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Category:Inspection Report Correspondence
MONTHYEARIR 05000247/20080122008-06-0202 June 2008 Pre-Inspection Cover Sheet for Indian Point Unit 2, 50-247/2008-012 Inspection; Lead Inspector: J. Richmond ML0709405042007-01-12012 January 2007 Ltr from Orise Dtd 01/12/2007, Final Letter Report for Requested Analyses of Six Water Samples, Set Eleven, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006-007) (Rfta No. 06-001) IR 05000247/20060072007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0709406182007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0634902222006-12-11011 December 2006 Inspection Requests Associated with IP 2&3 PI&R Inspection IR 50-247 & 286 06-006 ML0701105592006-11-0303 November 2006 Interim Report for Requested Analyses for Samples from Sets Seven Through Nine and Sets Eleven Through Fourteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) IR 05000247/20060112006-10-17017 October 2006 IR 05000247-06-011, and IR 05000286-06-009, Indian Point Nuclear Generating Units 2 and 3, Ti 2515/168 IR 05000003/20180062006-10-12012 October 2006 IR 05000317-06-301 and IR 05000318-06/301 on 08/25, 08/28 - 09/01, 09/13 and 09/05-29/2006, Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination ML0701106022006-10-11011 October 2006 Letter Report for Uranium Analysis of One Water Sample, Set Ten, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0701105772006-10-11011 October 2006 Report for Requested Reanalysis of One Vegetation Sample for Nickel-63, Set Seven, Collected Between June 14 and June 22, 2006 from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-00 ML0709405342006-03-15015 March 2006 Ltr from Orise Dtd 03/15/2006, Interim Report for Completed Analyses for Samples from Set Sixteen, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0709405462006-03-0101 March 2006 Ltr from Orise Dtd 03/01/2006, Second Interim Report for Completed Analyses for Samples from Set Fifteen, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0607201482006-02-13013 February 2006 Orise Split Sample Analytical Results from Indian Point ML0709405152006-02-0202 February 2006 Ltr from Orise Dtd 02/02/2006, Second Interim Report for Requested Analyses of Eight Water Samples, Set Fourteen, from the Indian Point Power Station, Buchanan, New York (IR 05000247/2006007) (Rfta No. 06-001) ML0709405742006-01-19019 January 2006 Ltr from Orise Dtd 01/19/2006, Final Report for Requested Analyses of Three Water Samples, Set Twelve, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) IR 05000247/20030142003-12-30030 December 2003 Physical Security Baseline Inspection Report Nos. 05000247-03-014 and 05000286-03-012 IR 05000247/20010142002-03-26026 March 2002 IR 05000247/2001-014, on 12/30-020/9/2002, Entergy Nuclear Operations, Inc.; Indian Point 2 Nuclear Power Plant. Design Control for Mitigating Systems, Barrier Integrity, and Cross-Cutting Issues. Non-cited Violations Identified IR 05000286/20010132002-03-22022 March 2002 IR 05000286/2001-013, Entergy Nuclear Northeast, Indian Point 3 Nuclear Power Plant, Resident Inspection on 12/30/2001 - 02/16/2002 Related to Radiation Protection. No Violations Noted IR 05000286/20010072001-10-0101 October 2001 IR 05000286/2001-007, Indian Point 3 Nuclear Power Plant. on 07/18/2001 Related to Safety and Compliance. Non-cited Violations Noted ML0127501822001-10-0101 October 2001 IR 05000286/2001-007, Indian Point 3 Nuclear Power Plant. on 07/18/2001 Related to Safety and Compliance. Non-cited Violations Noted 2008-06-02
[Table view] 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:Report
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) 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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl ML20100F6352020-04-0808 April 2020 Expert Team Final Report 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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Technical
MONTHYEARNL-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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20100F6352020-04-0808 April 2020 Expert Team Final Report ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0632014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 5 of 5 NL-14-071, Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14107A0432014-03-31031 March 2014 Enclosure 2 to NL-14-045 - Acceptable Value of the Location of the Bottom of the Expansion Transition (Bet) for Implementation of H* at Indian Point Unit 2 ML13337A5942014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14027A5152014-01-16016 January 2014 WCAP-17828-NP, Revision 0, Indian Point Unit 2 H* Alternate Repair Criteria for the Tubesheet Hydraulic Expansion