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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River 2024-09-18
[Table view] Category:Meeting Summary
MONTHYEARML22309A0062022-12-12012 December 2022 Public Non-Sensitive Meeting Summary on Clarification Call with Holtec Regarding Request for Additional Information for Indian Point Unit 2 Master Decommissioning Trust Agreement as Per Indian Point Nuclear Generating Facility Unit 1 and 2 ML21342A1402021-12-0909 December 2021 Summary of Public Meeting in Tarrytown, Ny, to Discuss Indian Point Units 1, 2, and 3 (IPEC) Post-shutdown Decommissioning Activities Report ML21055A9122021-02-24024 February 2021 (E-mail Dated 2/24/2021) Summary of Feb 8, 2021, Pre-submittal Meeting for Relief Request No. IP3-ISI-RR-16, Code Case N-513-4 Periodic Inspection Frequency Extension ML20321A0002020-11-17017 November 2020 Summary of 9/30/20 Pre-Submittal Meeting with Entergy to Discuss Proposed One-Time Exemption Request - Biennial Emergency Preparedness Onsite Evaluated Exercise Requirements ML20289A7322020-10-15015 October 2020 2020 Annual Assessment Meeting for Indian Point - Meeting Summary ML20083F5962020-03-23023 March 2020 Summary of Teleconference with the National Marine Fisheries Service for Indian Point Biological Opinion ML20059P1292020-03-0303 March 2020 Summary of Partially Closed Pre-submittal Public Meeting with Entergy Nuclear Operations, Inc. to Discuss the Proposed License Amendment Request to Replace the Indian Point Unit No. 3 Crane with a New Holtec High-Lift Crane (EPID L:2019-LRM ML19330F5182019-11-29029 November 2019 Summary of Public Meeting Between the NRC and Entergy Regarding Pre-Submittal of a License Transfer Application to Holtec International for Indian Point Energy Center ML19319A0242019-10-0202 October 2019 NEIMA Meeting - Courtney Williams Comments ML19319A0282019-10-0202 October 2019 NEIMA Meeting - Marilyn Elie Comments ML19319A0272019-10-0202 October 2019 NEIMA Meeting - Linda Puglisi Comments ML19319A0252019-10-0202 October 2019 NEIMA Meeting - Jenean Eichenholtz Comments ML19198A2392019-07-17017 July 2019 Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary ML18200A2722018-07-19019 July 2018 Summary of Annual Assessment Meeting for Indian Point Energy Center ML18131A0572018-05-11011 May 2018 Summary of 04/12/2018 Meeting with the State of New York Regarding the Indian Point Generating Unit No. 2 Reactor Pressure Vessel Head Penetration Alternative Weld Repair ML18117A3162018-04-30030 April 2018 Summary of 04/03/2018 Meeting with Entergy on Planned Submittal of Propose Alternative for Reactor Pressure Vessel Head Nozzle Weld Repair ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML18002A2562018-01-30030 January 2018 11/30/2017 and 12/19/2017 Summary Telephone Conference Calls with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point License Renewal Application ML17256A2862017-09-25025 September 2017 Summary of Telephone Call on 09/06/17, Between NRC and Entergy Concerning Next Steps from the Site Audit on 08/1-3/17 ML17180A5032017-09-21021 September 2017 04/19/2017 Summary of Teleconference with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point Unit Nos. 2 and 3 License Renewal Application ML17237A2132017-08-25025 August 2017 Memo E-mail to File -Summary of July 26, 2017, Meeting with Entergy to Discuss Proposed License Amendment Request, New Criticality Safety Analysis ML17173A7672017-07-28028 July 2017 Summary of 6/20/2017 Meeting with Entergy to Discuss Plan for Decommissioning Licensing Actions of Palisades, Pilgrim, Indian Point, Units 2 and 3, and Vermont Yankee ML17160A1652017-06-27027 June 2017 Summary of Telephone Conference Call Held on May 31,2017, Between the NRC and Entergy Nuclear Operations Inc. Concerning Requests for Additional Information Pertaining to the Indian Point, License Renewal Application (TAC Nos. MD5407/MD5408 ML17172A1972017-06-20020 June 2017 Summary of Annual Assessment Meeting for Indian Point Units 2 and 3 ML17157B5422017-06-20020 June 2017 Conference Call on 2nd Round RAIs - Final ML17082A3112017-04-11011 April 2017 Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02 ML16281A2162016-10-25025 October 2016 10/04/2016,Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Proposed Changes to the Service Water Integrity Program for the Indian Point Nuclear Generating, Units 2 and 3 (IP2 and IP3) License Renewal Application (LRA) ML16209A3712016-08-17017 August 2016 July 21, 2016, Summary of Conference Call Held Between NRC and Entergy Nuclear Operations, Inc. Concerning the Draft RAI for the Review of the Indian Point, Units 2 & 3, License Renewal Application, Set 2016-01 (TAC Nos. MD5407 & MD5408) ML16188A0202016-07-0505 July 2016 Summary of Annual Assessment Meeting for Indian Point Units 2 and 3 ML16133A4992016-06-21021 June 2016 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Safety Review ML16035A4802016-02-12012 February 2016 Jsc Meeting Summary Attachment ML15351A2032015-12-30030 December 2015 Summary of Conference Call Held on December 9, 2015, Between the NRC and Entergy Nuclear Operations, Inc. Concerning the Draft Audit Plan for the Service Water Integrity and Fire Water System Aging Management Programs ML15190A2912015-07-22022 July 2015 070115, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review ML15152A0762015-05-29029 May 2015 Summary of Annual Assessment Meeting for Indian Point Units 2 and 3 on 5/20/2015 ML15120A6442015-05-0606 May 2015 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review ML15107A1752015-04-28028 April 2015 041615, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review ML15093A5052015-04-14014 April 2015 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Environmental Review ML15051A5022015-03-10010 March 2015 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review ML15022A1602015-02-11011 February 2015 and 01/13/15, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review ML14197A5832014-09-18018 September 2014 Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1 ML14260A4312014-09-17017 September 2014 Revised Summary of Annual Assessment Meeting for Indian Point Energy Center on 6/4/2014 ML14238A7262014-09-10010 September 2014 Summary of Conference Call Held on July 30, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations Inc., Regarding a Draft Request for Additional Information on Removal of Certain Aging Management Review Items ML14219A6742014-08-14014 August 2014 July 15, 2014 Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Environmental Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License R ML14206B1282014-08-0101 August 2014 June 19, 2014 & July 16, 2014 Summary of Conference Calls Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Regarding Entergy Response to a Request for Additional Information ML14178A8682014-06-25025 June 2014 Summary of Annual Assessment Meeting for Indian Point Energy Center on 6/4/2014 ML14136A0052014-05-27027 May 2014 Summary of Phone Call Between New York State Department of State and U.S. Nuclear Regulatory Commission on May 7, 2014, Regarding the Coastal Zone Management Act Consistency Review ML14105A3542014-04-24024 April 2014 Summary of Conference Call Held on March 26, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning a Draft Request for Additional Information on the Reactor Vessel Internals Program ML14078A3992014-03-21021 March 2014 Summary of Conference Call Held on February 20, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning a Draft Request for Additional Information on LR-ISG-2012-02 and Draft LR-ISG-2013-01 ML13256A0862013-09-24024 September 2013 Summary of Meeting with Entergy Nuclear Operations, Inc. and Netco on Indian Point Unit 2 Spent Fuel Pool Management 2022-12-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 September 17, 2014 MEETING
SUMMARY
LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.
FACILITY: INDIAN POINT ENERGY CENTER, UNITS 2 AND 3
SUBJECT:
SUMMARY
OF PUBLIC MEETING
On June 4, 2014, from 6:00 p.m. to 9:00 p.m., the U.S. Nuclear Regulatory Commission (NRC) met with members of the public at the Colonial Terrace, Cortlandt Manor, NY, to discuss the NRC's assessment of safety performance at Indian Point for calendar year 2013.
