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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:Miscellaneous
MONTHYEARML22013A7062022-01-13013 January 2022
Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G
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
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
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
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
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
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-15-013, 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
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
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
ML14141A5402014-05-0909 May 2014
Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML14071A1832014-04-0101 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
NL-14-042, Entergy Seismic Hazard and Screening 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 Fukushima Dai-ichi.2014-03-31031 March 2014
Entergy Seismic Hazard and Screening 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 Fukushima Dai-ichi.
NL-14-043, Entergy Seismic Hazard and Screening 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 the Fukushima.2014-03-31031 March 2014
Entergy Seismic Hazard and Screening 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 the Fukushima.
ML14071A1982014-03-20020 March 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14015A4172014-01-30030 January 2014
Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage
ML14304A7512013-12-13013 December 2013
Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 8 of 9
NL-13-133, 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time2013-10-0202 October 2013
10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time
ML13221A4172013-07-26026 July 2013
LTR-13-0662 - Susan Lerner, Common Cause New York Ltr Provides a Copy of Generating Influence, Entergy'S Political Spending and the Battle Over the Indian Point Nuclear Power Plant.
ML14304A7522012-12-31031 December 2012
Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 9 of 9
ML12346A3432012-11-20020 November 2012
Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End
ML12346A3422012-11-20020 November 2012
Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434
NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 4342012-11-20020 November 2012
Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434
NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End2012-11-20020 November 2012
Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End
NL-12-136, 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments2012-10-0101 October 2012
10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments
NL-14-002, Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies2012-09-20020 September 2012
Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies
NL-12-009, Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 52012-01-11011 January 2012
Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5
ML12040A3102012-01-11011 January 2012
Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5
ML11280A1212011-09-28028 September 2011
License Renewal Application - Completion of Commitment #30 Re Reactor Vessel Internals Inspection Plan
NL-11-094, Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension2011-08-0303 August 2011
Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension
NL-10-109, CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/20102010-10-12012 October 2010
CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML11299A1752010-02-0808 February 2010
Lr Hearing - Indian Point Task I Report - Deliverable (Redacted Version)
ML0936410942009-12-30030 December 2009
Preliminary Power Authority of the State of New York, Indian Point No. 3, Nuclear Power Plant, Systems Interaction Study. Volume II
ML0926401772009-08-28028 August 2009
Environmental Science and Engineering
NL-09-095, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes2009-07-21021 July 2009
Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes
ML0905407042009-01-0909 January 2009
American Radiation Services, Inc. Laboratory Analysis Report No. ARS1-08-02367, Revised 01/09/2009
2022-01-13
[Table view] |
Text
2609 North River Road, Port Allen, Louisiana 70767 (800) 401-4277 -- FAX (225) 381-2996 RNATIONAL American Radiation Services, Inc.Laboratory Analysis Report ARS1-08-01563 Prepared for.Nuclear Regulatory Commission (NRC)James Noggle USNRC Region 1 475 Allendale Road King of Prussia, PA,19406 James. Noggle@nrc.gov Phone: 610.337.5063 Fax:~#nager Review4 1) )'h Fr x &A il1\a" .-Management Notes: Arnencan Radiation Services, Inc. assumes no liability for (he use or intarpretation of any anflytifal results provided other than the mots of the analysis itself.Reproduction of this report in less than fut requires the written consent of the client.Contact Person: Questions regarding this analytical report should be addressed to: Project Manager ProjectManagers@amrad.com Phone: 225.381.2991 Fax: 225.381.2996 LELAP Cert#.30658 NELAP Cert# E87558 INTERNATIONAL 2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 ARS Sample Delivery Group: ARS1-08-01563 Client Sample ID: MW-66-21-(005)07-29/1148 Sample Collection Date: 07/29/08 11:48.Sample Matrix: Aqueous Request or PO Number: N/A ARS Sample ID: ARS1-08-01563-001 Date Received:
8/12/2008 Report Date: 09/15/08 10:19Afal5ysis A na lys' f Analysis T ,.MC Dep o. Reslts E 2 ..............