Region (Model 44F - 4-Loop) ML14010A3312014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Indian Point Energy Center, Units 2 and 3, TAC Nos.: MF0744 and MF0745 NL-14-027, LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2013-11-30030 November 2013 LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0082013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 62013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 6 ML13176A0122013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 ML13176A0102013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0092013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 ML13176A0072013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 ML17052A3142013-03-29029 March 2013 Analysis of Potential Sedimentation Effects of Proposed Cylindrical Wedgewire Screens for Intake of Cooling Water at Indian Point Energy Center ML13072A0832013-01-31031 January 2013 12-4116.IPEC.V002, Revision 1, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation: EA-12-051 ML12353A4662012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 2021-02-10
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O R I S E
,ON 1 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
ADDENDUM T O ANALYSIS OF THIRD SET OF WATER SAMPLES FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION N O . 050-247/2005-0111 [RFTA N O . 06-0011
Dear Mr. Kottan:
The Oak k d g e Institute for Science and Education (ORISE) received four water samples on December 28, 2005 from the Indian Point Power Station in Buchanan, New York. The origmal results were sent to you in a letter report dated January 13, 2006. In an e-mail on January 20, 2006, you requested that sample 1677W0014 be reanalyzed for radiostrontium. Two 0.1 Liter Q aliquots of the sample were analyzed for radiostrontium (Procedures AP4, Revision 13; CP3, Revision 2). The concentrations of the two aliquots were 0.2 k 1.2 pCi/L and 0.2 Lf 1.1 pCi/L, respectively. The minimum detectable concentrations for the aliquots were 2.1 pCi/L and 2.0 pCi/L.
The Quality Control (QC) requirements were met for this analysis and are available for your review upon request.
Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you have any questions.
Sincerely, Dale Condra, Manager Laboratory RDC:WI:ar C: T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISE E. IGox-Davin, NRC/NMSS/TWFN 8A23 S. IGrk, ORISE M. Miller, NRC Region I J. White, NRC Region I J. Noggle, NRC Regon I File 1677 Distribution approval and concurrence : Initials Technical Management Team Member QCA &f-55K Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
PH 2: 42 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406
SUBJECT:
REVISED REPORT FOR ANALYSIS OF WATER SAMPLES FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION N O . 050-247/2005-0111 [RFTA N O . 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received seven water samples on October 28,2005 from the Indian Point Power Station in Buchanan, New York. The sample identification and collection data are in Table 1. The samples were analyzed by gamma spectroscopy (GS) (Procedure CP1, Revision 15), for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15, Procedure CP4, Revision 3), and for strontium (Sr-90) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS results are presented in Table 2. The results for H-3 are presented in Table 3. The results for Sr-90 are presented in Table 4. The data for all analyses are reported in microcuries per millhter (pCi/mL).
T h s letter report is a revision to a letter report sent December 8, 2005. The data in the data tables were changed, at your request, to have the concentrations and TPUs contain the same number of significant digits. No other changes have been made.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC fdes are available for your review upon request.
Please contact me at 865.241.3242or Wade Ivep at 865.576.9184 should you have any questions.
Sincerely, Dale Condra, Manager Laboratory RDC:VWI:ar Enclosures C: T. McLaughlm, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISE E. IGox-Davin, NRC/NMSS/TCVFN 8A23 S. Kirk, ORISE File 1677 Distribution approval and concurrence : Initials Technical Management Team Member (JC/& &--3s\\
Quality Manager fW Voice: 865.241.3242 Fax: 865.241-3248 E-mad: condrad@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID NRC Region I Collection Date Collection Time Sample ID 1677W0001 Unit 2 SFP 10/21 /ZOO5 12:45 1677W0002 Unit 1 West SFP 10/20/2005 _ _a 1677W0003 Unit 1 SFDS 10/19/2005 8:25 1677W0004 Unit 2 SFP Wall Gutter 10/24/2005 _ _a 1677W0005 MW-111 10/14/2005 1O:lO 1677W0006 NCD Composite 10/21/2005 12:45 1677W0007 MW-111 9/29/2005 _ _a T h e collcction time was not provided.