From 6:00 p.m. to 7:00 p.m., the NRC held an Open House during which NRC personnel were available, in an informal setting, to answer questions from individuals and discuss issues or concerns related to Indian Point. From 7:00 p.m. to 9:00 p.m., the NRC hosted a question and answer session in an adjacent area, during which interested stakeholders were able to ask questions or make statements in a public forum. The NRC did not make a formal presentation.
Approximately 200 people attended the meeting, including representatives of federal, state, and local governments. During the question and answer session, individuals requested time to either make a statement or ask a question related to NRC oversight of Indian Point. Following the question and answer session, NRC pers onnel were available to speak individually with stakeholders.
Both during and after the meeting, the NRC received questions from members of the public on a wide variety of regulatory topics that were not able to be immediately answered. The NRC's position and actions taken regarding these topics is included in the Enclosure to this letter.
The NRC's assessment letter can be found in the Agencywide Documents Access and Management System (ADAMS) with an Accession Number of ML14063A053. The annual assessment meeting notice can be found in ADAMS with an Accession Number of ML14136A046. ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html.
______/RA/______________
Arthur L. Burritt, Chief Projects Branch 2
Division of Reactor Projects
Enclosures:
- 1. Public Meeting Sign-in Sheet
- 2. Annual Assessment Meeting Topics of Public Interest
ML14260A431 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP NA.M.E TSetzer/TCS ABurritt/ALB DATE 09/15/14 09/17/14
1 Enclosure 2 Annual Assessment Meeting Topics of Public Interest Planning and selection of the meeting venue The planning for this year's Annual Assessment meeting included visits to a number of venues near the Indian Point facility. The Colonial Terrace was chosen as the meeting's location because of its availability, ability to accommodate a sizable audience, and the fact that it is within the 10-mile-radius Emergency Planning Zone for Indian Point. With respect to the last factor, the location allowed for easier access to those who live in communities near the plant, as opposed to further locations.
Use of transcription for annual assessment meetings Many NRC meetings and hearings have publically available records. In the case of Annual Assessment meetings, these are not hearings or decision-making sessions. Annual Assessment meetings are intended to be a public outreach information event and not a
decision-making session or one at which the NRC is soliciting formal testimony, as is the case at a hearing. We hold hundreds of public meetings each year and must balance the agency's commitment to openness with attention to our fiscal responsibilities. As such, many of our meetings are not transcribed or video-recorded. We engage in active listening and note-taking during these meetings and do our best to respond to key questions and concerns. If we cannot answer a question on the spot, we provide a response sometime afterwards when an individual requests a reply. Each year we look at ways to improve public meetings. The Chairman has tasked the staff with looking at how we can improve NRC meetings, and an initiative to do that has begun. This initiative includes determining ways to better document public meetings, such as considering the use of transcription.
Nuclear plant design to withstand seismic events Nuclear plant structures, systems, and components important to safety must be designed to safely withstand the effects of natural phenomena, such as earthquakes, without loss of capability to perform their safety function. The vibratory ground motion for which these structures, systems, and components must be designed to remain functional is the plant's safe shutdown earthquake (SSE). The NRC requires that if the SSE ground motion occurs, these
structures, systems, and components must be able withstand the effects and assure the plant's capability to shut down the reactor and maintain it in a safe-shutdown condition. For any seismic ground motion felt onsite, licensee procedures require walkdowns to be conducted to verify that plant components and structures, including the spent fuel pool, are capable to perform their intended functions. If the SSE is exceeded, as was the case in the August 2011 Virginia earthquake near North Anna Nuclear Power Station, NRC regulations require that the station not start up until it can demonstrate that no functional damage occurred to those features needed for continued safe operation.
