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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 ARS1-08-01560 Preparedfor:
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:
Proje" nager Review Management RA)iw Notes: American Radiation Services. Inc. assumes no liability for the use or Interpretation of any analytical mrults provided other than the cost of the analysis itself.
Reproduction of this report in less than tull requires the witten consent of the client.
Contact Person: Questions regarding this analytical report should be addressed to:
Project Manager ProjectManagers@armrad.com Phone: 225.381.2991
-Fax: 225.381.2996 LELAP Cert# 30658 NELAP Cert# E87558
2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 INTERNATIONAL ARS Sample Delivery Group: ARS1-08-01560 Request or PO Number: N/A Client Sample ID: MW-66-21-(004)04-21/1410 ARS Sample ID: ARSI-08-01560-001 Sample Collection Date: 04/21/08 14:10 Date Received: 8/12/2008 Sample Matrix: Aqueous Report Date: 09/15/08 09:51 Analysis Analysis Analysis MDC O. L DLC iQua]i Analysis Unt Analysis Analysis Analysis Tracer/Chemr Descripion .Results Error +/- 2 s 0 . i units Test Method I Date/finne Technician Rec/ery I MN-54 T -70 0.795 2.660 I 1.330 1 pCl/L i ARS-007/EPA 901.1 8/25/08 16:06 JLA N/A 4--
FE-59 0.286 j 1.402 4.790 . 2.395 pCi/L ARS-007/EPA 901.1 I 8/25/08 16:06 ; JLA N/A pCt/L ARS-007/EPA 901 1 I 8/25/08 16:06 ILA co-58 *1.0S1 3.178 2.590 1.295 N/A
.-.--------...---............ -_--.-.--- .-- __-0--. --.-
CO-60 -0.257 f 1.439 2.660 I 1.330 I PC/L ARS-007/EPA 901.1 8/25/08 16:06 1 ILA N/A ZN-65 2468 2.376 6070 3035 pCi/L ARS-007/EPA 901.1 8/25/08 16:06 JLA N/A NB-95 0.215 0.712 2.410 1.205 pCi/L ARS-007/EPA 901 8/25/08 16:06 ILA N/A
- *R95 -0.467 i 1,324 4 480 i 2 240 i pCt/L ARS-007/EPA 901.1 ,8/25/OR 16
- 06 3LA N/A 1 S5-134 ! 0.907 0.817 2.720 1 1360 ! pCl/L i ARS-007/EPA 903.2 8/25/08 16:06 ]L .. N/A S-137
- 298 0.9 2030 i .3050 pCi/L ARS-007/EPA 901.1 N/A AR1400.4679 SLA1340 ._ ........
1.6324 0945 I_
10510 700.245 4.0 3.260_ 1.630 0
pC/L pCi/L ARS 007/EPA ARS-007/EPA 901.1
__ 901.1_ _ _
8/25/08 8/25/08 16:06
__ 16:06 ILA_
ILA _ ....
N/A N/A BA-14 -017982.3515.68 102.7001 58.350 p!/ AR-0/P ARS-032/EPh 90. . /50 1-6 J. /
CSR-90 21.59222 9 0.390 pCi/L 9 RW-01 8/26/08 13:46 82S 41.00% I H '982.685 50568 162.621 80.080 I pCi/L ARS-054/EPA 906.0 9/6/08 15:24 BS I N/A Nl-63 1.5697 4.774 8.0688 I 3.9699 pCi/L ARS-022 BIS N/A.
.. -J ........... .. ..... .....
NOTES: Shipment# 08-152 Project Manager Rqle~v Notes: American Radiation Services, Inc. assUrnesno liability for the use or interpretation of any analytical results providecl 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
.. RS 1INTERNATIONAL 2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 ARS Sample Delivery Group: ARSI-08-01560 Request or PO Number: N/A Client Sample XD: MW-66-36-(004)04-21/1325. ARS Sample ID: ARS1-D8-01560-002 Sample Collection Date: 04/21/08 13:25 Date Received: 8/12/2008 Sample Matrix: Aqueous Report Date: 09/15/08 09:51 Analy its Analysis Analysis MDC II DLC ! Analysis Analysis Analysis Analysis Tracar/Chern Descrip btan ... ........ ..........
