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Category:Graphics incl Charts and Tables
MONTHYEARML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16112A1722016-04-25025 April 2016 Indian Point Nuclear Generating Unit Nos. 2 And 3 Interim Staff Response To Reevaluated Flood Hazards Submitted In Response To 10 CFR 50.54 (f) Information Request Flood-Causing Mechanism Reevaluation (CAC NOS. MF3313 and MF3314) NL-16-035, Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-04-0505 April 2016 Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015 Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application ML11221A3052011-08-0909 August 2011 Lr Hearing - NIA-078 NL-11-013, Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions2011-02-10010 February 2011 Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions ML0936409322009-12-30030 December 2009 Table I, Structural Heat Sinks, Table II, Containment Heat Sink Thermodynamic Data NL-09-151, Telephone Conference Call Regarding Met Tower Data for SAMA Analysis2009-11-16016 November 2009 Telephone Conference Call Regarding Met Tower Data for SAMA Analysis NL-09-018, Reply to Request for Additional Information - Miscellaneous Items2009-01-27027 January 2009 Reply to Request for Additional Information - Miscellaneous Items ML11221A3032008-12-22022 December 2008 Lr Hearing - NIA-077 NL-08-144, Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3)2008-10-23023 October 2008 Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3) ML0905604702008-08-31031 August 2008 Long-Term Monitoring Plan Position Paper ML11221A1262008-08-14014 August 2008 Lr Hearing - NIA-076, Table 1, Projections of the Population and Components of Change for Us: 2010 to 2050 ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0904006772008-07-0101 July 2008 Unit 3 SBO Event: Time Line to Energize Unit 3 Bus from App R Diesel Via Gt/Bt ML0904006972008-07-0101 July 2008 SBO Event: Time Line to Energize a 480V Bus from GT-25/26 and App R Diesel ML0904100382008-07-0101 July 2008 SBO Event: Time Line to Energize 480V Bus 6A from GT-25/26 and App R Diesel (Total Time: 47 Minutes) ML0904100962008-07-0101 July 2008 ECN 7385; Attachment 7.46 - Post MOD Test Plan ML0904104002008-06-17017 June 2008 Vendor Data for 24-Hr. Run; Entergy, Buchanan, Ny ML0814804812008-05-27027 May 2008 NRC Graphics - Indian Point ML0905101052008-05-0505 May 2008 Trend Report for Nuclides: Co-60, Cs-137, H-3, Ni-63, Sr-90 ML0905101062008-05-0505 May 2008 M10 Investigation Wells NL-08-074, Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074)2008-04-30030 April 2008 Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074) ML0905401352008-01-10010 January 2008 Ground Water Monitoring Well Information Table ML0905102022008-01-0808 January 2008 Groundwater Investigation - Summary NYS Results as of 01/08/2008 ML0736200892007-12-20020 December 2007 Report for Analysis or Eight Water Samples from Set 6 from the Indian Point Power Station, Buchanan, New York Dated December 20, 2007 ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0731801672007-10-18018 October 2007 Report for Analysis of Seven Water Samples from Set Five from the Indian Point Power Station, Buchanan, New York, Dtd October 18, 2007 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0729502532007-10-10010 October 2007 Siren Schedule 11 X 17 Dtd 10/10/07 ML0728403122007-07-31031 July 2007 Report for Analysis for Samples from Set Twenty-Four from the Indian Point Power Station, Buchanan, New York. Dtd. July 31, 2007 ML0728402552007-05-0303 May 2007 Interim Report for Completed Analysis for Samples from Set Twenty-One from the Indian Point Power Station, Buchanan, New York. Dtd. May 3, 2007 ML0713102862007-03-20020 March 2007 E-Mail from D. Winslow of GZA to M. Barvenik of GZA, J. Noggle of USNRC and J. Adler of Entergy, Regarding GZA Results ML0713100562007-02-15015 February 2007 E-Mail from T. Rice of NYSDEC to Various, Regarding Latest State Results ML0713100452007-02-12012 February 2007 E-Mail from P. Donahue of Entergy to T. Rice of NYSDEC, Regarding Split Sample Data ML0713005932007-01-24024 January 2007 E-Mail from D. Gray of Entergy to J. Noggle of USNRC, Regarding Historical Sr Data 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) ML0701105612006-12-15015 December 2006 Interim Report for Completed Analyses for Samples from Sets Fifteen and Sixteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0704003112006-12-0404 