The ability of a nuclear plant to withstand certain levels of ground motion is measured in accelerations (g's), not the Richter scale. Ground motion depends not only on an earthquake's magnitude, but also on its distance from the site and geological characteristics of materials (density, saturation, elasticity, and energy damping properties) through which the energy waves travel. The ground acceleration used for the design of Indian Point Units 2 and 3 safety-related structures, including the spent fuel pool, is 0.15g. As part of the NRC's post-Fukushima actions, each plant was required to perform a seismic hazard reevaluation. We are currently in the process of reviewing those reevaluations. Indian Point has been prioritized as a Tier 1 plant, 2 Enclosure 2 which means the results of its reevaluation qualify it for the most immediate attention. Entergy submitted seismic reevaluations for Indian Point Unit 2 and Unit 3 on March 31, 2014. The plants can continue to operate until these reviews are complete because their robust designs and redundant safety features ensure they can safely shut down during the largest postulated seismic event. Since plants gener ally have significant margin beyond their existing seismic design basis, it is possible they can continue to operate safely without modification even with a higher seismic hazard. No decisions have been made yet with respect to whether any structures at Indian Point will have to be modified or reinforced.
Indian Point spent fuel design and storage capacity (original vs. current)
Anytime a plant's owner intends to increase the capacity of its spent fuel pool beyond the licensed amount, a thorough evaluation must be conducted to ensure the continued safe storage of the material, including a review of the increased heat load and an analysis of any increased potential for safety hazards. In the case of Indian Point, this took place each time they changed the configuration of the spent fuel pools, providing assurance that the pools
remained safe. The NRC independently reviewed each of the spent fuel pool evaluations and concluded that the spent fuel pools remain safe under the licensed loading limit. Both Indian Point Unit 2 and 3 were originally licensed for a maximum capacity of 264 fuel assemblies. Since then, analyses and evaluations have proven that the pool can safely accommodate more than the original licensed limit. Currently, the Unit 2 spent fuel pool has a capacity of 1374 assemblies, and the Unit 3 spent fuel pool has a capacity of 1345 assemblies. Both pools are similarly loaded near full capacity.
Indian Point began using dry cask storage for some of its spent nuclear fuel several years ago. As is the case at other U.S. nuclear power plants, Indian Point schedules periodic dry cask loading campaigns, during which a number of spent fuel assemblies are removed from the spent fuel pools and moved into dry casks. These moves are made to afford the licensee operational flexibility and to comply with regulatory requirements regarding spent fuel pool capacity. Spent fuel assemblies are loaded into dry casks using specialized equipment located in the Unit 2 spent fuel pool area. Entergy has been granted license amendments to allow spent fuel transfer from the Unit 3 spent fuel pool to the Unit 2 spent fuel pool using a newly designed transfer cask. The NRC has performed a significant amount of inspection regarding this fuel transfer to verify that it is executed safely.
Operation of Indian Point absent a long-term solution for spent fuel storage The NRC has repeatedly reaffirmed its view that spent fuel can be safely stored on-site at U.S.
nuclear power plants, either in spent fuel pools or in dry cask storage. The D.C. Circuit of Appeals several years ago remanded the agency's 2010 Waste Confidence Decision and Rule to the agency for further environmental review. The NRC is currently in the process of addressing those concerns. For more information about the Waste Confidence Decision and Rule, see the following webpage on the NRC website: http://www.nrc.gov/waste/spent-fuel-storage/wcd.html Algonquin natural gas pipeline (AIM Project)
Federal Energy Regulatory Commission (FERC) approves the siting and oversees environmental matters related to natural gas pipelines. The Department of Transportation develops the regulations that assure safety in the design, construction, testing, maintenance, and operating standards for natural gas pipelines. Indian Point is required to ensure the plant 3 Enclosure 2 can withstand any hazard the pipeline may introduce to structures, systems, or components important to safety. An installation of a new gas pipeline on the Indian Point property may require Indian Point to perform modifications to the plant, which could require prior NRC review and approval.