Results ... -
Error /- -...
2s 22.570 7.....
1.285 1
/.I pCI/L Test Method Date/Time Technician MN-54 0.465 0.767 ARS-007/EPA 901.1 8/25/08 16:06 JLA N/A FE-59 -0.94 18.882 5.700 i 2.850 pCI/L ARS-007/EPA 901.1 8/25/08 16:06 1 ILA N/A CO-58 """"
O *
- -0.300
! 0.707
. -- 0"3 ....
238
.'"'21.
3... 0 i S0190 1,.390 i pCi/L pCi/L ARS-007/EPA ARS 0 7/ 901.1.
A 90 8/25/08 1606'A 8/25/08 1 : 66 3.LA N//
CO____60_ -1.62_3.07_2.69 pCi/L ARS 007/EPA 901.1 8/25/08 16:06 ILA N/A ZN-65 -2.234 4.053 5.670 1 2.835 1 1 pCi/L ARS-007/EPA 901.1 8/25/08 16:06 .LA N/A NB-95 0.036 0.677 2 330 1 165 pC/L I ARS-007/EPA 901.1 I 8/25/08 16:06 iLA N/A ZR-95 -0,424 2.238 4.270 2.135 I pCi/L I ARS-007/EPA 901.1 ] 8/25/08 16:06 JLN/A 4-1.271 ,3.613 2 .90 1495 I ,pCi/, ARS-007/EPA 901.1 8/25/08 16:06 - LA
,,N/A CS 137 CS-137 -
"-0.660 0.6.. 0...
.. "] ... 82 0.805 .... ......65 2.690 1.345 p -
pCi/L .. AR 0 ARS-007/EPA . 1 901.1 8/25/08 B / 0 16:06...
16:06 JLAA.N/Aý l N/A BA-140 1.842 3.028 10.200 5.150 pCi/L z ARS-007/EPA 901.1 ] 8/25/08 16:06 )ILA N/A
-140-0.009 0.864 2.990 1.495 pC /L I ARS-D07/EPA 901.1 8/25/08 16:06 IL.JA N/A 4 -
SR-90 16.485 1.327 0.651 0.307 1 pCi/L ARS-032/EiChrOm SRW-01 8/26/08 13:46 ! BJS 58.00%
H-3 . 5220.405 I. 559.443 160.470 79.021 pdVL ARS-054/E 9/6/08 19:32 ) BJS N/A I
-i*N-63 ..
........... ." .496.
2.496 [ 4.8098 H '. "* -- H 8.0646 3.9679 1 pCI/L ARS-022 BiS N/A NOTES: Shipment# 08-152 Un~~vL)l iV~ri PFoIct Maonager R Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any ana!ytical 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.
- I LELAP Certificate# 30658 NELAP Certificate # E87558
5 5d/l PA1VdFAJ d 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
[L ROUTINE GROUND WATER 2000 ML -2 Kg URGENT SAMPLE COLLECTION INTERVAL MONTH DAY YEAR TIME START INSPECTOR RESPONSIBLE TELEPHONE NUMBER Jim Noggle (USNRC) . (610) 337-5063 STOP LIST DESIRED LIST DESIRED ANALYSIS TO BE PERFORMED LLD (Optional) OTHER TYPE OF ANALYSIS (Specify) LLD (Optional)
D GROSS ALPHA (GA) STRONTIUM-90 (Sr90)
- GROSS BETA (GB) NICKEL-63 (Ni63)
GAMMA SPEC (GS) r-_
" TRITIUM (H3) D D CARBON-14 (C14) D D IODINE-125 (1125) E RELENQUISHEDBY RECEIVED BY DATE TIME REASON FOR CHANGE OF CUSTODY
- ,2 5SECuiti .Sr&ace $ ZoPV
- g~§z 103d prizre Ar /,l9,,s, FEE RECOVERABLE I NO YES TAC NUMBER REMARKS
Inspection Report: 1007005 NOTE: SAMPLES WILL BE DISCARDED AFTER ANALYSIS UNLESS REASON ARE NOTED IN REMARKS ABOVE.