Indian Point Power Station projects/l677/Data Tables/2006-02-02 Data Tablcs
j.
3 J
TABLE 2 2'
NRC Region I Radionuclide Concentrations"(pCi/mL)
ORISE Sample ID Sample ID CO-58 CO-60 CS-134 (3-137 1677WOOOl Unit 2 SFP (3.46 k 0.16)E-04b (7.95 f 0.28)E-04 (8.57 f 0.31)E-04 (1.319 f 0.046)E-03 1677W0002 Unit 1 West SFP (-5 f 18)E-07 (2.98 f 0.35)E-05 (2 ?c 14)E-07 (6.74 f 0.22)E-03 1677W0003 Unit 1 SFDS (-5 k 24)E-10 (-8 f 23)E-10 (-1.9 f 2.3)E-09 (9 ? 22)E-10 1677W0004 Unit 2 SFP Wall Gutter (2.4 f 3.4)E-09 (4.56 k 0.49)E-08 (2.64 f 0.12)E-07 (4.88 k 0.15)E-06
-~1677W0005 MM-111 (-7 f 23)E-10 (1.8 f 2.2)E-09 (1.9 f 2.2)E-09
~~~~~~ (-2.1 f 3.6)E-09 1677WO006 NCD Composite (-1.4 f 1.8)E-09 (0.0 f 2.1)E-09' (-6 rf: 19)E-10 (4.48 f 0.42)E-08 1677W0007 Mw-Ill (2.7 k 4.3)E-09 (3.5 f 3.1)E-09 (-5 f 39)E-10 (-9 f 29)E-10
TABLE 3 CONCENTRATIONS OF TRITIUM I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AND COUNTING AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Tritium Concentrations, TPUs, and ORISE Sample ID Sample ID M D C S ~(pCi/mL) 1677W0001 Unit 2 SFP (2.929 & 0.083)E-0Zb (0.053E-02) 1677W0002 Unit 1 West SFP (4.18 _+ 0.72)E-04 (1.1E-04) 1677W0003 Unit 1 SFDS (5.7 2 2.6)E-07 (4.2E-07) 1677W0004 Unit 2 SFP Wall Gutter (2.208 If: 0.047)E-02 (0.02 1E-02) 1677W0005 Mw-111 (7.29 5 0.41)E-06 (0.42E-06) 1677W0006 I NCD ComDosite I (1.425 5 0.053)E-05 f0.042E-05) 1677W0007 I Mw-111 I (2.168 2 0.028)E-04 (0.0042E-04)
'LhlDCs are in parenthesis.