December 2006 E-Mail from T. Rice of Department of Environmental Conservation to J. Adler of Entergy, and J. Noggle and J. White of USNRC, Regarding Latest State Data ML0704002992006-11-28028 November 2006 E-Mail from T. Rice of Department of Environmental Conservation to Various, Regarding Latest State Results ML0701105482006-11-17017 November 2006 Interim Report for Requested Analyses for Samples from Sets Eleven Through Fourteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0628302122006-06-15015 June 2006 E-mail from R. Lavera of Entergy to J. Noggle of NRC, Regarding Sample Log ML0618605182006-04-26026 April 2006 E-mail from R. Sachatello of Entergy to M. Barvenik and D. Sinslow of GZA, Regarding Pressure Test Discussion with GZA ML0620001512006-04-13013 April 2006 E-mail from K. Mcmullian, Entergy, to J. Boska, NRR, Et Al., IPEC Status Report April 13 ML0610006912006-03-27027 March 2006 Units 1 & 2 Tritium History (GL-80-10), in Nci/Ml 2024-06-04
[Table view] 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
MONTHYEARIR 07200051/20244022024-11-20020 November 2024 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200051/2024402 (Public) ML24240A1692024-09-18018 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) IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 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 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 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 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 2024-09-18
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Text
IB O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION March 1, 2006 Mr. Jim Kottan U S . Nuclear Regulatory Commission Regon I 475 Allendale Road IOng of Prussia, PA 19406
SUBJECT:
SECOND INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET FIFTEEN, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set 15, consisting of 15 water samples, associated with the Indian Point Power Station on November 21 and November 22,2006. Sample analysis was initiated based on your previous direction for handling samples from t h s licensee. Sample identification and collection data for the samples addressed in t h s report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 8, respectively. The pertinent procedure references are provided in each specific table.
ORISE's Quality Control (QC) requirements were met for these analyses. The Q C files are available for your review upon request. Additional reports will follow after the completion of the requested analyses.
ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of t h s radionuclide. ORISE is discontinuing the reporting of Ni-59 data until t h s problem can be resolved.
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:WPI:ar Enclosures C: T. Carter, NMSS/DWMEP 7518 E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN 8A23 S. I G k , ORISE M. Roberts, NRC Regon I J. Whte, NRC Regon I File 1697 Distribution approval and concurrence :
Technical Management 'I'cam Membcr Init&. -
Quality Manager
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 1697W0078" MW-41-42-(007) 11/13/2006 12:55 1697M0041 1697W0078 filter 11/13/2006 12:55 1697W0079 MW-41-64-(006) 11/13/2006 13:10 1697M0042 1697W0079 filter 11/13/2006 13:10 1697W0080 MW-45-43-(007) 11/13/2006 13:20 1697M0043 1697W0080 filter 11/13/2006 13:20 1697W0081 MW-45-62-(007) 11/13/2006 11:20 1697M0044 1697W0081 filter 11/13/2006 11:20 11 1697W0082 I MW-53-80-(002) I 11/9/2006 I 11:15 11 1697M0045 1697W0082 filter 11/9/2006 11:15 1697W0083 MW-53-120-(002) 11/9/2006 11:20 1697M0046 1697W0083 filter 11/9/2006 11:20 1697W0084 MW-55-24-(001) 11/9/2006 13:20 1697M0047 1697W0084 filter 11/9/2006 13:20 1697W0085 MW-55-35-(001) 11/9/2006 13:40 1697M0048 1697W0085 filter 11/9/2006 13:40 1697W0086 MW-55-54-(001) 11/9/2006 13:30 1697M0049 1697W0086 filter 11/9/2006 13:30 1697W0087 MW-56-85-(002) 11/9/2006 10:20 1697M0050 1697W0087 filter 11/9/2006 10:20 1697W0088 MW-50-67-(008) 11/15/2006 10:37 1697M0051 1697W0088 filter 11/15/2006 10:37 1697W0089 MW-50-42-(008) 11/15/2006 10:47 1697M0052 1697W0089 filter 11/15/2006 10:47 1697W0090 MW-49-26-(008) 11/15/2006 11:28 1697M0053 1697W0090 filter 11/15/2006 11:28 1697W0091 MW-49-42-(008) 11/15/2006 14:21 1697M0054 1697W0091 filter 11/15/2006 14:21 1 1697W0092 1697M0055 MW-49-65-(008) 1697W0092 filter
~ ~~~
11/15/2006 11/15 /2006 13:46 "The W in the OliISE sample identification represents a water matrix.
