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Category:Graphics incl Charts and Tables
MONTHYEARCNRO-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 ML0610006872006-03-27027 March 2006 Fsb Sample Log 2018-03-19
[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
MONTHYEARML24011A1982024-01-12012 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 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency 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 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage 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 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) 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 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 ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] |
See also: IR 05000247/2006007
Text
IB ORISE Distribution
approval and concurrence
- Technical
Management
'I'cam Membcr Quality Manager OAK RIDGE INSTITUTE
FOR SCIENCE AND EDUCATION
Init&. - March 1, 2006 Mr. Jim Kottan US. 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 THE 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 ths licensee. Sample identification and collection data for the samples addressed in
ths 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 QC 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 ths radionuclide.
ORISE is discontinuing
the reporting
of Ni-59 data until
ths 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 M. Roberts, NRC Regon I File 1697 S. IGk, ORISE J. Whte, NRC Regon I
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS
AND COLLECTION
DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection
Collection
Sample ID Date Time 1697W0078" 1697M0041
1697W0079
MW-41-42-(007)
11/13/2006
12:55 1697W0078 filter
11/13/2006
12:55 MW-41-64-(006)
11 /13/2006 13:10 1697M0042
1697W0080
1697M0043
1697W0081
1697M0044
11 1697W0082
I MW-53-80-(002)
I 11/9/2006
I 11:15 11 1697W0079 filter
11/13/2006
13:10 MW-45-43-(007)
11 /13/2006 13:20 1697W0080 filter 11 /13/2006
13:20 MW-45-62-(007)
11/13/2006
11:20 1697W0081
filter 11/13/2006
11:20 1697M0045
1697W0083
1697M0046
1697W0084
1697M0047 1697W0082 filter 1 1 /9/2006 11:15 MW-53-120-(002)
11 /9/2006 11:20 1697W0083 filter
11 /9/2006 11 :20 MW-55-24-(001) 1 1 /9/2006 13:20 1697W0084
filter 11 /9/2006 13:20 1697W0085
1697M0048
1697W0086
MW-55-35-(001)
11 /9/2006 13:40 1697W0085 filter
1 1 /9/2006 13:40 MW-55-54-(001)
11 /9/2006 13:30 1697M0049
1697W0087
1697M0050
1697W0088
1697M0051
