |
|
| |
|
| of the meeting. | | LICENSE RENEWAL PROCESS & STATUS Richard Conte, Team Manager 5 |
| Meeting Ground Rules (cont.)*Speakers will be called to the microphone up front -NRC can not field questions from the audience due to its size.
| | License Renewal Process Onsite License Inspection Renewal 71002 Onsite Application Inspection Submitted To 71003 NRC Safety Evaluation Review Plant enters License Period of Safety renewed Extended Review Operation NRC Application Decision accepted by regarding Yes ACRS |
| *Order called will vary from the sign
| | * NRC Staff? Issuance of and Renewed Hearings Follow-up License inspection Environmental License Not (if needed) |
| -up order to ensure all groups are heard. | | Review Renewed Site No Environmental Continue Review Current Licensing Basis to |
| *See NRC staff if you have procedural questions / concerns or still want to sign | | * Independent review by Advisory Committee on Reactor Safeguards (ACRS) is mandatory Expiration |
|
| |
|
| up.*Please silence cell phones and pagers | | Key Dates |
| -Thank you! | | * April 23 / May 3 / June 21, 2007 |
| *If you posed a question that NRC has committed to reply to later, please make | | - Entergy submits application for IP Units 2 & 3 |
| | * July 25, 2007 |
| | - Application accepted by NRC |
| | * January 28 - February 14, 2008 |
| | - Planned onsite inspection |
| | * April 30, 2008 |
| | - Entergy reports Unit 2 Station Blackout (SBO) |
| | Diesel installed and operational 7 |
| | Key Dates |
| | * Tentative Dates for NRC Decision: |
| | - July 2009 (No Hearing) |
| | - April 2010 (Hearing) |
| | * License Expiration Dates: |
| | - IP2: Sep. 28, 2013 |
| | - IP3: Dec. 12, 2015 |
| | - Note: IP1 is in safe storage status not subject to license renewal 8 |
| | |
| | Environmental Review |
| | * Environmental review in progress |
| | - Planned site reviews completed by NRC staff |
| | * Review Entergy responses |
| | * September 2008 |
| | - Tentative schedule for draft Supplemental Environmental Impact Statement (SEIS) |
| | * October 2008 |
| | - Tentative public meeting on draft SEIS 9 |
| | Safety Review |
| | * Safety review is in progress |
| | - Planned site reviews completed by NRC Staff |
| | * Inspection completed |
| | - Major effort completed February 2008 |
| | - Follow-up weeks March 30 and June 2, 2008 |
| | * June 18, 2008 |
| | - Public Inspection Exit |
| | * September 2008 |
| | - Initial Safety Evaluation Report (SER) 10 |
| | |
| | INSPECTION EXIT MEETING Glenn Meyer, Team Leader 11 License Renewal Inspection Objective - to verify the in-plant aspects of scoping, material condition, aging management program development, and documentation, supporting the license renewal application. |
| | |
| | Scope of Inspection |
| | * NRC team - approximately 1,500 hours to date (8 inspectors) |
| | * Reviewed: |
| | - Effects of non-safety structures & components on safety related equipment |
| | - Aging Management Programs (AMP) |
| | * Implementation checks for existing programs |
| | * Feasibility of implementation for modified or new programs |
| | - Documentation is auditable, retrievable and supports the application |
| | * Methods: |
| | - Walkdowns in plant areas |
| | - Reviews of procedures & records |
| | - Interviews 13 Overall Results of the Inspection |
| | * Observations will be documented in the following areas: |
| | - Scoping of non-safety systems |
| | - Existing and Modified/New Aging Management Programs |
| | * These observations will be used to; |
| | - Provide for Headquarters consideration on its safety evaluation |
| | - Be incorporated into the licensing corrective action process 14 |
| | |
| | Observations Resulting in Application Revision |
| | * Structural Monitoring Program |
