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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report 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 NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
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Indian Point Energy Center 450 Broadway, GSB3 P.O. Box 249 flffli Buchanan, N.Y. 10511-0249 I. ITel (914) 734-6700 J. E. Pollock Site Vice President Administration January 11, 2008 Indian Point Units 1, 2 and 3 Re: Dockets50-003, 50-247 and 50-286 NL-08-009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Results of Ground Water Contamination Investigation
Reference:
Entergy Letter NL-06-033, "Current Status / Future Plans Regarding Onsite Groundwater Contamination at IPEC," dated April 10, 2006.
Dear Sir or Madam;Entergy Nuclear Operations,
Inc. (Entergy) has completed a comprehensive ground water investigation at the Indian Point Energy Center (IPEC). This investigation was conducted in accordance with the referenced letter from October 2005 through October 2007 as a result of an apparent spent fuel pool (SFP) leak at Unit 2 which was discovered during construction activities within the Unit 2 Fuel Storage Building (FSB) as previously reported.
During the ensuing investigation it also became apparent that the previously known Unit 1 leak was migrating beyond collection points thought to contain it.The scope of this investigation included all three (3) reactor units and all areas of the site where credible potential sources of leakage could exist. The investigation has identified the sources of leaking radioactivity responsible for the radioactive contaminants that have been found in ground water at the IPEC site. The affected ground water regime has been characterized and modeled to determine the nature of leaked contaminants in the environment, identified the sources of the leakage and determined the radiological impacts that result from this leakage. As a result, Entergy has begun implementation of a long term ground water monitoring program and initiated a remediation program. Detailed results of the investigation are provided in the enclosed ground water investigation report, and summarized below.The sources of ground water contamination have been traced back to leakage that originates from two separate structures, the Unit 2 fuel building and the Unit 1 fuel building.
This conclusion is based on the radionuclide and chemical characteristics of the sources, ground water flow patterns, and the concentration gradients within the PaJ2K Indian Point Units 1, 2 and 3 Dockets50-003, 50-247 and 50-286 NL-08-009 Page 2 of 4 plumes. No other sources of leakage to ground water were identified as contributing to these ground water plumes.The resulting contaminated ground water at IPEC can be characterized as two commingled ground water contaminant plumes that flow west towards and into the plants' discharge canal and the Hudson River. The plume originating from Unit 2 was found to be comprised of predominantly one radionuclide,'Tritium (H-3); while the plume originating from Unit 1 is comprised principally of Strontium (Sr-90), with other radionuclides being observed in smaller sub-sets of the plume (e.g., Cobalt (Co-60), Nickel (Ni-63), and Cesium (Cs-137)).
Two interrelated leak mechanisms were identified as having contributed leakage to the Unit 2 Tritium plume. Entergy has determined that there was a legacy leak discovered and repaired in the early 1990's and that there was likely a small leak from the spent fuel pool transfer canal liner (terminated when the canal was drained for inspection in July 2007 and repaired in December 2007), both of which are responsible for the observed ground water contamination.
The legacy leak that occurred in the 1990s was a result of Unit 2 SFP's stainless steel liner being accidentally punctured.
That puncture occurred in 1990 as a result of fuel rack modification activities.
That leak was discovered and repaired in 1992. As a result of that liner damage, SFP water filled the interstitial space behind the liner and concrete structure, and upon reaching a construction joint at the 85' elevation, flowed out through the wall joint on the east side of the Spent Fuel Building (SFB). It is believed that SFP water leaked out of the construction joint at a rate of about 50 gallons per day for about 2 years, leaking into the underlying ground water. An additional consequence of this leak resulted in the interstitial space between the liner and concrete pool structure being left filled with pool water after the damaged liner was repaired.A pin hole sized flaw is now known to have been present in the Unit 2 transfer canal liner. This flaw, a pin hole in a liner weld, was discovered in September of 2007 as a result of two years of varied pool and transfer canal liner inspection activities.
This flaw appears to be present from the time of original construction.