....... ..MN-54 0 -o.784 0.782 2.600* l~C 1.300 Qu~al Analysis I Analysis Units Test Method S pCi/L I ARS-007/EPA 901.1* Analysis I AnislyalO ,Analysis Analysis Date/rime Technician 8/21/08 16:01 )LA Tracer/Chem RecoNer t N/A FE-59 0 952 1.529 5.140 2.570 pCi/L ARS-007/EPA 901.1 8/21/08 16:01 JLA N/A CO-58 -0.573 0.778 2.600 1.300 i pCVL .1 ARS-007/EPA 901.1 8/21/08 16:01 " LA .N/A O-60 0622 .0.650 2.240 1 1.120 1 pCi/L. ARS-007/EPA 901.1 8/21/08 16:01 31A N/A ZN-65 0.000 2.499 1 8.400 4.200 ' PCi/L ARS-007/EPA 901.1 8/21/08 16:01 .LA N/A NB-95 J -0.738 1.953 2.81D 1.405 CA 8 N/A ZR-95 0783 1264 4.240 2.120 ' pCI/L I ARS-007/EPA 901.1 8/21/08 16:01 ILA N/A CS-134 -0.289 1.169 2.960 1.480 pci/L ARS-007/EPA 901.1 8/21/08 16:01 3LA N/A C-137 -0.783 0858 1 2.850 1.425 pCI/L t ARS-007/EPA 901.1 8/21/08 16:01 JLA N/A S BA-140 " i 4.539 I .537 10.400 5.200 pCi/L AR5-O07/EPA 901.1 8/21/08 16:01 2LA N/A... ...........- -.........................
ARS O-EPA 901.8/21/08 1 ..A......LA-140 -0.601 12 3.310 I 1.655 J pCI/I ARS-007/EPA 901.1 8/21/08 16:01 21LA j N/A SR'90 1.005 0.216 0.588 j 0.277 pCi/L I ARS-032/Eichrom SRW-01 { 8/28/08 17:35 8JS 58,00% i*! 130 666 163239 7,9.400 .p/I .ARS-054/EPA 906.0 : 9/8/(0 8:39 I BS N/S NI-63 3.0899 4.4642 7.4175 3.6493 pCl/L ARS-022 8910/09 2:05 B3S N/S____ __ _ Ij__ _ -_ _ _ _ _ _ i ___/___I NOTES: Shipment#
08-152 rý=A c ~ 1 i Rr c5 i , £1 P5roct Manager keCýr -Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results provided other than the cost of the analysis Itself. Reproduction of this report in less than full requlres the written consent of the client.LELAP Certificate#
30658 NELAP Certificate I E87558
-INTERNATIONAL 2609 North River Road, Port Alien, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 ARS Sample Delivery Group: ARSI-08-01563 Client Sample ID: MW-66-36-(005)07-29/1205 Sample Collection Date: 07/29/08 12:05.Sample Matrix: , Aqueous Request or PO Number: ARS Sample ID: Date Received: Report Date: N/A ARSI-08-01563-002 8/12/2008 09/15/08 10:19 Anlss Anlss .Analysis Anaysi iL Analyi Descripthon Results Error +/- 2 s M l " Ua! Units I Test MethOd -I MN-54 0.282 1 0.685 " 2.340 1.170 pCiL ARS-007/SPA 901.1 1-8 FE-59 1.794 1.079 3.5S0 1.775 pCiL ARS-007/EPA 901.1 8 Analysis Analysls Date/Time Technician
/21/08 16:00 1 LA Tracer/Chern N/A$ILA N/A/21/08 16:00 ILA N/A it___ ____ I t CO-58 0.007 0.686 2.260 1.130 pCi/L ARS-007/EPA 901.1 8/21/08 16:00 ILA N/A CO-60 0.008 0.687 F 2.450 1.225 1 pCI/I ARS-007/EPA 901.1 I 8/21/08 16:00 )LA N/A ZN-6S _ "0.101 1.311 j 4.500 2.250 pCi/Li ARS-007/EPA 901.1 8/21/08 16:00 " LA N/A NB-95 -0.715 0.732 2.440 1.220 pCi/L ARS-007/EPA 901.1 8/21/08 16:00 .A N/A ZR-95 -0.232 6.055 1 4.030 2.015 pCi/L I ARS-007/EPA 901.1 8/21/08 16:00 ILA. N/A CS-134 -0.438 2.482 2.540 1.270 pCi/L ARS-007/EPA 901.1 8/21/08 16:00 --A N/A C13.270 0.681 2.300 1.150 pCV'L j ARS-007/EPA 901.1 8/21/08 16:00 ILA N/A BA-140 -4.173 26.705 10.300 5.150 pCI/L ARS-007/EPA 901.1 8/21/08 16:00 LA I N/A LA- 140 1 r2.118 2.508 I 3.430 1.715 pCi/L ARS-007/EPA 901.1. 8/21./08 16:00 ILA -N/A SR-90 14.269 1.149 0.566 0.267 j pCi/L ARS-032/Eilchrom SRW-01 8/28/08 17:35 BS 6600%H-3 4630.409 499.979 160.739 j 79.153 pCi/ I ARS-054/EPA 906.0 9/8/08 12:47 N/S NI-63 7.4-21 4 .7 7.4096 i 3.6455 -, CI- AR--022 9/10/0-8 6I:4 8)5 N/S., ......................