| | - IP3 service water pump fiberglass baffling not included |
| | * Selective Leaching Program for certain alloys and various water environments |
| | - Sampling technique unclear |
| | * Diesel Fuel Monitoring Program |
| | - Inappropriate testing for wall thickness of IP3 fuel storage tanks |
| | - Deficient procedures for IP2 sample location and process |
| | - Procedures omitted fuel tank for IP2 security diesel generator 15 Observations Resulting in Application Revision |
| | * Water Chemistry - Closed Cooling Program |
| | - Testing for pH and glycol not specified |
| | * Bolted Cable Connections Monitoring Program |
| | - Inspection methods inconsistent with NRC draft guidance |
| | * Metal Enclosed Bus (MEB) Monitoring Program |
| | - Unclear acceptance criteria for internal inspections |
| | * Lubricating Oil Program |
| | - Reactor Coolant Pump (RCP) motor coolers not included 16 |
| | |
| | Other Observations For Applicant Review |
| | * Material conditions not in corrective action program |
| | - Boric acid leaks |
| | - Concrete |
| | - Fire protection equipment |
| | * Containment visual indications |
| | - Additional measurements are being considered to supplement visual observations of exposed rebar 17 Other Observations For Applicant Review |
| | * Operating experience review on MEB |
| | - Basis documentation did not include inoperable bus example in 2004 |
| | * IP2 Instrument air heat exchangers |
| | - Not included in heat exchanger monitoring program |
| | * Cable separation material |
| | - Transite material used in some locations not identified in aging management review 18 |
| | |
| | Follow-up Inspection Observations |
| | * Containment Internal Inspection |
| | - Inspectors confirmed acceptable material condition |
| | * Manhole Inspection |
| | - Water found - pumped out - cables used with water submergence being reviewed by Headquarters |
| | * Station Blackout (SBO) Diesel Inspection |
| | - SBO was included in the current licensing basis to supplement the LRA |
| | - For purposes of license renewal, scoping and screening was consistent with LRA |
| | - Current operation issues addressed by ROP 19 Summary of observation results |
| | * The effects of non-safety structures & |
| | components on safety related equipment are adequately addressed with few exceptions noted. |
| | * AMPs can be implemented with few exceptions noted. |
| | * Documentation is auditable, retrievable and supports the application - no exceptions noted. |
| | |
| | Entergy Response 21 NRC Summary 22 |
| | |
| | Additional Information |
| | * NRC Homepage |
| | - www.nrc.gov |
| | * Indian Point 2 Current Performance Summary |
| | - www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip2_chart.html |
| | * Indian Point 3 Current Performance Summary |
| | - www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip3_chart.html |
| | * Indian Point "Specific Plant of Interest" Page |
| | - www.nrc.gov/reactors/plant-specific-items/indian-point-issues.html |
| | * Indian Point License Renewal Review Status |
| | - www.nrc.gov/reactors/operating/licensing/renewal/applications/in dian-point.html 23 BREAK 24 |
| | |
| | Meeting Facilitator Richard Barkley, PE Nuclear & Environmental Engineer - |
| | Technical Communications Assistant for Region I Meeting Ground Rules |
| | * Please be respectful of the speaker - only one speaker at a time. |
| | * To be fair to the other questioners, please limit your remarks to about 5 minutes (There are many people who want to speak). |
| | * The moderator will alternate between elected officials and the public at the start of the meeting. |
|
| |
|
| sure of exchanging contact information.
| |
| *NRC staff members will be available after the meeting.