NRC FORM303 (4-2004) PRINTED ON RECYCLED PAPER
Ak PAGE 2 of 2 NRC FORM 303 U.S. NUCLEAR REGULATORY COMMISSIOI-k 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.-(004) Ground Water Split Sample of MW-66-21-(004) 4'2t' c i Ic Sample is unfiltered & unpreserved. Analyze for
- I I Gamma Spec, H3, Sr90, Ni63 MW-66-36-(004) Ground Water Split Sample of MW-66-36-(004) Sample is unfiltered & unpreserved. Analyze tfo Gamma Spec, H3, Sr9O, Ni63 NRC 0RM33 (-200) PINTE ON ECYLIW APE NRC FORM303 (4-2004) PRINTED ONRECYCLED PAR
2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 ieSERVICES.INC.
QC Results Report Sample Delivery Group: ARSI-08-01560 I Date Received: 8/12/2008 Laboratory Control Sample Evaluation aysi QC A yte Analyss (1) MDC Expected Report Analysis Analysis Analysis Percent L .I Aatch Type Result Ilys I Value Units Test Method DaeTima Technician Recovery %) n N/A LCS Nl-63 210.12 48.8 8.0357 204.49 pCi/L ARS-022 8/28/08 20:51 BJS 103 175%-125%
Blank Evaluation Analysis tch Bac QC ye Type Analyte Analysit Anl Results sis 1(1 a)
I ( )
MDC DC Expected Value IuaQua.l Report Units I Analysis T______
Test Method L Analysis it/ia Dets/Tine Analysis ic___
Techn_____ia Te-hnidan N/A MBL Ni-63 -0.141 4.68 7.9878 NA U PCI/L ARS-022 8/29/08-5:17 BJS RER Duplicate Evaluation aly QC Analysis Analysis Analysis Analysis RER tnE atcrl Type Description Result 1 CSU I (1 a) Result 2 CSU 2 (is) Qual Units Test Method Dato/Timea Technician N/A LCSD Ni-63 210.12 48.8 219.354 50.926 pCI/L ARS-022 8/29/08 1:05 82S . 0.09 DER Duplicate Evaluation AIyis Btch N/A QC Type LCSD I Analysis Description i-53 I/___
Ni-63 Re sul t 210.12 210.12 1 CSU1 (1 a) 48 "
481i Result 2Analysis 219.354.
1 219354 1___
50.92I
_ Qual Units p*i/L 1______________
_+ Analysis Test Method
" -ARS-022I t092 Analysis Date/Time 8/29/0.81:05, Analysis Technician BIS DER 0.268<
DER A."ptanceR Projbct Manager R Notes: American Radiation Services, Inc. assumes no liability for the use or interpretation of any analytical results pro0lOed other than the cost of the analysis itself. Reprouctlion of this report in less than full retuires the written consent of the client.
LELAP Certificate# 30658 NELAP Certificate # E87558
2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 SERVICES, INC.