1697W0089 ~ ~~~ "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 1697W0086 filter
11/9/2006
13:30 MW-56-85-(002)
11 /9/2006 10:20 1697W0087
filter 11 /9/2006 10:20 MW-50-67-(008)
11/15/2006
10:37 1697W0088 filter
1 1 /15/2006 10:37 MW-50-42-(008)
11 /15/2006 10:47 Indian Point
Power Station projccts/l697/Data Tables/2007-03-01 2nd Interim Data Tables 1697 Sets
15 1697M0052
1697W0090
1697M0053
1697W0091
1697M0054 1697W0089 filter
11/15/2006
10:47 MW-49-26-(008)
11 /15/2006 11:28 1697W0090 filter
11/15/2006
11:28 MW-49-42-(008)
1 1 /15/2006 14:21 1697W0091 filter
11/15/2006
14:21 1 13:46 1697W0092
MW-49-65-(008)
11/15/2006
1697M0055
1697W0092
filter 11 /15 /2006
CO-60 CS-134 cs-137 1.1 k 2.1 2.8 k 2.3 -0.1 & 1.6 1.9 & 2.2 0.3 k 2.1 0.5 & 2.1 -1.2 k 3.5 0.6 k 2.3 0.9 k 2.1 -0.6 & 1.8 0.5 k 1.5 -0.2 k 2.2 1.9 f 3.5 -0.5 & 2.3 0.3 & 2.1 1697W0083
1697W0084
1697W0085
1697W0086
MW-53-120-(002)
MW-55-24-(001)
MW-55-35-(001)
MW-55-54-(001) ~~ ~ 0.7 k 2.1 -0.1 & 2.4 0.4 & 1.8 3.6 & 3.1 0.1 k 2.2 1.7 k 1.7 0.3 & 2.2 1.3 k 4.2 -0.2 f 2.7 1.6 k 2.2 2.8 k 2.1 1.2 k 1.7 -0.3 & 2.2 0.4 & 5.1 2.5 k 2.4 -0.1 ? 2.1 -0.2 & 1.9 -1.5 & 1.6 TABLE 2 CONCENTRATIONS
OF SELECTED GAMMA EMITTING RADIONUCLIDES
IN WATER SAMPLES
BY GAMMA SPECTROSCOPY
CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radic ORISE NRC Region I Sample ID Sample ID CO-58 -1.7 & 2.1' 1.3 k 2.2 1.2 k 1.6 11 1697W0081
I MW-45-62-(007)
0.2 k 2.3 11 1697W0082
I MW-53-80-(002)
-0.7 & 2.3 -0.1 k 2.0 2.8 k 1.7 I 1.1 k 2.3 I 0.3 & 1.9 -1.2 f 2.1 -0.7 & 2.4 -2.1 k 3.0 -0.4 k 2.3 11 1697W0087
I MW-56-85-(002)
11 1697W0088
I MW-50-67-(008)
0.4 & 2.2 11 1697W0089
I MW-50-42-(008)
-0.8 k 1.6 1697W0090
MW-49-26-(008)
1697W0091
MW-49-42-(008)
+ 1697W0092
MW-49-65-(008)
-0.8 & 2.0 2.4 & 2.5 I 2.3 ? 2.2 I -1.5 k 3.5 -2.9 k 2.2 1.9 f 2.41 1.0 & 2.3 I 1.8 & 2.1 ~~ 0.6 k 1.91 1.3 k 1.7 I 0.4 f 1.5 1.4 k 1.7 "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.
projects/l697/lha
Tables/2007-03-01
2nd Interim Data Tables 1697 Sets
15 Indian Point Powcr Station
TABLE 3 1697W0079
1697W0080
1697W0081 CONCENTRATIONS OF HARD
TO DETECT BETA EMITTING
RADIONUCLIDES
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK MW-41-64-(006)
16 t- 18, 31 2.9 2 5.8, 9.8 300 2 220, 370 MW-45-43-(007)
16 k 18, 31 4.7 k 5.8 , 9.8 710 t- 250, 370 MW-45-62-(007)
-1 t 18, 31 5.0 k 5.8, 9.8 1,140 t 270, 370 ~ ~~ Radionuclide
Concentrationsa (pCi/L) ORISE I NRCRegionI
I I I 1697W0082
1697W0083
1697W0084
Sample ID I sample^^
I Fe-55b I MW-53-80-(002)
19 k 19, 31 5.6 k 5.8 , 9.8 570 t- 240 , 370 MW-53-120-(002)