'The M in the OliISE sample identification represents the filtcred fraction of the preceding water sample Indian Point Power Station projccts/l697/Data Tables/2007-03-01 2nd Interim Data Tables 1697 Sets 15
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radic Sample ID Sample ID CO-58 CO-60 CS-134 cs-137
-1.7 & 2.1' 1.1 k 2.1 0.5 & 2.1 -1.2 k 3.5 1.3 k 2.2 2.8 k 2.3 0.6 k 2.3 0.9 k 2.1 1.2 k 1.6 -0.1 & 1.6 -0.6 & 1.8 0.5 k 1.5 1 1697W0081 I MW-45-62-(007) 0.2 k 2.3 1.9 & 2.2 -0.2 k 2.2 1.9 f 3.5 1 1697W0082 I MW-53-80-(002) -0.7 & 2.3 0.3 k 2.1 -0.5 & 2.3 0.3 & 2.1 1697W0083 MW-53-120-(002) -0.1 I k 2.0 2.8 k 1.7 1.1 k 2.3 0.3 &
~~ ~
I 1.9 1697W0084 MW-55-24-(001) -1.2 f 2.1 0.7 k 2.1 0.3 & 2.2 1.3 k 4.2 1697W0085 MW-55-35-(001) -0.7 & 2.4 -0.1 & 2.4 -0.2 f 2.7 1.6 k 2.2 1697W0086 MW-55-54-(001) -2.1 k 3.0 0.4 & 1.8 2.8 k 2.1 1.2 k 1.7 1 I
+
1697W0087 MW-56-85-(002) -0.4 k 2.3 3.6 & 3.1 -0.3 & 2.2 0.4 & 5.1 1 1697W0088 I MW-50-67-(008) 0.4 & 2.2 0.1 k 2.2 2.5 k 2.4 -0.1 ? 2.1 1 1697W0089 I MW-50-42-(008) -0.8 k 1.6 1.7 k 1.7 -0.2 & 1.9 -1.5 & 1.6 1697W0090 MW-49-26-(008) I
-0.8 & 2.0 2.4 & 2.5 2.3 ? 2.2 -1.5 k 3.5 I 1697W0091 MW-49-42-(008) -2.9 k 2.2 1.9 f 2.41 1.0 & 2.3 I 1.8 & 2.1 I
~~
1697W0092 MW-49-65-(008) 1.4 k 1.7 0.6 k 1.91 1.3 k 1.7 0.4 f 1.5 "I'hc range of MDCs for the selected radonuchdes is 2.6 pCi/L to 5.0 pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Powcr Station projects/l697/lha Tables/2007-03-01 2nd Interim Data Tables 1697 Sets 15
TABLE 3 CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK I I
~ ~~
Radionuclide Concentrationsa(pCi/L)
ORISE NRCRegionI I I Sample ID I I
sample^^ I I
Fe-55b I I
Ni-63" I I