.. ........--- ----- .-....me......NOTES: Shipment#
08-152 -* Prdject Manager n.. .Notes; American RodiaLion Services, Inc, assumes no liability for the use Or Interpretation of any analytical results provided other than the cost of the analysis itself. Reproduction of this report In less than full requires the written consent of the client.LELAP Certificate#
30658 NELAP Certificate
- E87558 St PAGE 1 of 2 NRC FORM 303 U.S. NUCLEAR REGULATORY COMMISSION LABORATORY USE ONLY (4-2004) CONTROL NUMBER REQUEST FOR ANALYSIS AND CHAIN OF CUSTODY LABORATORY:
SAMPLE LOCATION (LICENSEE)
LICENSEE NUMBER DOCKET NO.INDIAN POINT ENERGY CENTER SAMPLE SUBMITTED
"# TOTAL TYPE -VOLUME WEIGHT DATE SAMPLES SUBMITTED PRIORITY fl ROU~iNE GROUND WATER 2000 ML -2 Kg I [] URGENT SAMPLE COLLECTION INTERVAL MONTH DAY YEAR TIME START INSPECTOR RESPONSIBLE TELEPHONE NUMBER STOP: Jim Noggle (USNRC) (610) 337-5063 LIST DESIRED LIST DESIRED ANALYSIS TO BE PERFORMED LLD (Optional)
OTHER TYPE OF ANALYSIS (Specify)
LLD (Optional)
[Z GROSS ALPHA (GA) F-7 STRONTIUM-90 (Sr90)] GROSS BETA (GB) NICKEL-63 (Ni63)*[]GAMMA SPEC (GS) El-STRITIUM (H3) I-D CARBON-14 (C14) D D-IODINE-25 (1125)RELENQUISHED BY RECEIVED BY DATE TIME REASON FOR CHANGE OF CUSTODY-56COIRI s~ro~"wq:1-$
r- 8-6-2006 /030 Prer /'? jlA, FEE RECOVERABLE NO YSTAC NUMBER REMARKS:'NOTE: SAMPLES WILL BE DISCARDED AFTER ANALYSIS UNLESS REASON ARE NOTED IN REMARKS ABOVE.NRC FORM303 (4-2004)PRINTED ON RECYCLED PAPER a PAGE 2 of 2 NRC FORM 303 U.S. NUCLEAR REGULATORY COMMISSION LABORATORY USE ONLY (4-2004) CONTROL NUMBER SAMPLE RECORD -Continued LABORATORY:
SAMPLE SAMPLE NAME COLLECTION REMARKS, PRESERVATIVE NUMBER AND DESCRIPTION DATE/TIME ANALYSIS REQUESTED, ETC.MW-66-21-(005), Ground Water Split Sample of MW-66-21-(005)
Sample is unfiltered
& unpreserved.
Analyze fo c, _ _ Gamma Spec, H3, Sr9O, Ni63 MW-66-36-(005)
Ground Water Split Sample of MW-66-36-(005)
Sample is unfiltered
& unpreserved.