QC Results Report Sample Delivery Group: ARSI-08-01560 Date Received: 8/12/2008 Laboratory Control Sample Evaluation BItch nae T
P Anlyse lysie CSU {1() ~1 .1MDC 1 Epected ua ] Report ] Analysis ILCS Analysis Analysis Percent np t Results Vauje Units Test Method DatetTirne Technician Recovery ( Acnept"nse R)
ARSI-B08-02293 LCS H3 1136.06 161:4 158.48416 1270.45 pCI/L ARS-054/EPA 906.0 9/4/08 18:01 B1S 89 75%-125%
Blank Evaluation Analysis A~l~i Qc C Anallyte Analysis cSU 1 (1 a8l MDC Expected Vled 1* ,R1 Report epr 1 Analysis Analysis Analysis
-Batch Type Results Vae Units Test Method .Dote/Time Technician ARS1-B08-02293 MBL H3 67.923 94.439817 158.41962 NA U pCi/L ARS-054/EPA 906.0 9/5/08 2:16 BIS RER Duplicate Evaluation Analysis ji1 QC Aatch sDecription Type Reslt I csUI (1 e) Result 2 CSU 2 (15) Qual ee Units Test lMethod 1 Analysis I RER Date/Time Technician RER AcceptenceR 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 1. B2S 0.02 < 1 DER Duplicate Evaluation r Analysis n
Batch 1.. Qc Type Anlyis Description Result 2 TF I
CSU 1(I ) ...It2 s iU (Is)
T Quai Analysis Units Analysis Test Method f]DER.Analysis Dote/Time Analysis Techniden D ER .e ARSI-808-02293 LCSD H3 1136.06 161.4 1143.2572 161.9636 pCi/L ARS-054/EPA 906.0 9/4/08 22:09 BJS D 0.06 Matrix Spike
' Analys Anlyta Analysie CSU 1 () Unpik e Con. Qoel Report Analysis Analyst.is Percent Ace Bitch Type Results Activity. Units Test Method Dte/itirns I Technician Recory(%) Reange ARS1-BO8-02293 MS H3 13755.623 1429.035 1862.953 13970.11 pCi/L ARS-054/EPA 906.0 9/5/08 6:24 B)s 8S 60%-140D%
Proji t Manager Re( -
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
2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 E1tICAN RADIATION QC Results Re ort Sample Delivery Group: ARSI-08-01560 Date Received: 08/12/08 Laboratory Control Sample Evaluation Anelyie "QC Anelyte Analysis CSU 1 (1.) MDC Expected Report Ansly.is Analysis Analyssl PerAent Betch Type Results Value Unit. Test Method Dete/Tinme Technician Recovery ( Ae ARS1-B08-02219 ICS Sr-90 21.729 1.699 0.531 21.34 pCi/L ARS-32/EPA 905.0 8/26/08 13:46 B3S 102 75%-125%
Blank Evaluation Analysis Qc Anlyte Analysis CSU 1(1) MDC Expiected Qual Report Analysis Analysis Analysls Batch Type Results * . Val.e. j l Units Test Method Date/Time Technician ARS1-B08-02219 MBL Sr-90 -0.200 0.202 0.729 NA U pCi/L ARS-032/FPA 905.0 8/26/08 13:46 B3S_
RER Duplicate Evaluation Analysit QC Analy1i1 Anely Analysis Analysis Analysis c REp Type Description Re"euit I CSU I ( a)R uRlt2 CSU 2 (1e) Qual Unityis Unt sest Med TAaet 4thod Dete/Tn Dt./Time TAnaysis Technician R* Acpac Betu.
ARS3- 08-02219 LCSD Sr-90 21.729 1.699 23.673 1.862 pCi/L ARS-032/EPA 905.0 8/26/08 13:46 835 0.55 DER Duplicate Evaluation "
Analysis TCAnlyi Aalssynlyis DR c DER Aneyh T T D t eeslt 1 CSU I(* Reult CSU 2 (.) Quel Anelydie Aneiyle Afteysis Anelesic ype unit et Method Date/Tim.e ,Technicen c .
A 2..Aan 9 APSI-B08-02219 LCSD Sr-90 21.729 _1 1.699 123.673 1.862 1 pCi/L IARS-O32/EPA 905.0 8/26/08 13:46 8.1S 1.54 < 3 Pro Ct Marnager Rý!