22 & 19, 31 27.7 k 6.5, 9.8 8,210 2 570, 370 MW-55-24-(001)
13 k 18. 31 3.1 ? 5.8, 9.8 1,890 t- 310, 370 Ni-63" I 1697W0085
1697W0086
1697W0087
H-3d MW-55-35-(001)
-5 k 18 , 32 3.8 ? 5.8 , 9.8 9,450 k 620, 370 MW-55-54-(001)
4 k 19 , 32 9.6 k 5.4, 8.8 12,840 t 750, 370 MW-56-85-(002)
-4 k 18. 32 1.2 t- 5.2, 8.8 210 t 220, 370 I I I I 1697W0078
I MW-41-42-(007)
I 15 t- 18'. 31 I 2.4 k 5.8, 9.8 I 600 t 240, 370 1697W0088
1697W0089
1697W0090
MW-50-67-(008)
9 t- 19, 32 7.9 t- 5.3, 8.8 5,620 k 470 , 370 MW-50-42-(008)
7 t- 19 , 32 4.4 k 5.2, 8.8 2,740 t- 350, 370 MW-49-26-(008)
-11 k 18, 32 7.9 t 5.3, 8.8 9,070 ? 610, 370 1697W0091
1697W0092
MW-49-42-(008)
2 t 19, 32 4.7 t- 5.2, 8.8 6,300 k 500, 370 MW-49-65-(008)
-6 t 18, 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 ORISE Sample ID CONCENTRATIONS
OF TECHNETIUM-99 (Tc-99) IN WATER SAMPLES
BY LIQUID SCINTILLATION
ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Tc-99 NRC Region I Sample ID Concentrationsa (pCi/L) ~~ 1697W0085
MW-55-35-(001)
-2.7 k 8.1 , 14.0 1- 1697W0086
MW-55-544001)
-4.5 -t 8.0 ~ 14.0 1 I 1697W0080
MW-45-43-(007)
1 11 1697W0081
I MW-45-62-(007)
1697W0088
MW-50-67-(008)
1697W0089
MW-50-42-(008)
11 1697W0082
I MW-53-80-(002)
I 11 1697W0083
I MW-53-120-(002)
1697W0091
MW-49-42-(008)
-3.8 !c 8.0 14.0 1697W0092 MW-49-65-(008) -5.7
& 8.0 14.0 11 1697W0084
I MW-55-24-(001)
-1.6 !r 8.1" 14.0 -3.0 k 8.1 . 14.0 ~~ ~ 0.7 rL 8.1 , 14.0 4.0 2 8.2, 14.0 0.3 !r 8.1 , 14.0 -0.6 & 8.1 . 14.0 -3.3 IfI 8.0, 14.0 11 1697W0087
I MW-56-85-(002)
I 1.1 k 8.2, 14.0 11 1697W0090
I MW-49-26-(008)
-5.7 k 8.0, 14.0 ~ -3.4 !c 8.0, 14.0 -2.7 k 8.1 , 14.0 ~~ "The PVflXs are after
the comma. "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 ORISE Sample ID CONCENTRATIONS
OF TOTAL RADIOSTRONTIUM
IN WATER SAMPLES BY LOW BACKGROUND
BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide and MDCS" (pCi/L) NRC Region I Concentrations, TPU~, Sample ID 1697W0078
1697W0079
MW-41-42-(007)
3.45 k 0.48b , 0.57 MW-41-64-(006)
2.12 & 0.43 . 0.58 1697W0080
-5143-(007)
I 0.02 k 0.72 , 1.26 1697W0087
1697W0088
~ MW-45-62-(007)
I 0.21 1697W0081
k 0.34 ~ 0.). 1697W0082
MW-53-80-(002)
-0.18 k 0.34 , 0.61 1697W0083
MW-53-120-(002)
34.3 ? 1.5 1697W0084
MW-55-24-(001)
18.8 k 1.0 MW-56-85-(002)
-0.02 k 0.60 , 1.05 MW-50-67-(008)
27.1 k 1.3 , 0.7 1697W0085
1- MW-55-35-(001)
I 43.6 k 1.8 , 0.7 1697W0090
1697W0091
1697W0092
1697W0086
I MW-55-54-(001)
I 34.8 ? 1.8 ~ 1.0 MW-49-26-(008)
15.27 k 0.92 , 0.63 MW-49-42-(008)
23.6 k 1.3 , 0.7 MW-49-65-(008)