bUncertamtics represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data 'I'ables/2006-02-02 Data Tables
TABLE 4 CONCENTRATIONS OF STRONTIUM-90 I N WATER SAMPLES BY GAS-FLOW PROPORTIONAL COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Strontium Concentrations Sample ID Sample ID and MDCS"(pCi/mL) 1677W0001 Unit 2 SFP (5.87 & 0.24)E-06' (0.12E-06) 1677W0002 Unit 1 West SFP (1.300 k 0.035)E-04 (0.OOOZE-04) 1677WOOO3 Unit 1 SFDS (-0.2 ? 1.2)E-09 (2.1E-09) 1677W0004 Unit 2 SFP Wall Gutter (3.70 k 0.12)E-07 (0.02E-07) 1677W0005 Mw-111 (1.1 k 1.3)E-09 (2.2E-09) 1677W0006 NCD Composite (9.97 k 0.42)E-08 (0.20E-08) 1677W0007 Mw-111 (1.4 k 1.2)E-09 (2.1E-09)
Indian Point Power Station projects/lG77/Data Tables/2006-02-02 Data Tables
O R I S E O A K R I D G E I N S T I T U T E F O R S C I E N C E AND E D U C A T I O N January 13,2006 Mr. Jim Kottan U S . Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF THIRD SET OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION NO. 050-247/2005-0111[RFTA NO. 06-0011
Dear Mr. Kottan:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) received four water samples on December 28,2005 from the Indian Point Power Station in Buchanan, New York. After a phone conversation with Mark Roberts on December 28,2005, the analytical work associated with these samples was changed from routine to urgent. The sample identifications and collection data are presented in Table 1. The samples were analyzed by gamma spectroscopy (GS) (Procedure CPl , Revision 15), for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15; Procedure CP4, Revision 3), and for total radiostrontium (Sr) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS, H-3, and Sr results are presented in Tables 2-4, respectively.
ESSAP's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you have any questions.
Sincerely, Distribution approval and concurrence : Initials Technical Management Team Member + ,?C A-Quality Manager Operated by Oak Ridge Associated Universities for the U.S. Department of Energy
ORISE TABLE 1 ESSAP Sample NRC Region I Collection Collection ID Sample ID Date Time
~~
1677W00014 Mw-101 12/8/2005 12:50 1677W00015 MW-105 12/8/2005 12:20 1677W00016 MW-107 12/8/2005 11:15 1677W00017 MW-38 12/8/2005 10:30 Indian Point Power Station projects/l677/Data Tabled2006-01-13 Data Tables
ORISE TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
%e range of MDCs for the selected radionuclides is 3.9 pCiL to 5.9 p C i L kncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data Tables/2006-01-13 Data Tables
ORISE TABLE 3 CONCENTRATIONS OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Tritium Concentrations, TPUs, and MDCS" 1677W00014 1677W00015 MW-101 MW-105 70
-10 r
f 120b 120 (200)
(200) 1 11 1677W00016 t MW-107 I 130 f 120 (200) 11 11 1677W00017 I MW-38 I 740 f 130 (200) 11 "MDCs are in parenthesis hUncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data TabIes/2006-01-13 Data Tables
ORISE TABLE 4 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES BY GAS-FLOW PROPORTIONAL COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Total Radiostrontium ESSAP NRC Region I Concentrations, T P U ~ ,
Sample ID Sample ID and MDCS(pCi/L) 1 1677W00014 I MW-101 I 3.1
- 1.3b (2.0) 1 11 1677W00015 I MW-105 I -0.2 k 1.2 (2.1) 11 1677W00016 MW-107 0.8
- 1.2 (2.0) 1677W00017 MW-3 8 0.4 k 1.2 (2.1)
MDCs are in parenthesis buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data Tables/2006-01-13 Data Tables
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O A K RIDGE INSTITUTE F O R S C I E N C E A N D E D U C A T I O N 1
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January 3,2006
,. .. I Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF SECOND SET OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION NO. 050-247/2005-0121[RFTA NO. 06-0011
Dear Mr. Kottan:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) received six water samples on December 12,2005 from the Indian Point Power Station in Buchanan, New York. After a phone conversation with Marie Miller on December 16, 2005, the analytical work associated with these samples was changed from routine to urgent. The sample identifications and collection dates are presented in Table 1. The samples were analyzed by gamma spectroscopy (GS) (Procedure CPI, Revision 15),
for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15; Procedure CP4, Revision 3), and for total radiostrontium (Sr) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS results are presented in Table 2. The results for H-3 are presented in Table 3 . The results for Sr are presented in Table 4.
ESSAP's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you have any questions.