H-3d 1697W0078 I MW-41-42-(007) I 15 t- 18'. 31 I 2.4 k 5.8, 9.8 I 600 t 240, 370 1697W0079 MW-41-64-(006) 16 t- 1 8 , 31 2.9 2 5.8, 9.8 300 2 220, 370 1697W0080 MW-45-43-(007) 16 k 1 8 , 31 4.7 k 5.8 , 9.8 710 t- 250, 370 1697W0081 MW-45-62-(007) -1 t 1 8 , 31 5.0 k 5.8, 9.8 1,140 t 270, 370 1697W0082 MW-53-80-(002) 19 k 1 9 , 31 5.6 k 5.8 , 9.8 570 t- 240 , 370 1697W0083 MW-53-120-(002) 22 & 1 9 , 31 27.7 k 6.5, 9.8 8,210 2 570, 370 1697W0084 MW-55-24-(001) 13 k 1 8 . 31 3.1 ? 5.8, 9.8 1,890 t- 310, 370 1697W0085 MW-55-35-(001) -5 k 18 , 32 3.8 ? 5.8 , 9.8 9,450 k 620, 370 1697W0086 MW-55-54-(001) 4 k 19 , 32 9.6 k 5.4, 8.8 12,840 t 750, 370 1697W0087 MW-56-85-(002) -4 k 1 8 . 32 1.2 t- 5.2, 8.8 210 t 220, 370 1697W0088 MW-50-67-(008) 9 t- 1 9 , 32 7.9 t- 5.3, 8.8 5,620 k 470 , 370 1697W0089 MW-50-42-(008) 7 t- 19 , 32 4.4 k 5.2, 8.8 2,740 t- 350, 370 1697W0090 MW-49-26-(008) -11 k 1 8 , 32 7.9 t 5 . 3 , 8.8 9,070 ? 610, 370 1697W0091 MW-49-42-(008) 2 t 1 9 , 32 4.7 t- 5.2, 8.8 6,300 k 500, 370 1697W0092 MW-49-65-(008) -6 t 1 8 , 32 9.6 k 5.4, 8.8 3,590 t- 390, 370
'I'hc MDCs for each radionuclide are after thc comma.
"Fe-55 analyzed using proccdurc 1'11'13, lievision 4.
'Ni-63 analyzed using procedure AP17, Revision 0.
dl 1-3 analyzed using proccdurc AP2, Revision 15.
eUnccrtainties represent the 95% confidence lcrcl, based on total propagated unccrtandes.
Indian Point Power Station projccts/1697/Data Tables/2007-03-01 2nd Intcrtm Data 'I'ablcs 1697 Scts 15
TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Tc-99 ORISE NRC Region I Concentrationsa Sample ID Sample ID (pCi/L) 1 I
-1.6 !r 8.1" 14.0
~~
-3.0~
k 8.1 . 14.0 1697W0080 MW-45-43-(007) 0.7 rL 8.1 , 14.0 11 1697W0081 I MW-45-62-(007) 4.0 2 8.2, 14.0 11 1697W0082 I MW-53-80-(002) 0.3 !r 8.1 , 14.0 11 1697W0083 I MW-53-120-(002) -0.6 & 8.1 . 14.0 11 1697W0084
~~
I MW-55-24-(001) -3.3 IfI 8.0, 14.0 111- 1697W0085 1697W0086 1697W0087 I MW-55-35-(001)
MW-55-544001)
MW-56-85-(002) I
-2.7
-4.5 1.1 k
-t k
8.1 , 14.0 8.0 14.0
~
8.2, 14.0 111 1697W0088 1697W0089 1697W0090 I MW-50-67-(008)
MW-50-42-(008)
MW-49-26-(008)
~
-5.7
-3.4 !c
-2.7 k
k 8.0, 14.0 8.0, 14.0 8.1 , 14.0 I 1697W0091 1697W0092
~~
"The PVflXs are after the comma.