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
A-iRS INTERNATIONAL 2609 North River Road, Port Allen, Louisiana 70767 1 (800) 401-4277 FAX (225) 381-2996 QC Results Report Sample Delivery Group: ARSI-08-01560
-. Date Received: 08/12/08 Laboratory Control Sample Evaluation I Analysis QC Anslyt. Analysis CSU 1 (1 6) MDC Expected Report Analysis Analysis Analysis Percent LCS Acceptance Iertch Typul te ts value Units Test Metod Date Technitin Recovery (R*e Rwge ARS1-508-02203 LCS CO-60 25281.00 495.35 210.80 25315.22 pCi/g EPA 901.1 08/19/08 ILA 100 75%-125%
ARS1-B08-02203 LCS CS-137 15370.00 345.75 130.00 15285.98 pCi/g EPA 901.1 08/19/08 ILA 101 75%-125%
ARS1-B08-02203 LCS i "AM-241 34109.00 j1251.70 288.40 34794.33 pCi/g EPA 901.1 08/19/08 J3LA 98 75%-125%
Blank Evaluation Analysis QC t Analysis U1(18) MDC Expected Report Analysis Anlysisl Analysis Batch Type Results Value Qual Units Test method Date Technician ARS1-B08-02203 MEL CO-60 0.001 0.001 0.004 NA U pCi/g EPA 901.1 08/19/08 ILA ARS1-B08-02203 MBL CS-137 0.001 0.001 0.004 NA U PCi/g EPA 901.1 08/19/08 ILA ARSI-B08-02203 MBL AM-241 0.000 0.003 0.007 NA UL pCi/g EPA 901.1 08/19/08 JLA RER Duplicate Evaluation Analyste QC Analysis A A aetch Type Deeription Result 1 CSU 1 (18) Result 2 CSU 2 (18) Quel Anelysis Anily Anelysis Anelys RER RER I I Units Test Method . Date Technician Accepteneeeenge AFLSI-B08-02203 LC5D CO-60 25281.00 495.35 24786.00 496.33 pCV/9 EPA 901.1 08/19/08 ILA 0.50 ARS1-B08-02203 LCSD CS-137 15370.00 345.75 14809.00 374.51 pCi/g EPA 901.1 08/19/08 3LA 0.78 <I ARS1-008-02203 LCSD AM-241 34109.00 1251.70 34780.00 1262.00 pCr/g EPA 901.1 08/19/08 JLA 0.27 < 1 DER Duplicate Evaluation Analysis QC Analysis t Analysis Analysis Analyist Batch Type Description Result 1 CSU 1 (1.) Reslt 2 CSU 2 (1L) Qual Units Test method Date Technician DER Aceeptencekange ARS1-B08-02203 LCSD CO-60 25281.00 495.35 24786.00 496.33 pCi/Q EPA 901.1 08/19/08 ILA 1.41 <3 ARS1-808-02203 LCSD CS-137 15370.00 345.75 14809.00 374.51 pCi/g , EPA 901.1 06/19/08 ILA 2.20 <3 ARS1-B08-02203 LdSD AM-241 34109.00 .1251.70 34780.00 1262.00 pCI/s EPA 901.1 08/19/08 3LA 0.76 < 3 Quu-ility ASsuranCe " . .
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 writtet consent of the client.
LELAP Certificate# 30658 NELAP Certificate # E87558
2609 North River Road
- Port Allen, Louisiana 70767 A ION 11(800) 401-4277 FAX (225) 381-2996 0*APM5Rt Notes:
Comments:
1.0) Soil and.Sludge analysis are reported on a wet basis or an as received basis unlessiotherwise indicated.
2.0) The data in this report are within the limits of uncertainty specified in the 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 nudides. 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", 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 r 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) DetectionLimit 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