Sincerely, DL Dale Condra i%+dL Laboratory Manager Environmental Survey and Site Assessment Program RDC:WP1:db Enclosures cc: T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISEESSAP E. Knox-Davin, NRC/NMSS/TWFN SA23 S . Kirk, ORISEESSAP M. Miller, NRC Region I J. White, NRC Region I J. Noggle, NRC Region I File 1677 Distribution approval and concurrence : Initials, -
Technical Management Team Member Quality Manager P. 0.BOX 117, OAK RIDGE, TENNESSEE 37831-01 17 Operated by Oak Ridge Associated Universities for the U.S. Department of Energy
ORISE TABLE 1 ESSAP Sample NRC Region I Collection Collection ID Sample ID Date Time 11 1677W0008 I Gwsum Plant Stream I 11/30/2005 I 15:20 1677W0009 Trap Rock Quarry 11/30/2005 15:50 1677WOOlO Algonquin Outfall 11/30/2005 15:25 1677W0011 5th Street Well 11/30/2005 16:05 1677W0012 Lefarge Gypsum Plant #1 12/6/2005 11:lO 1677W0013 Lefarge Gypsum Plant #3 12/6/2005 9:55 Indian Point Power Station projectdl 677/1etters/2006-1-3 Data Tables
ORISE TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Sample Radionuclide Concentrationsa (pCi/L)
ESSAP Sample ID ID co-58 Co-60' CS-134 CS-137
?lie range of MDCs for the selected radionuclides is 3.9 pCiL to 4.2 pCi/L.
hZero values are due to rounding
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projectdl 677/letters/2006-1-3 Data Tables
ORISE TABLE 3 CONCENTRATIONS OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ESSAP Sample ID a M D C are
~ in parenthesis.
buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projectdl 677/letters/2006-1-3 Data Tables
ORISE TABLE 4 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES BY GAS-FLOW PROPORTIONAL COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ESSAP NRC Region I Radionuclide Concentrations!
Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1677WOOO8 Gypsum Plant Stream 0.5 rt l.Ob (1.8) 1677W0009 Trap Rock Quarry 0.9 f 1.0 (1.7) 1677W0010 Algonquin Outfall 0.3 f 1.0 (1.8) 1677W0011 5th Street Well 0.4 f 1.0 (1.8) 1677W0012 Lefarge Gypsum Plant #1 1.2 f 1.1 (1.8) 1677WOO13 Lefarge Gypsum Plant #3 0.1 f 1.0 (1.7)
Indian Point Power Station projects/l 677/1etters/2006- 1-3 Data Tables
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U.S. Nuclear Regulatory Commission Region I
-.. !-a Z-J ul 475 Allendale Road W King of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION NO. 050-247/2005-0111 [RFTA NO. 06-0011 11 '
Dear Mr. Kottah:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) received seven water samples on October 28, 2005 from the Indian Point Power Station in Buchanan, New York. The sample identifications and collection dates are in Table 1.
The samples were analyzed by gamma spectroscopy (GS) (Procedure CP1, Revision 15), for tritium (H-3) by liquid scintil.lation analysis (Procedure AP2, Revision 15, Procedure CP4, Revision 3), and for strontium (Sr-90) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS results are presented in Table 2. The results for H-3 are presented in Table 3. The results for Sr-90 are presented in Table 4. The data for all analyses are reported in microcuries per milliliter (pCi/mL). '
ESSAP's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you have any questions.
