|
---|
Category:Environmental Assessment
MONTHYEARML21062A2712021-03-31031 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Big Rock Point ISFSI ML0428900542005-03-11011 March 2005 Environmental Assessment and Finding of No Significant Impact Related to Consideration of a License Termination Plan ML0435502502005-01-11011 January 2005 Environmental Assessment and Finding of No Significant Impact for Consumers Energy'S Request to Modify Existing 20.2002 Authorization, for Big Rock Point ML0434906422004-10-27027 October 2004 Analytical Results for Water Samples Collected 12/02/2003 at Big Rock Point Nuclear Plant, Charlevoix, Michigan (Inspection Report No. 050-00155-03-07) (Rfta 04-001) 2021-03-31
[Table view] Category:Letter
MONTHYEARIR 07200043/20234012024-02-0505 February 2024 Public-Big Rock Point (Brp) Independent Spent Fuel Storage Installation (ISFSI) - NRC Security Inspection Report 07200043/2023401 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 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 PNP 2023-015, License Termination Plan, Revision 42023-05-16016 May 2023 License Termination Plan, Revision 4 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-013, 2022 Radiological Environmental Operating Report2023-04-12012 April 2023 2022 Radiological Environmental Operating Report ML23101A1172023-04-11011 April 2023 Human Performance Error Resulted in Compensatory Measures Not Properly Employed L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-009, Report of Changes, Tests and Experiments and Summary of Commitment Changes2023-03-28028 March 2023 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2023-003, Independent Spent Fuel Storage Installation Radioactive Effluent Release Report2023-02-15015 February 2023 Independent Spent Fuel Storage Installation Radioactive Effluent Release Report L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22215A1472022-08-0303 August 2022 & Big Rock Point Plant - Update Report for Holtec Decommissioning International (HDI) Fleet Decommissioning Quality Assurance Program (DQAP) Revision 2 ML22213A0092022-07-27027 July 2022 2022 Holtec Palisades, LLC and Holtec Decommissioning International, LLC ANI Certified Copy Endorsements for Palisades Nuclear Plant and Big Rock Point Nuclear Generating Plant ML22182A4982022-07-0101 July 2022 and Big Rock Point Plant, Indemnity Agreements ML22173A1732022-06-28028 June 2022 and Big Rock Point Plant - Issuance of Amendment Nos. 129 and 273 Order Approving Transfer of Licenses and Conforming License Amendments (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) PNP 2022-019, & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals2022-06-24024 June 2022 & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals ML22178A0772022-06-24024 June 2022 (HDI) Satisfactory Documentary Evidence Required Before the Planned Closing Date of the Purchase and Sale Transaction of Palisades Nuclear Plant and Big Rock Point Plant ML22096A3042022-05-0909 May 2022 and Big Rock Point Plant - New Information Regarding Order Approving Transfer of Licenses (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) PNP 2022-003, and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report2022-04-25025 April 2022 and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report ML22104A0782022-04-14014 April 2022 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML22088A2552022-03-29029 March 2022 Change for NRC Distribution Lists Re Entergy'S Vice President, Regulatory Assurance ML22087A5002022-03-28028 March 2022 and Palisades Nuclear Power Plant - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) -- Entergy Nuclear Operations, Inc ML22081A2992022-03-21021 March 2022 Entergy Operations, Inc - Summary of Property Damage Insurance Coverage ML22073A1892022-03-14014 March 2022 River Bend Nuclear Station; and Waterford Steam Electric Station, Unit 3 - Proof of Financial Protection (10 CFR 140.15) PNP 2022-001, 2021 ISFSI Annual Radioactive Effluent Release Report2022-02-24024 February 2022 2021 ISFSI Annual Radioactive Effluent Release Report ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22021B6702022-01-21021 January 2022 and Big Rock Point - Supplement to Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments ML21354A7452021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination ML21349A3742021-12-15015 December 2021 ISFSI, Decommissioning Funding Plans (10 CFR 72.30) ML21292A1452021-12-13013 December 2021 and Big Rock Point Plant - Order Approving Transfer of Licenses and Draft Conforming Administrative License Amendments (EPID L-2020-LLM-0003) (Letter) ML21302A0642021-10-29029 October 2021 and Big Rock Point - Supplement to Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments IR 07200043/20214012021-07-29029 July 2021 Independent Spent Fuel Storage Installation Security Inspection Report 07200043/2021401 PNP 2021-023, Biennial Update License Termination Plan2021-05-19019 May 2021 Biennial Update License Termination Plan PNP 2021-015, and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report2021-04-21021 