Analyze to__ Gamma Spec, H3, Sr9O, Ni63 NR ,OMO (420)PITDONRCCE AE NRC FORM303 (4-2004)PRINTED ON RECYCLED PAPER OA1 RCNRDATION SERVICES, INC.2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225)'381-2996
- QC Results Report Sample Delivery Group: ARSI-08-01563 Date Received:
8/12/2008 Laboratory Control Sample Evaluation Antclysis Analyt. Analysis CSU I C) DC Expacted Report Analysis Analysis Analysis Percent Acc BItch Type I Valeu Units Test rasthod Date/Time Technidan Recovery Accaptanca N/A LCS Ni-63 237.73 55.2 8.6999 204.44 pCi/L ARS-022 9/9/08 13:28 BIS 116 75%-125%Blank Evaluation Aays 1QC1 1Analysis Ip.~ ReotAIay" Antlychs yp Analyt. Casis IEpected Report An(lysis
- Analysis AWslyala *_atch Type R__ut_ I _ ( )
- ile Units Test Method Data/Tim a j Tedhnician N/A MBL Ni-63 '1.023 4.5347 7.6916 NA U pCi/L ARS-022 9/9/08 21:58 B)S RER Duplicate Evaluation Analysis QC Analysis etst CSU I( (1) Result2 CSU 2 (is) Analysils Analysis Arnlysi Analytis R cRER Batchs Type Description
+/- 1 Units Tea Maehod Date/Tin.
Techinician RER Acpanc.R N/A LCSD Ni-63 237.73 55.2 229.996 53.406 pCl/L ARS-022 9/9/08 17:42 BI5 0,07 DER Duplicate Evaluation Analys QC alyi sI (1 ) Result 2 CSU 2 () Qua Analys is Analyysi Analysis DER NAtch IType IDes 27iption 5 229.9Un96t 5e.T6t Method Dat9/Tim9 echn/ia8 74.5. 20 N/A ILCS0 NIM-63 237.73 1 55.2 1229.996 153.466 1 PCI/L ARS-022 9/9/08 17A42 -035 0.20<Projnect mi"nager Rlk" Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results provided other than the cost of the analysis itself. Reproduction of this report in less than full requires the written consent of the client.LELAP Certificate#
30658 NELAP Certificate
- E87558 MERICAN RADIATION SERVICES, INC.2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 QC Results Report Sample Delivery Group: ARSI-08-01563 Date Received:
8/12/2008 Laboratory Control Sample Evaluation Analysis QC Anetyte Analysis I (1 Expected et Qual Report Analylo Analylis Analysli Percent LCS Batch Type Results I MDc I value Units I TeWt Method Dote/Time Tachnici.n Recovery (%) AccIltlnce ARS1-B08-02293 LCS H3 1136.06 " .61.4 16 158.48416 1270.45 pCi/.L ARS-054/EPA 906.0 9/4/08 128:01 B35 89 75%-125%Blank Evaluation A Anlysis QC ] 1 Analysis CSu i (1s) MDC Expected lReport. Analysis Analysis Analysi&Btch Typ o je Results value Unit. Test Method Date/Tkne Technician ARS1-B08-02293 M8L H3 67.923 94.439817 158.41962 NA U pCVL ARS-054/EPA 906.0 9/5/08 2:16 BIS RER Duplicate Evaluation Anallysis Qc Analysis Reut1 CU1 (1 e) Result 2 AnSU Anlyi Anaysi ,Aayi Unt ER Ac Rtn Botch Type Description Res ult 1 CSU CSU 2(1 s) Qs al Unito Teat Method Date/Tim.
Technic ien ER Acce tn.R j I_ IF I_ I I_ _ I n_ _ F11 .ARS1-808-02293 LCSD H3 13136.06 161.4 1143.2572 161.9636 pCi/L ARS-054/EPA 906.0 9/4/08 22:09 BJS .0.02 <I DER Duplicate Evaluation Anlyi TQC1Analysias
[A~n-.i.iT AsOlysi. ] Asyao [Analyst.