| |
| Meeting Ground Rules (cont.) | | Meeting Ground Rules (cont.) |
| 29 Public Questions for NRC
| | * Speakers will be called to the microphone up front - NRC can not field questions from the audience due to its size. |
| *Please use Q&A cards.}} | | * Order called will vary from the sign-up order to ensure all groups are heard. |
| | * See NRC staff if you have procedural questions / concerns or still want to sign up. |
| | Meeting Ground Rules (cont.) |
| | * Please silence cell phones and pagers - |
| | Thank you! |
| | * If you posed a question that NRC has committed to reply to later, please make sure of exchanging contact information. |
| | * NRC staff members will be available after the meeting. |
| | |
| | Public Questions for NRC |
| | * Please use Q&A cards. |
| | 29}} |
|
---|
Category:Meeting Agenda
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[Table view] Category:Meeting Briefing Package/Handouts
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[Table view] Category:Slides and Viewgraphs
MONTHYEARML24173A2132024-06-13013 June 2024 NRC Presentation; Indian Point Decommissioning Oversight Board, Dated June 13, 2024 ML23031A2532022-12-0707 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 ML17171A1922017-06-14014 June 2017 NRC Staff Presentation - Power Reactor Decommissioning Program ML17171A1872017-06-14014 June 2017 NRC Staff Presentation - Baffle-Former Bolt Inspections at Indian Point ML17160A1952017-06-12012 June 2017 Meeting Slides for Pre-Submittal Meeting with Entergy Regarding the Plan for Decommissioning Licensing Actions ML16182A1022016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Presentations from the Public ML16182A0672016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - NRC Presentation Slides 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 ML0823107362008-08-0808 August 2008 IPEC ANS Public Meeting - Entergy Slides ML0823107202008-08-0808 August 2008 IP ANS Public Meeting - August 8, 2008; NRC 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 2024-06-13
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Indian Point License Renewal Inspection Exit Meeting June 18, 2008 1
Welcome & Opening Remarks Sam Collins Regional Administrator, NRC Region I Richard Conte Chief Engineering Branch 1, DRS 2
Introductions
- NRC meeting representatives:
- S. Collins, Regional Administrator
- D. Roberts, Deputy Director, DRS, Region 1
- R. Conte, Chief, Engineering Branch 1, DRS, Region I
- R. Franovich, Chief, License Renewal Branch B, NRR
- G. Meyer, Sr. Reactor Inspector/Team Leader, DRS, Region I
- Entergy meeting representatives:
- F. Dacimo, Vice President, License Renewal, IPEC
- G. Young, Manager, License Renewal, Entergy
- J. Curry, Sr. Project Manager, License Renewal, IPEC
- M. Stroud, Manager, Business Development, Entergy
- A. Cox, Manager, Project Management, Entergy 3
Agenda
- Exit Meeting with Entergy
- Public Questions to NRC 4
LICENSE RENEWAL PROCESS & STATUS Richard Conte, Team Manager 5
License Renewal Process Onsite License Inspection Renewal 71002 Onsite Application Inspection Submitted To 71003 NRC Safety Evaluation Review Plant enters License Period of Safety renewed Extended Review Operation NRC Application Decision accepted by regarding Yes ACRS
- NRC Staff? Issuance of and Renewed Hearings Follow-up License inspection Environmental License Not (if needed)
Review Renewed Site No Environmental Continue Review Current Licensing Basis to
Key Dates
- April 23 / May 3 / June 21, 2007
- Entergy submits application for IP Units 2 & 3
- Application accepted by NRC
- January 28 - February 14, 2008
- Planned onsite inspection
- Entergy reports Unit 2 Station Blackout (SBO)
Diesel installed and operational 7
Key Dates
- Tentative Dates for NRC Decision:
- July 2009 (No Hearing)
- April 2010 (Hearing)
- License Expiration Dates:
- IP2: Sep. 28, 2013
- IP3: Dec. 12, 2015
- Note: IP1 is in safe storage status not subject to license renewal 8
Environmental Review
- Environmental review in progress
- Planned site reviews completed by NRC staff
- Tentative schedule for draft Supplemental Environmental Impact Statement (SEIS)
- Tentative public meeting on draft SEIS 9
Safety Review
- Safety review is in progress
- Planned site reviews completed by NRC Staff
- Major effort completed February 2008
- Follow-up weeks March 30 and June 2, 2008
- Public Inspection Exit
- Initial Safety Evaluation Report (SER) 10
INSPECTION EXIT MEETING Glenn Meyer, Team Leader 11 License Renewal Inspection Objective - to verify the in-plant aspects of scoping, material condition, aging management program development, and documentation, supporting the license renewal application.