Metallurgical assessments have found there is no ongoing degradation of the liner associated with the cause of the flaw, nor is there an ongoing concern. Inspections of the transfer canal and accessible portions of the SFP liner have been completed and only that single flaw in the transfer canal has been identified.
The transfer canal defect has been repaired.During excavation activities performed in 2005 next to the south wall of the. SFP structure, water seepage was observed on shrinkage cracks. Initially the flow rate was on the order of 1500 ml per day. However that flow rate rapidly decreased over the next few weeks. After that, water flow was intermittent with flow rates of about 20 ml per day becoming the norm. Based upon two years of flow and radiological and chemical sample data, we believe that the higher initial flow rates were due to the shrinkage crack opening up, due to soil pressure on the exterior wall of the fuel pool being relieved by the excavation activities.
This allowed the water that had been trapped behind the liner since 1992 to flow out of the opened crack.
Indian Point Units 1, 2 and 3 Dockets50-003, 50-247 and 50-286 NL-08-009 Page 3 of 4 Hydro-geological characterization data indicates that there is a perched body of ground water in the vicinity of the Unit 2 SFP where clearance rates are very low when compared to the rest of the site. This data supports the hypotheses that some of the pool water released from the 1990's leak has been held up in the ground water in that area. This hypothesis is further supported by dye tracer testing and the fact that the Unit 2 ground water plume also does not contain any short half-lived radionuclide's that are'abundant in Unit 2's SFP water. Thus, it is Entergy's conclusion that the Unit 2"Tritium" plume that has been observed is primarily the result of an old legacy leak, which was being recharged in small amounts by the pinhole leak from the Unit 2 transfer canal.Entergy has determined that Unit 1 west fuel pool water leaks to ground water under the fuel building and is responsible for the Unit 1 "Strontium" ground water plume that was discovered in 2006. Prior to that time, Entergy's predecessor, Consolidated Edison had identified leakage from the west fuel pool in the 1990's and was managing the leakage by collecting it from a re-configured footing drain that surrounded the fuel building.However, based on Entergy's ground water investigation, it has been determined that the pool leakage management program was not successful in collecting all of the leakage. As a result, uncollected contaminants released from the Unit 1 SFP, past and present, have been observed by Entergy's ground water investigation at various locations near the site of Unit 1.Ground water contamination is limited to Indian Point's property and is not migrating towards off-site properties to the north, south or east. The ground water contamination migrates with the site ground water from areas of higher hydraulic heads to areas of lower heads along paths of least resistance, and ultimately discharges to the Hudson River to the west.The radiological dose impact of these leaks due to the resulting ground water contamination has been evaluated.
The only significant pathway for ground water is through consumption of fish and invertebrates in the Hudson River, the calculated doses of which are well below 1/100 of the federal limits.Based upon the results of the ground water investigation, Entergy has been, and will continue to take the following corrective and remedial actions: 1. Continue source term reduction in Unit 1 pool via the installed demineralization system which has been reducing the quantity of radioactivity in the Unit 1 leakage; and remove the remaining Unit 1 fuel and drain the pool to stop leakage from Unit 1 by the end of 2008.
Indian Point Units 1, 2 and 3 Dockets50-003, 50-247 and 50-286 NL-08-009 Page 4 of 4 2. Implement long-term monitoring of the site's ground water which includes monitoring the natural attenuation of the ground water plumes and providing ongoing detection and identification of potential new leaks, in support of ongoing annual assessment of the dose impact. This will be done consistent with the commitments made in the referenced letter. Entergy will also implement' site specific enhancements to the dose assessment method for the 2007 Radioactive Effluent Release Report.Entergy is making no new commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Donald Mayer, Unit 1 Director, Indian Point Energy Center at (914) 827-7716.Sincerely yours, Site Vice President Indian Point Energy Center
Enclosure:
Results of Ground Water Contamination Investigation cc: Mr. Samuel Collins, Regional Administrator, NRC Region 1 Mr. John White, NRC Region 1 NRC Resident Inspector's Office, IPEC Mr. John Boska, Senior Project Manager, NRC NRR DORL Mr. Paul D. Tonko, President, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service w/o enclosure:
Mr. Timothy Rice, New York State DEC