DDER Anlyi DE DceRtnc Analysis Q- Tp ascripsion Result I CSU 1 (1I) Result 2 CSU 2 (1.) Qual T Meth Moisod Ata/lysi Technicayn Batch .yI Dc r I .I I I [ Units T I arpne ARS1-808-02293 LCSD H3 1136.06 161.4 1143.2572 161.9636 pCi/LI ARS-054/EPA 906.0 9/4/08 22:09 BIS 0.06 < 3 Matrix Spike Anlyal C Unspiked Report Analysis Analysis Analysis Percent LCS Anl Q A (1 ) Spike Con. Qul A ___ nc.Botch Type Results Activity Unit. Test Method Dote/Time Technicton Recovery(%)
Acceptonce I i Range ARS1-808-02293 MS H3 13755.623 1429.035 1862.953 13970.11 pCC/L ARS-054/EPA 906.0 9/5/08 6:24 83S 85 609/o-140%
Proj ct Manager l Note": American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results provided other than the cost of the analysis itself. Reproduction of this report in less than foll requires the written consent of the client.LELAP Certificate#
30658 -NELAP Certificate
- E87558 AMERICAN RADIATION SERVICES INC QC Results Report 2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-32996 Sample Delivery Group: ARSI-08-01563 Date Received: 08/12/08 Laboratory Control Sample Evaluation Analysis Qc Ana1te Analysi sC Expected If Report Analysis Analysis I Analysis T Percent LCS BRtch Type Results I (1 6) DC Value ,Units Test Method I TeR ARS1-808-02253.
LCS Sr-9 0 23.536 1.834 0.541 20.835 pCI/L ARS-032/FPA 905.0 8/28/08 14:29 BIS 113 75%-125%Blank Evaluation Analysis Qc AnalYtO Analysis su I (I.) MDC Expected i l Report "Analysis Analysis Analysis Batch Type Result. Vlue. Qul Units Test Method Dste/Time Technician ARS1-B08-02253 MBL] Sr-90 0.065 0.180 0.618 NA U pCI/L ARS-032/EPA 905.0 8/28/08 14:29 BIS RER Duplicate Evaluation Analysis Result ] CSU 1 (1 e) Result 2 CSU 2 ( Xe) QulAnaly is Analysis M DAnaelysis Analysis RER Ietch Type Description
[Units Test Method Di/Tene Technician RA_ _.pt ARS1-B08-02253 LCSD Sr-90 23.536 1.834 21.025 1.649 pCi/L ARS-032/EPA 905.0 8/28/08 14:29 8S1 0.72 < 1 DER Duplicate Evaluation Anlysi 1 QC a Al i AnalysisAnlysie Alysi 1 DR Retch oType Descrip Bton e CSU I 1 1 Result 2 CSU 2 (1.) Q unl i Anysl lysis. D E R Units Test Method Dete/Ti. Technigan E. cceptnceR ARS1-B08-02253 LCSD Sr-90 23.536 1.834 21.025 1.649 pCi/L ARS-032/EPA 905.0 8/28/08 14:29 831 S 2.04 < 3 Proect Manager Revi Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results provided other than the cost of the arlalysis itself. Reproduction of this report in less than full requires the written consent of the client.LELAP Certificate#
30658 NELAP Certificate
- E87558 QKI.'RS I INTERNATIONAL 2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX4aa5) 381-2996 QC Results Report Sample Delivery Group: Date Received: ARSI-08-01 563 08/12/08 'Laboratory Control Sample Evaluation Analysis QC [ Analysis S Expected Report Analysis Analysis Analysis Percent LCS Acceptance Retch Type nlt Results CS I MC Valcueo Qa Units Test Method Date Technician Recovery (%) Range ARS1-808-02204 LCS CO-60 .24779.00 495.75 200.80 25315.22 pCi/g EPA 901.1 .08/18/08 ILA 98 75%-125%ARS1-B08-02204 LCS CS-137 15083.00 359.87 137.80 15285.98 pCi/g EPA 901.1 08/18/08 ILA 99' 75%-125%ARS1-B08-02204 LCS AM-241 34007.00 1235.00 277.10 34794.33 pCi/g EPA 901.1 08/18/08 ILA 98 75%-125%Blank Evaluation Anaiysis Q Aflyte Analysis CSU 1i(1) MDC Expected Report Analysis Analysis Analysis Batch Type Results Value 1 Units Test Method Data Technician ARSI-808-02204 MBL CO-60 -0.001 0.005 0.005 NA U pCi/g EPA 901.1 08/18/08 JLA ARSI-B08-02204 MEL CS-137 0.001 0.001 0.004 NA U pCi/g EPA 901.1 08/18/08 ILA ARSI-B08-02204 MEL AM-241 -0.001 0.014 0.006 NA U pCi/g EPA 901.1 08/18/08 JLA RER Duplicate Evaluation Analysis QC Analysis Analysis Analysis Analysis Analysis RR batch Type Description Result I RF 1ca ROE al 2CU2(s Qa myi Units Test Method Date Technician RER AccltanceeRange ARSI-808-02204 LCSD CO-60 24779.00 495.75 25129.00 492.32 pCI/g EPA 901.1 08/18/08 JLA 0.35 < 1 ARS1-BO-02204 LCSD CS-137 15083.00 359.87 15425.00 341.69 pCi/g EPA 901.1 08/18/08 JLA 0.49 < I ARS1-808-02204 LCSD AM-241 34007.00 1235,00 34050.00 1247.60 pCi/g EPA 901.1 08/18/08 1LA 0.02 < I DER Duplicate Evaluation\
Analysis Qc Analysis Result 1 rSU 1 (1 6) Result 2 CSU 2 ( Is AnalysI Analyasi Analysis Analyss DER DER batch Type Description Units Test Method Date Technician AcceptanceRage.