19.6 * 1.1 , 0.7 1697W0089
I MW-50-42-(008)
I 12.46 k 0.83 , 0.62 '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 -0.04 2 0.12 , 0.28 I 0.00 t- 0.01 . 0.02 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 1697KVoo82
1697M0045
~ m-53-80-(002)
0.17 k 0.20 , 0.33 0.11 k 0.13 , 0.20 1697VK@32
filter 0.02 f 0.02 . 0.04 0.00 k 0.01 . 0.02 0.11 t- 0.16 , 0.27 0.01 t 0.01 , 0.01 0.06 k 0.10 , 0.18 0.00 k 0.01 , 0.03 -0.03 t- 0.13 , 0.24 0.00 k 0.01 , 0.02 0.05 k 0.12 , 0.22 0.04 f 0.05 , 0.05 0.01 t- 0.01 , 0.01 0.00 f' 0.01 , 0.02 0.00 f 0.04 , 0.10 0.01 t- 0.10 , 0.19 -0.02 k 0.02 , 0.04 0.00 t 0.01 , 0.02 0.03 5 0.06 , 0.11 0.06 k 0.12 , 0.20 0.00 f 0.01 , 0.02 0.00 t- 0.01 , 0.02 ~~ ~ 1697M0046
1697W0084
1697W0083
filter W-55-24-(001)
_______ ORISE Sample ID 1697W0078
r Ki/L for water) NRC Region I Radionuclide Concentrationsa
@Ci/g ( Sample ID Am-241 Cm-242 sediment in 100 mL Cm-243 /244
N~-237 0.04 t 0.13 . 0.25 0.00' t- 0.11 . 0.24 0.00 -t 0.05 , 0.14 1697M0041
0.01 k 0.02 , 0.03 0.00 t 0.01 , 0.02 0.02 & 0.04 . 0.06 0.01 f 0.01 , 0.02 1697W0079
0.02 t 0.07 . 0.15 0.00 k 0.10 . 0.22 m-41-64-(006)
0.04 k 0.19 , 0.35 1697W0079
filter 0.00 f 0.02 , 0.03 1697M0042
0.00 k 0.01 , 0.03 -0.07 k 0.09 . 0.25 0.00 t- 0.01 , 0.02 0.02 t 0.04 . 0.06 0.00 f 0.01 , 0.02 0.06 f 0.10 . 0.18 ~ 1697W0080
1697M0043
0.00 f 0.01 , 0.03 0.04 2 0.13 . 0.25 0.00 k 0.02 0.03 0.05 t 0.09 . 0.16 0.01 2 0.01 , 0.02 0.00 t- 0.06 , 0.16 0.00 t 0.01 , 0.02 1697W0081
1697M0044
0.01 t- 0.01 , 0.01 0.01 t 0.01 , 0.02 0.00 & 0.05 ~ 0.14 -0.002 k 0.004d , 0.015 1697W0083
1 Mw-53-120-(002)
-0.06 t 0.11 , 0.27 0.01 t- 0.01 . 0.01 0.10 t 0.09 , 0.06 0.01 t- 0.01 . 0.02 1697M0047-
I 1697W0084
filter M\sii-55-35-(00
1) 16c)7WO085
1697M0048
0.02 F 0.08 , 0.16 -0.03 k 0.02 . 0.05 ~~ 1697W0085
filter
F g 3 TABLE 6 (Continued)
I 0" 4 0" 4 w n I 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
U-234 0.78 f 0.25 . 0.14 U-238 0.69 k 0.23 . 0.14 0.00 k 0.01 , 0.01 1.20 k 0.32 , 0.18 0.01 f 0.01 . 0.01 -0.01 f 0.01 , 0.03 0.94 t 0.28 , 0.06 0.01 f. 0.01 . 0.02 0.58 f 0.22 , 0.17 0.09 k 0.03 , 0.01 1.93 f 0.42 . 0.29 0.26 f 0.14 , 0.06 0.11 f 0.03 , 0.01 1.23 k 0.34 . 0.27 0.00 k 0.01 , 0.01 1.38 f 0.34 , 0.18 0.06 L 0.02 . 0.01 0.01 f 0.01 , 0.02 1.13 k 0.31 , 0.20 0.07 f 0.02 . 0.01 0.13 & 0.04 , 0.03 0.75 f 0.24 . 0.06 0.12 f 0.03 , 0.02 0.71 k 0.24 . 0.06 0.80 k 0.26 , 0.18 0.04 !E 0.02 . 0.02 0.74 t 0.24 , 0.06 0.04 f 0.02 . 0.02 TABLE 6 (Continued)
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 F P 3 :oncentrationsa (pCi/g.