Scope of Inspection
- NRC team - approximately 1,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> to date (8 inspectors)
- Effects of non-safety structures & components on safety related equipment
- Aging Management Programs (AMP)
- Implementation checks for existing programs
- Feasibility of implementation for modified or new programs
- Documentation is auditable, retrievable and supports the application
- Walkdowns in plant areas
- Reviews of procedures & records
- Interviews 13 Overall Results of the Inspection
- Observations will be documented in the following areas:
- Scoping of non-safety systems
- Existing and Modified/New Aging Management Programs
- These observations will be used to;
- Provide for Headquarters consideration on its safety evaluation
- Be incorporated into the licensing corrective action process 14
Observations Resulting in Application Revision
- Structural Monitoring Program
- IP3 service water pump fiberglass baffling not included
- Selective Leaching Program for certain alloys and various water environments
- Sampling technique unclear
- Diesel Fuel Monitoring Program
- Inappropriate testing for wall thickness of IP3 fuel storage tanks
- Deficient procedures for IP2 sample location and process
- Procedures omitted fuel tank for IP2 security diesel generator 15 Observations Resulting in Application Revision
- Water Chemistry - Closed Cooling Program
- Testing for pH and glycol not specified
- Bolted Cable Connections Monitoring Program
- Inspection methods inconsistent with NRC draft guidance
- Metal Enclosed Bus (MEB) Monitoring Program
- Unclear acceptance criteria for internal inspections
- Reactor Coolant Pump (RCP) motor coolers not included 16
Other Observations For Applicant Review
- Material conditions not in corrective action program
- Boric acid leaks
- Concrete
- Fire protection equipment
- Containment visual indications
- Additional measurements are being considered to supplement visual observations of exposed rebar 17 Other Observations For Applicant Review
- Operating experience review on MEB
- Basis documentation did not include inoperable bus example in 2004
- IP2 Instrument air heat exchangers
- Not included in heat exchanger monitoring program
- Cable separation material
- Transite material used in some locations not identified in aging management review 18
Follow-up Inspection Observations
- Containment Internal Inspection
- Inspectors confirmed acceptable material condition
- Water found - pumped out - cables used with water submergence being reviewed by Headquarters
- Station Blackout (SBO) Diesel Inspection
- SBO was included in the current licensing basis to supplement the LRA
- For purposes of license renewal, scoping and screening was consistent with LRA
- Current operation issues addressed by ROP 19 Summary of observation results
- The effects of non-safety structures &
components on safety related equipment are adequately addressed with few exceptions noted.
- AMPs can be implemented with few exceptions noted.
- Documentation is auditable, retrievable and supports the application - no exceptions noted.
Entergy Response 21 NRC Summary 22
Additional Information
- www.nrc.gov
- Indian Point 2 Current Performance Summary
- www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip2_chart.html
- Indian Point 3 Current Performance Summary
- www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip3_chart.html
- Indian Point "Specific Plant of Interest" Page
- www.nrc.gov/reactors/plant-specific-items/indian-point-issues.html
- www.nrc.gov/reactors/operating/licensing/renewal/applications/in dian-point.html 23 BREAK 24
Meeting Facilitator Richard Barkley, PE Nuclear & Environmental Engineer -
Technical Communications Assistant for Region I Meeting Ground Rules
- Please be respectful of the speaker - only one speaker at a time.
- To be fair to the other questioners, please limit your remarks to about 5 minutes (There are many people who want to speak).
- The moderator will alternate between elected officials and the public at the start of the meeting.
Meeting Ground Rules (cont.)
- Speakers will be called to the microphone up front - NRC can not field questions from the audience due to its size.
- Order called will vary from the sign-up order to ensure all groups are heard.
- See NRC staff if you have procedural questions / concerns or still want to sign up.
Meeting Ground Rules (cont.)
- Please silence cell phones and pagers -
Thank you!
- If you posed a question that NRC has committed to reply to later, please make sure of exchanging contact information.
- NRC staff members will be available after the meeting.
Public Questions for NRC
29