ARS1-B08-02204 LCSD CO-60 24779.00 495.75 25129.00 492.32 pCI/g EPA 901.1 08/18/08 31LA 1.00 " 3 APRS1-B08-02204 LCSD CS-137 -15083.00 " 359.87 15425.00 341.69 pCl/u EPA 901.1 08/18/08 ILA 1.38 < 3 ARS1-BOB-02204 LCSD AM-241 34007.00 1235.00 34050.00 1247.60 pCi/O EPA 901.1 08/18/08 ILA 0.05 < 3 QulyAssurance Notes: American Radiation Services, inc. assumes no liability for the use or interpretation of any analytital results provided other than the cost of the analysis itself. Reproduction of this report in less than full requires the written consent of the client.LELAP Certificate#
30658 NELAP Certificate
- E87558 2609 North River Road -Port Allen, Louisiana 70767 RS CA1 (800) 401-4277 FAX (225) 381-2996 AMENAN RDIAION SEAVICES, INC.Notes: Comments: 1.0) Soil and Sludge analysis are reported on a wet basis or an as received basis unless otherwise indicated.
2.0) The data in this report are within the limits of uncertainty specified inthe reference method unless specified.
3.0) Modified analysis procedures are procedures that are modified to meet the certain specifications.
An example may be the use of a water method to analyze a solid matrix due to the, lack of an officially recognized procedure for the analysis of the solid matrix.4.0) Derived Air Concentrations and Effluent Release Concentrations are obtained from 10 CFR 20 Appendix B.5.0) Total activity is actually total gamma activity and is determined utilizing the prominent gamma emitters from the naturally occurring radioactive decay chains and other prominent radioactive nuclides.
Total activity may be lower than~the actual total activity due to the extent of secular equilibrium achieved In the various decay chains at the time of analysis.
The total activity is not representative of nuclides that emit solely alpha or beta particles.
6.0) Ra-228 is determined via secular equilibrium with its daughter, Actinium 228. (Gamma Spectroscopy only).7.0) U-238 is determined via secular equilibrium with its daughter, Thorium 234. (Gamma Spectroscopy only).8.0) All gamma spectroscopy was performed utilizing high purity germanium'detectors (HPGe).9.0) ARS makes every attempt to match sample density to calibrated density; however, in some cases, it is not practical or possible to do so and data results may be affected.Method
References:
1.0) EPA 600/4-80-032, Prescribed Procedures for the Measurements of Radioactivity in Drinking Water, August 1980.2.0) Standard Methods for Examination of Water and Waste Water, 18 t 1992.3.0) EPA SW-846, Test Methods for Evaluating Solid Waste, Third Edition, (9/86). (Updated through 1995).4.0) EPA 600/4/79-020, Methods for Chemical Analysis of Water and Waste, March 1983.5.0) HASL 300 Definitions:
1.0) BDL Analyte not detected because the value was below the detection limit.2.0) ND Not detected above the detection limit.3.0) Detection Limit The minimum amount of the analyte that ARS can detect utilizing the specific analysis.4.0) B Method Blank 5.0) D Method Duplicate 6.0) MS Matrix Spike 7.0) S Spike 8.0) RS Reference Spike 9.0) *SC Subcontracted out to another qualified laboratory 10.0) NR Not Referenced 11.0) N/A Not Applicable 12.0) .Reported as a calculated value 13.0) False Positive due to interference from Bi-214 Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results provided other than the cost of the analysis itself. Reproduction of this report in less than full requires.the written consent of the client.LELAP Cert# 30658 NELAP Cert# E87558