MW-49-42-(008)
MW-49-65-(008)
-3.8 !c
-5.7 &
8.0 14.0 8.0 14.0 "Uncertainties represent the 95% confidence level, bascd on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-03-01 2nd Interim Data Tables 1697 Sets 15
TABLE 5 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC RegionI Concentrations, T P U ~ ,
Sample ID Sample ID and MDCS"(pCi/L)
I 1697W0078 MW-41-42-(007) 3.45 k 0.48b , 0.57 1697W0079 1697W0080 1697W0081 1697W0082 1697W0083
~
MW-41-64-(006)
-5143-(007)
MW-45-62-(007)
MW-53-80-(002)
MW-53-120-(002)
I 2.12 0.02 0.21
-0.18 34.3 k 0.72 k 0.34 0.43 k 0.34 , 0.61
? 1.5
~ 0.).
0.58 1.26 1697W0084 MW-55-24-(001) 18.8 k 1.0 1697W0085 1- MW-55-35-(001) I 43.6 k 1.8 , 0.7 1697W0086 I MW-55-54-(001) I 34.8 ? 1.8 ~ 1.0 1697W0087 MW-56-85-(002) -0.02 k 0.60 , 1.05 1697W0088 MW-50-67-(008) 27.1 k 1.3 , 0.7 1697W0089 I MW-50-42-(008) I 12.46 k 0.83 , 0.62 1697W0090 MW-49-26-(008) 15.27 k 0.92 , 0.63 1697W0091 MW-49-42-(008) 23.6 k 1.3 , 0.7 1697W0092 MW-49-65-(008) 19.6
'MMDCs are after the comma.
'Uncertainties represcnt thc 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station prolects/l697/Data 'l'ables/2007-03-01 2nd Interim Data Tables 1697 Sets 15
TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa @Ci/g ( sediment in 100 mL r K i / L for water)
Sample ID Sample I D Am-241 Cm-242 Cm-243/244 N~-237 1697W0078 0.04 t 0.13 . 0.25 0.00' t- 0.11 . 0.24 0.00 -t 0.05 , 0.14 1697M0041 0.01 f 0.01 , 0.02 0.01 k 0.02 , 0.03 0.00 t 0.01 , 0.02 1697W0079 m-41-64-(006) 0.04 k 0.19 , 0.35 0.00 k 0.10 . 0.22 0.02 t 0.07 . 0.15 0.02 & 0.04 . 0.06 1697M0042 1697W0079 filter 0.00 f 0.02 , 0.03 0.00 f 0.01 , 0.02 0.00 k 0.01 , 0.03 0.00 t- 0.01 , 0.02
~
1697W0080 0.06 f 0.10 . 0.18 -0.07 k 0.09 . 0.25 0.02 t 0.04 . 0.06 1697M0043 0.01 2 0.01 , 0.02 0.00 f 0.01 , 0.03 0.00 k 0.02 0.03 1697W0081 0.00 t- 0.06 , 0.16 0.04 2 0.13 . 0.25 0.05 t 0.09 . 0.16 1697M0044 0.00 t 0.01 , 0.02 0.01 t- 0.01 , 0.01 0.01 t 0.01 , 0.02
~
1697KVoo82 m-53-80-(002) 0.17 k 0.20 , 0.33 0.11 k 0.13 , 0.20 -0.04 2 0.12 , 0.28 0.00 & 0.05 ~ 0.14 1697M0045 1697VK@32 filter 0.02 f 0.02 . 0.04 0.00 k 0.01 . 0.02 I 0.00 t- 0.01 . 0.02 -0.002 k 0.004d , 0.015
~~
1697W0083
~