NRC actions post-Fukushima The NRC has taken significant action to enhance the safety of reactors in the U.S. based on the lessons learned from the events at Fukushima. After the Fukushima accident, a task force of senior NRC staff reviewed the circumstances of the event to determine what lessons could be learned. In July 2011, the task force provided recommendations to enhance U.S. reactor safety, and these became the foundation of the NRC's post-Fukushima activities. The Commission
then approved a three-tiered prioritization which is currently being implemented. A few examples of the many requirements the NRC has initiated to enhance U.S. reactor safety include requiring strategies that will allow plants to cope without permanent electrical power sources for an indefinite amount of time; requiring reevaluations of flooding and seismic effects or hazards that could impact the site; and reassessing emergency plans and staffing needed to respond to a large accident. Information about these and many other requirements are available at our publically available website on our Japan Lessons Learned webpage: http://www.nrc.gov/reactors/operating/ops-experience/japan-dashboard.html Indian Point Unit 2 and Unit 3 current operating licenses Both Indian Point Unit 2 and Unit 3 license renewal applications meet the "timely renewal" provisions of Title 10 of the Code of Federal Regulations (10 CFR) 2.109(b). This states, "If the licensee of a nuclear power plant licensed under 10 CFR 50.21(b) or 50.22 files a sufficient application for renewal of either an operating license or a combined license at least 5 years before the expiration of the existing license, the existing license will not be deemed to have expired until the application has been finally determined." Indian Point Unit 2 entered the period of extended operations in September 2013, and the original 40-year license for Unit 3 expires in December 2015. While Indian Point Unit 2 continues to operate under its current license, they have implemented commitments made to the NRC in their renewed license application. The NRC has performed inspections to ensure that the licensee has properly implemented these commitments.
Operations of Indian Point before and during Superstorm Sandy The NRC closely monitored the plant during the storm to verify safe operations and to determine whether it should remain online. No safety concerns were identified with the continued operation of Indian Point. Additionally, wind speed thresholds requiring shutdown, which are described in the Indian Point Technical Requirements Manual and monitored by NRC inspectors, were not exceeded. Indian Point Unit 3 automatically shut down in response to electrical grid disturbances caused by the storm. Shutdowns as a result of grid disturbances are within the plant design and safety system r eadiness to provide core cooling or emergency electric power was not affected.
Underground piping and inspections The NRC continues to engage the nuclear industry on the subject of underground piping integrity. The NRC has a significant amount of information related to this topic and our requirements in this area on our website, including inspecting underground piping. More 4 Enclosure 2 information on underground piping can be found at the following webpage: http://www.nrc.gov/reading-rm/doc-collections
/fact-sheets/buried-pipes-tritium.html.
To date, the NRC has not identified any safety significant issues with underground piping integrity at Indian Point.
Potassium Iodide (KI)
The NRC's current consideration of KI in emergency planning is described on the following website: http://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-preparedness/potassium-iodide.html#current-status. Further information on the topic of KI can be found at the following webpage:
http://www.nrc.gov/about-nrc/emerg-preparedness/about-emerg-preparedness/potassium-iodide/ki-faq.html 10-mile emergency planning zones The NRC has determined that the 10-mile-radius Emergency Planning Zone (EPZ) should be the focus of emergency planning activities, including biennial exercises, sirens, and the stockpiling of KI tablets, because that is the area that would likely be mo st significantly impacted by a severe accident at a U.S. nuclear power plant. However, evacuations or other protective actions would not be bound by that geographical area. Emergency planning decision-makers have the ability to call for protective measures beyond the EPZ if they deem that necessary. The Federal Emergency Management Agency (FEMA) takes the lead in initially reviewing and assessing the offsite planning and response and in assisting State and local governments, while the NRC reviews and assesses the onsite planning and response. We would also note that once every six years, a 50-mile Ingestion Planning Zone drill is conducted.