Sincerely, Dale Condra Laboratory Manager Environmental Survey and Site Assessment Program l2DC :WPI :ar Enclosures cc: T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISEESSAP E. Knox-Davin, NRC/NMSS/TWFN 8A23 S. Kirk, ORISEESSAP File/l677 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager
T t r g k ATP P. 0. BOX 1 17, OAK RIDGE, TENNESSEE 3783 1-01 17 Operated by Oak Ridge Associated Universities for the U.S. Department of Energy
ORISE TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATES INDIAN POINT POWER STATION BUCHANAN, NEW YORK ESSAP Sample NRC Region I Collection Collection ID Sample ID Date Time 11 1677W0001 I Unit 2 SFP I 10/21/2005 12:45 1677W0002 Unit 1 West SFP 10/20/2005 1677W0003 Unit 1 SFDS 10/19/2005 8:25 1677W0004 Unit 2 SFP Wall Gutter 10/24/2005 --
11 1677W0005 I MW-111 I 10/14/2005 1O:lO 1677W0006 NCD Composite 10/21/2005 12:45 1677W0007 MW-111 9/29/2005 --
Indian Point Power Station 167712005-12-08 Data-Tables-1 677
ORISE TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrations"(pCilmL)
ESSAP Sample ID Sample ID c0-58 c0-60 CS-134 CS-137 1677WOOOl Unit 2 SFP 3.5E-04 f 1.6E-05b 8.OE-04 f 2.8E-05 8.6E-04 f 3.1E-05 1.3E-03 f 4.6E-05 1677W0002 Unit 1 West SFP -5.4E-07 f 1.8E-06 3.OE-05 f 3.5E-06 2.2E-07 f 1.4E-06 6.7E-03 f 2.2E-04 1677W0003 Unit 1 SFDS -5,OE-10 f 2.4E-09 -8.OE-10 f 2.3E-09 -1.9E-09 f 2.3E-09 9.OE-10 f 2.2E-09 1677W0004 Unit 2 SFP Wall Gutter 2.4E-09 f 3.4E-09 4.6E-08 f 4.9E-09 2.6E-07 f 1.2E-08 4.9E-06 f 1SE-07 1677W0005 MW-111 -7.OE-10 f 2.3E-09 1.8E-09 f 2.2E-09 1.9E-09 f 2.2E-09 -2.1E-09 f 3.6E-09 1677W0006 NCD Composite -1.4E-09 f 1.8E-09 O.OEOOc f 2.1E-09 -6.OE-10 f 1.9E-09 4.5E-08 f 4.2E-09 1677W0007 MW-111 2.7E-09 f 4.3E-09 3.5E-09 f 3.1E-09 -5.OE-10 f 3.9E-09 -9.OE-10 f 2.9E-09 m
-4
ORISE TABLE 3 CONCENTRATIONS OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AND COUNTING AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrations, ESSAP Sample ID I 2.9E-02 1 I 1677WOOO1 1677W0002 Unit 2 SFP Unit 1 West SFP f
I 4.2E-04
- 8.3E-04b (5.3E-04) 7.2E-05 (1.1E-04) 1677W0004 Unit 2 SFP Wall Gutter 2.2E-02 f 4.7E-04 (2.1E-04) 1677W0005 MW-111 7.3E-06 f 4.1E-07 (4.2E-07) 1677W0006 NCD Composite 1.4E-05 f 5.3E-07 (4.2E-07) 1677W0007 MW-111 2.2E-04 5 2.8E-06 (4.2E-07)
Indian Point Power Station 1677/2005-12-08 Data-Tables-1 677
ORISE TABLE 4 CONCENTRATIONS OF STRONTIUM-90 IN WATER SAMPLES BY GAS-FLOW PROPORTIONAL COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK II I I II ESSAP NRC Region I Radionuclide Concentrations Sample ID Sample ID and MDCS"(pCi/mL) 1677W0001 Unit 2 SFP 5.9E-06 f 2.~lE-07~ (1.2E-07) 1677W0002 Unit 1 West SFP 1.3E-04 -+ 3.5E-06 (2.OE-08) 1677W0003 Unit 1 SFDS -2.OE-10 f 1.2E-09 (2.1E-09) 1677W0004 Unit 2 SFP Wall Gutter 3.7E-07 f 1.2E-08 (2.OE-09) 1677W0005 MW-111 1.1E-09
- 1.3E-09 (2.2E-09) 1677W0006 NCD Composite 1.OE-07 f 4.2E-09 (2.OE-09) 1677W0007 MW-111 1.4E-09 f 1.2E-09 (2.1E-09) a M D C are
~ in parenthesis and based on four hour count times buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station 167712005-12-08 Data-Tables-I677