1 Mw-53-120-(002) 0.11 t- 0.16 , 0.27 0.05 k 0.12 , 0.22 0.04 f 0.05 , 0.05 -0.06 t 0.11 , 0.27 1697M0046 1697W0083 filter 0.01 t 0.01 , 0.01 0.01 t- 0.01 , 0.01 0.00 f'0.01 , 0.02 0.01 t- 0.01 . 0.01 1697W0084 W-55-24-(001) 0.06 k 0.10 , 0.18 0.00 f 0.04 , 0.10 0.01 t- 0.10 , 0.19 0.10 t 0.09 , 0.06 1697M0047- I 1697W0084 filter 0.00 k 0.01 , 0.03 -0.02 k 0.02 , 0.04 0.00 t 0.01 , 0.02 0.01 t- 0.01 . 0.02 16c)7WO085 M\sii-55-35-(00 1) -0.03 t- 0.13 , 0.24 0.03 5 0.06 , 0.11 0.06 k 0.12 , 0.20 0.02 F 0.08 , 0.16
~~
1697M0048 1697W0085 filter 0.00 k 0.01 , 0.02 0.00 f 0.01 , 0.02 0.00 t- 0.01 , 0.02 -0.03 k 0.02 . 0.05
F g
3 TABLE 6 (Continued)
I 0
4 n
I 0
4 w CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED F
P ALPHA EMITTING RADIONUCLIDES 3 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I :oncentrationsa (pCi/g. a ?sedimentin 100 mL or pCi/L for water) I Sample ID Sample ID Pn-2338 P~-239/240 U-234 U-238 1697W0078 MW-41-42-(007) I -0.18 k 0.20 0.44 0.02 f. 0.08 . 0.17 0.78 f 0.25 . 0.14 0.69 k 0.23 . 0.14 1697M0041 1697W0078 filter I 0.00 f. 0.02 . 0.04 0.01 k 0.01 , 0.01 0.00 k 0.01 , 0.01 -0.01 f 0.01 , 0.03 1697WOO79 MW-41-64-(006) 0.02 k 0.23 , 0.43 -0.02 f 0.09 , 0.21 1.20 k 0.32 , 0.18 0.94 t 0.28 , 0.06 1697M0042 1697W0079 filter 0.01 f 0.02 . 0.02 0.00 f 0.01 . 0.02 0.01 f 0.01 . 0.01 0.01 f. 0.01 . 0.02 1697W0080 MW-45-434007) I 0.14 f 0.11 , 0.06 0.02 k 0.04 , 0.06 0.58 f 0.22 , 0.17 0.26 f 0.14 , 0.06 1697M0043 1697W0080 filter 0.01 k 0.02 , 0.03 0.01 f 0.01 , 0.01 0.09 k 0.03 , 0.01 0.11 f 0.03 , 0.01 1697W0081 MW-45-62-(007) 0.10 f 0.19 . 0.34 0.09 f 0.09 . 0.13 1.93 f 0.42 . 0.29 1.23 k 0.34 . 0.27 1697W0081 filter I -0.01 f. 0.02 . 0.04 .
~~~
1697M0044 0.01 k 0.01 0.02 0.00 k 0.01 , 0.01 0.01 f 0.01 , 0.02 1697W0082 MW-53-80-(002) 0.09 t 0.20 , 0.36 0.05 f 0.08 , 0.14 1.38 f 0.34 , 0.18 1.13 k 0.31 , 0.20 1697M0045 1697W0082 filter 0.00 f 0.01 . 0.02 0.01 k 0.01 . 0.01 0.06 L 0.02 . 0.01 0.07 f 0.02 . 0.01 1697W0083 MW-53-120-(002) I 0.19 k 0.19 . 0.30 0.07 f 0.08 . 0.06 6.86 k 0.87 , 0.14 I 4.28 k 0.64 , 0.14 11 1697M0046 0.00 k 0.01 , 0.02 0.13 & 0.04 , 0.03 0.12 f 0.03 , 0.02 1697W0084 0.08 f 0.09 - 0.15 0.75 f 0.24 . 0.06 0.71 k 0.24 . 0.06 1697M0047 0.01 f 0.01 . 0.02 0.09 k 0.03 . 0.01 I 0.15 k 0.04 . 0.01 11 1697W0085 MW-55-354001) I .