a ?sediment
in 100 mL or pCi/L for water) II Pn-2338 NRC Region I Sample ID ORISE Sample ID P~-239/240
0.02 f. 0.08 . 0.17 MW-41-42-(007)
I -0.18 k 0.20 0.44 1697W0078
1697M0041
1697W0078
filter I 0.00 f. 0.02 . 0.04 0.01 k 0.01 , 0.01 1697WOO79
-0.02 f 0.09 , 0.21 0.00 f 0.01 . 0.02 MW-41-64-(006)
0.02 k 0.23 , 0.43 1697W0079
filter 0.01 f 0.02 . 0.02 1697M0042
1697W0080
MW-45-434007)
I 0.14 f 0.11 , 0.06 0.02 k 0.04 , 0.06 1697M0043
1697W0080
filter 0.01 k 0.02 , 0.03 MW-45-62-(007)
0.10 f 0.19 . 0.34 0.01 f 0.01 , 0.01 0.09 f 0.09 . 0.13 1697W0081
1697M0044
~~~ 1697W0081
filter I -0.01 f. 0.02 . 0.04 0.01 k 0.01 . 0.02 1697W0082
0.05 f 0.08 , 0.14 0.01 k 0.01 . 0.01 MW-53-80-(002)
0.09 t 0.20 , 0.36 1697W0082 filter
0.00 f 0.01 . 0.02 1697M0045
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 0.08 f 0.09 - 0.15 1697W0084
1697M0047
0.01 f 0.01 . 0.02 0.09 k 0.03 . 0.01 I 0.15 k 0.04 . 0.01 11 MW-55-354001)
I 0.12 k 0.19 . 0.33 0.02 f. 0.06 , 0.13 0.00 t 0.01 , 0.01 1697W0085
1697W0085
filter I 0.00 t 0.01 , 0.02 1697M0048
P~-239/240
0.02 f 0.04 , 0.06 0.01 k 0.01 . 0.01 u-234 U-238 1.79 f 0.38 , 0.13 1.26 ? 0.32 , 0.16 0.06 k 0.02 . 0.01 0.07 k 0.03 . 0.03 0.08 k 0.08 , 0.06 0.01 f 0.01 . 0.01 1.34 k 0.36 , 0.29 1.29 k 0.35 , 0.25 0.01 f 0.01 . 0.01 0.00 f 0.01 . 0.02 0.00 ? 0.01 , 0.02 0.00 f 0.08 , 0.19 0.01 t 0.01 . 0.01 0.03 k 0.01 , 0.01 0.04 k 0.02 , 0.01 0.70 f 0.23 , 0.06 0.66 ? 0.23 , 0.06 0.02 t 0.01 . 0.01 0.02 k 0.01 . 0.02 0.002 k 0.004 , 0.006 0.11 f 0.12 , 0.17 0.01 ? 0.01 . 0.02 0.00 f 0.01 , 0.03 0.01 f 0.01 , 0.02 1.36 k 0.41 , 0.44 0.83 k 0.27 , 0.18 0.00 f 0.01 . 0.01 0.002 & 0.004 . 0.006 '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 POINT POWER STATION
BUCHANAN, NEW YORK Radionuclide
- oncentrationsa (pCi/e of sediment in 100 mL or pCi/L for water) ORISE 1697W0086
NRC Region I Sample ID MW-55-54-(001)
Pu-238 0.25 k 0.26 . 0.42 11 1697M0049 1697W0086 filter
0.01 f 0.01 , 0.03 1697W0087
1697M0050
1697W0088
-5 -. 1697M0051
1697W0089
1697M0052
1697W0090
1697M0053
$ 51 1697W0091
1697M0054
1697W0092
1697M0055
\ h 0 -4 \ L c c: 5 ' Y 0. "The MDCs are after
the con MW-56-85-(002) 1697W0087 filter
0.00 t 0.06 , 0.16 0.00 k 0.02 . 0.04 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 1697W0088 filter
MW-50-42-(008)
0.01 f 0.01 , 0.02 0.02 k 0.25 . 0.46 1697W0089 filter
0.00 f 0.02 . 0.03 0.09 f 0.11 , 0.18 I 1.36 k 0.33 , 0.06 I 0.71 k 0.24 , 0.14 MW-49-26-(008) 1697W0090 filter
0.15 t 0.24 , 0.41 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 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 1697WOO91
filter MW-49-65-(008)
0.01 f 0.01 , 0.02 -0.11 k 0.21 . 0.43 1697W0092 filter
0.00 f 0.01 , 0.02 ma. 5% confidence
level, based on "b 5 Uncertainties represent
the ' id propagated uncertainties
3 E 5 'Zero values are due to rounding. dSignificant figures
expanded to avoid reporting a
TPU of zero at the request
of the inspector.
TABLE 7 ~ ~~ 1697W0079
1697M0042
1697W0080
1697M0043
CONCENTRATIONS
OF PLUTONIUM-241
ALPHA EMITTING RADIONUCLIDES
IN SUSPENDED
AND DISSOLVED FRACTIONS
OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK MW-41-64-(006)
-1 5 rf: 34 , 59 1697W0079
filter -1.0 k 3.5 , 6.0 MW-45-43-(007)
6 k 34 , 58 1697W0080 filter
-4.6 ? 3.7 . 6.3 ORISE Sample ID 1697W0081
1697M0044
1697W0082
1697M0045
Radionuclide
Concentrations (pCi/g of sediment in 100 ml or pCi/L for water) NRC Region I Sample ID MW-45-62-(007)
7 k 36 , 62 1697W0081 filter
0.1 5 3.6 , 6.2 MW-53-80-(002)
-2 1 k 32 , 56 1697W0082 filter
-1.2 k 3.6 . 6.2 1697W0083
1697M0046
1697W0084
1697M0047
1697W0085
1697M0048
1697W0086
1697M0049
1697W0087
1697M0050
1697W0088
1697M0051
II 1697M0041
I 1697W0078 filter
I -0.9 & 3.6 , 6.2 MW-53-120-(002)
-1 k 33 , 56 1697W0083 filter
-0.3 rf: 3.5 , 6.0 MW-55-24-(001)
2 k 35 , 60 1697W0084 fdter
0.9 t 3.8 , 6.5 MW-55-35-(001)
39 rf: 30 , 49 1697W0085 filter
-4.4 rf: 3.7 , 6.3 MW-55-54-(001)
25 k 30 , 50 1697W0086
filter 1.4 k 3.1 , 5.3 MW-56-85-(002)
34 k 30 , 50 1697W0087 filter
1.1 rf: 3.7 , 6.4 MW-50-67-(008)
28 k 31 , 51 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)
ORISE Sample ID 1697W0089
1697W0052
1697W0090
1697M0053
1697W0091
1697M0054
1697W0092
1697M0055 CONCENTRATIONS OF
PLUTONIUM-241
ALPHA EMITTING RADIONUCLIDES
IN SUSPENDED
AND DISSOLVED FRACTIONS
OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide
Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water) NRC Region I Sample ID MW-50-42-(008) 27
k 31 , 52 1697W0089 filter 0.6
k 3.5 , 5.9 MW-49-26-(008)
14 k 28 , 47 1697W0090
filter 1.7 k 3.7 6.2 MW-49-42-(008)
16 k 30 , 51 1697WOO91
filter 2.8 k 3.9 6.4 MW-49-65-(008)
8 k 27 , 46 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 ORISE Sample ID CONCENTRATIONS
OF CARBON-14
IN WATER SAMPLES BY LIQUID SCINTILLATION
ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Sample ID 1697W0078
1697W0079
~~ MW-41-42-(007)
MW-41-64-(006)
11 1697W0080
I MW-45-434007)
((9G84 -T MW-55-24-(001)
11 1697W0085
1 MW-55-35-(001)
11 1697W0089
I MW-50-42-(008)
Radionuclide
Concentrations, TPUs, and MDCS" (pCi/L) b -11.1 k 9.3 . 16.2 11 -7.8 k 9.3 , 16.2 11 1 9.5 I 16.2 1 2.5 -2.5 If: 9.4 16.2 -4.9 9.4 16.2 ___ If: 9.5 . 16.2 11 0.5 -1.1 If: 9.5 16.2 4.3 ? 9.6 16.2 7.2 k 9.6 16.2 1.3 k 9.5 . 16.2 -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