0.12 k 0.19 0.33 0.02 f. 0.06 , 0.13 0.80 k 0.26 , 0.18 0.74 t 0.24 , 0.06 1697M0048 1697W0085 filter I 0.00 t 0.01 , 0.02 0.00 t 0.01 , 0.01 0.04 E! 0.02 . 0.02 0.04 f 0.02 . 0.02
'i:
I TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN P O I N T POWER STATION BUCHANAN, N E W YORK ORISE NRC Region I Radionuclide :oncentrationsa (pCi/e of sediment in 100 m L or pCi/L for water)
Sample I D Pu-238 P~-239/240 u-234 U-238 1697W0086 MW-55-54-(001) 0.25 k 0.26 . 0.42 0.02 f 0.04 , 0.06 1.79 f 0.38 , 0.13 1.26 ? 0.32 , 0.16 11 1697M0049 1697W0086 filter 0.01 f 0.01 , 0.03 0.01 k 0.01 . 0.01 0.06 k 0.02 . 0.01 0.07 k 0.03 . 0.03 1697W0087 MW-56-85-(002) 0.00 t 0.06 , 0.16 0.08 k 0.08 , 0.06 1.34 k 0.36 , 0.29 1.29 k 0.35 , 0.25 1697M0050 1697W0087 filter 0.00 k 0.02 . 0.04 0.01 f 0.01 . 0.01 0.01 f 0.01 . 0.01 0.00 f 0.01 . 0.02 1697W0088 MW-50-67-(008) 0.03 t 0.18 , 0.33 0.07 f 0.07 . 0.05 I 0.56 f 0.22 . 0.15 I 0.58 k 0.23 . 0.15 . 1697M0051 1697W0088 filter 0.01 f 0.01 , 0.02 0.00 ? 0.01 , 0.02 0.03 k 0.01 , 0.01 0.04 k 0.02 , 0.01
\
1697W0089 MW-50-42-(008) 0.02 k 0.25 . 0.46 0.00 f 0.08 , 0.19 0.70 f 0.23 , 0.06 0.66 ? 0.23 , 0.06 L
h 0 1697M0052 1697W0089 filter 0.00 .
f 0.02 0.03 0.01 t 0.01 . 0.01 0.02 t 0.01 . 0.01 0.02 k 0.01 . 0.02 I
\-4 c
1697W0090 MW-49-26-(008) 0.15 I t 0.24 , 0.41 0.09 f 0.11 , 0.18 1.36 k 0.33 , 0.06 0.71 k 0.24 , 0.14 c: 1697M0053 1697W0090 filter 0.01 f 0.02 . 0.04 0.01 f 0.01 - 0.02 I 0.01 ? 0.01 - 0.02 I 0.00 f 0.01 . 0.02 5
51 1697W0091 MW-49-42-(008) 0.06 t 0.21 , 0.38 0.12 f 0.11 . 0.15 I 1.89 f 0.45 . 0.34 1 0.83 t 0.28 . 0.19 1697M0054 1697WOO91 filter 0.01 f 0.01 , 0.02 0.002 k 0.004 , 0.006 0.00 f 0.01 , 0.03 0.01 f 0.01 , 0.02
'Y 0.
1697W0092 1697M0055 MW-49-65-(008) 1697W0092 filter
-0.11 0.00 k 0.21 . 0.43 0.11 f 0.12 , 0.17 1.36 k 0.41 , 0.44 0.83 f 0.01 , 0.02 0.01 ? 0.01 . 0.02 0.00 f 0.01 . 0.01 0.002 k 0.27 , 0.18
& 0.004 . 0.006 "The MDCs are after the con ma.
5
" b Uncertainties represent the ' 5% confidence level, based o n id propagated uncertainties 3
E
'Zero values are due to rounding.
5 dSignificantfigures expanded to avoid reporting a TPU of zero at the request of the inspector.
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations ORISE NRC Region I (pCi/g of sediment in 100 ml Sample ID Sample ID or pCi/L for water)
II ~ ~~
1697M0041 I 1697W0078 filter I -0.9 & 3.6 , 6.2 1697W0079 MW-41-64-(006) -15 rf: 34 , 59 1697M0042 1697W0079 filter -1.0 k 3.5 , 6.0 1697W0080 MW-45-43-(007) 6 k 34 , 58 1697M0043 1697W0080 filter -4.6 ? 3.7 . 6.3 1697W0081 MW-45-62-(007) 7 k 36 , 62 1697M0044 1697W0081 filter 0.1 5 3.6 , 6.2 1697W0082 MW-53-80-(002) -2 1 k 32 , 56 1697M0045 1697W0082 filter -1.2 k 3.6 . 6.2 1697W0083 MW-53-120-(002) -1 k 33 , 56 1697M0046 1697W0083 filter -0.3 rf: 3.5 , 6.0 1697W0084 MW-55-24-(001) 2 k 35 , 60 1697M0047 1697W0084 fdter 0.9 t 3.8 , 6.5 1697W0085 MW-55-35-(001) 39 rf: 30 , 49 1697M0048 1697W0085 filter -4.4 rf: 3.7 , 6.3 1697W0086 MW-55-54-(001) 25 k 30 , 50 1697M0049 1697W0086 filter 1.4 k 3.1 , 5.3 1697W0087 MW-56-85-(002) 34 k 30 , 50 1697M0050 1697W0087 filter 1.1 rf: 3.7 , 6.4 1697W0088 MW-50-67-(008) 28 k 31 , 51 1697M0051 1697W0088 filter 3.0 k 3.6 , 5.9 Indian Point Power Stauon prqects/lG97/Data Tables/2007-03-01 2nd Intcrim Data Tablcs 1697 Sets 15
TABLE 7 (Continued)
CONCENTRATIONS OF PLUTONIUM-241 ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Radionuclide Concentrationsa NRC Region I Sample ID (pCi/g of sediment in 100 mL Sample ID or pCi/L for water) 1697W0089 MW-50-42-(008) 27 k 31 , 52 1697W0052 1697W0089 filter 0.6 k 3.5 , 5.9 1697W0090 MW-49-26-(008) 14 k 28 , 47 1697M0053 1697W0090 filter 1.7 k 3.7 6.2 1697W0091 MW-49-42-(008) 16 k 30 , 51 1697M0054 1697WOO91 filter 2.8 k 3.9 6.4 1697W0092 MW-49-65-(008) 8 k 27 , 46 1697M0055 1697W0092 filter 0.7 k 3.3 , 5.6 Indian Point Power Station projccts/l697/Data Tables/2007-03-01 2nd Interim Data Tables 1697 Sets 15
TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1 I 1 11
~~
1697W0078 MW-41-42-(007) -11.1 k 9.3 b
. 16.2 1697W0079 MW-41-64-(006) -7.8 k 9.3 , 16.2 1 11 1697W0080 I MW-45-434007) 2.5 9.5 16.2
-2.5 If: 9.4 16.2
-4.9 9.4 16.2 0.5 If: 9.5 . 16.2 1
((9G84 -T MW-55-24-(001) -1.1 If: 9.5 16.2 1 1697W0085 1 MW-55-35-(001) 4.3 ? 9.6 16.2 7.2 k 9.6 16.2 1.3 k 9.5 . 16.2 11 1697W0089 I MW-50-42-(008)
-1.6 k 9.4 . 16.2 11 "MIICs arc in parentheses.
buncertainties rcpresent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tablcs/2007-03-01 2nd Interim Data 'I'ables 1697 Sets 15