April 2021 and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report ML21054A1322021-04-14014 April 2021 U.S. NRC Analysis of Entergy Nuclear Operations, Inc'S Initial and Updated Decommissioning Funding Plans for the Big Rock Point, Indian Point, Pilgrim, Palisades, Fitzpatrick, and Vermont Yankee Independent Spent Fuel Storage Installations ML21091A1472021-04-0101 April 2021 Annual Report for Entergy Quality Assurance Program Manual and Indian Point Energy Center Quality Assurance Program Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to ML21089A3222021-03-30030 March 2021 Entergy Operations, Inc and Entergy Nuclear Operations, Inc. - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML21084A7892021-03-25025 March 2021 Entergy Nuclear Operations, Inc. Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2020 - 10 CFR 50.82(a)(8)(vii) ML21084A8112021-03-25025 March 2021 Indian Point Nuclear Generating, Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) PNP 2021-009, 2020 ISFSI Annual Radioactive Effluent Release Report2021-02-25025 February 2021 2020 ISFSI Annual Radioactive Effluent Release Report ML21022A2212021-02-0505 February 2021 Letter to Senator Charles Schumer from Margaret Doane Response for NRC to Reconsider Its Decision to Not Allow for a Public Hearing in the Transfer of Indian Point'S License ML21012A0312021-02-0101 February 2021 and Big Rock Point Plant - Notice of Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments and Opportunity for a Hearing ML21011A0672021-02-0101 February 2021 Proposed Post-Shutdown Decommissioning Activities Report with Site-Specific Decommissioning Cost Estimate PNP 2020-042, and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2020-12-23023 December 2020 and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments PNP 2020-041, Independent Spent Fuel Storage Installation Radioactive Effluent Release Report2020-12-0909 December 2020 Independent Spent Fuel Storage Installation Radioactive Effluent Release Report 2024-02-05
[Table view] |
Text
> R I S HE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 27, 2004 Mr. James Shepherd U.S. Nuclear Regulatory Commission NMSS/DWM/DCB Mail Stop: T7F27 11545 Rockville Pike Rockville, Maryland 20852
SUBJECT:
ANALYTICAL RESULTS FOR WATER SAMPLES COLLECTED DECEMBER 2,2003 AT BIG ROCK POINT NUCLEAR PLANT, CHARLEVOIX, MICHIGAN (INSPECTION REPORT NUMBER 050-00155/2003-07) JRFTA 04-001]
Dear Mr. Shepherd:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) received six water samples on December 3, 2003 that were collected on December 2, 2003 at the Big Rock Point Nuclear Plant in Charlevoix, Michigan. The following analyses were performed on the samples per the sampling plan received by e-mail on November 18, 2003:
- 1. Gamma spectrometry (Procedure CPI, Revision 13)
- 2. Gross alpha and gross beta (Procedure API, Revision 14; Procedure CP3, Revision 2)
- 3. H-3 (Procedure AP2, Revision 14; Procedure CP4, Revision 2)
- 4. C-14 (Non-routine Procedure AP9, Revision 2; Procedure CP4, Revision 2)
- 5. Sr-90 as Total Radiostrontium by low background beta counting (Procedure AP4, Revision 11; Procedure CP3, Revision 2)
- 6. Pu-241 (Non-routine Procedure APIO, Revision 2; Procedure CP4, Revision 3)
- 7. Ni-63 (Non-routine Procedure AP12, Revision 3; Procedure CP4, Revision 3)
- 8. Fe-55 (Non-routine Procedure AP13, Revision 3; Procedure CP4, Revision 3)
- 9. Alpha isotopic (Procedure API 1, Revision 2; Procedure CP2, Revision 11)
The data for these analyses are presented in Tables 1 through 7, respectively.
Ni-59 was one of the requested radionuclides. ESSAP does not have the capability to analyze samples for Ni-59 due to the extremely low energies of the x-rays associated with this radionuclide. This fact should have been pointed out before beginning the analytical work and we apologize for this oversight.
P.0. BOX 117, OAK RIDGE, TENNESSEE 37831-0117 Operated by Oak Ridge Associated Universities for the U.S. Department of Energy
Mr. James Shepherd Januatya27, 2004 ESSAP's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 with any questions or comments.
Sincerely, Dale Condra Laboratory Manager Environmental Survey and Site Assessment Program RDC:WPI:ar Enclosure cc: T. McLaughlin, NRCINMSS/TWFN/7F27 E. Knox-Davin, NRC/NMSS/TWFN/8A23 J. Peckenpaugh, NMSS/DWM/EPAB M. LaFranzo, Region III G. Purdy, NRC/NMSS/TWFN/7F27 W. Snell, Region III E. Abelquist, ORISE/ESSAP T. Vitkus, ORISE/ESSAP File/895 Distribution approvaland concurrence: Initials Date Technical Management Team Member I I 1 7f /,U/
Quality Manager rP? a I O
ORISE TABLE 1 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROMETRY CP1, REVISION 13 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN ESSAP Sample l NRC Region IIII Radionuclide Concentrations 2 (pCi/L)
ID Sample ID Mn-54 Co-60 I Zn-65 -1um 1-129 895W001 MW-9 0.1 +/-1.6b 0.1 +/- 1.8 3.5 +/- 4.2 0.9 +/- 1.5 23 +/- 24 895W002 PZ-3MB 0.3 2.1 2.7 +/- 2.3 0.7 +/- 5.1 -3.0+/- 2.1 2 25 895W003 PZ-5S 0.8+/-2.0 -0.9+/-2.1 -2.7+/-4.7 0.4+/- 1.9 -11 + 18 895W004 PZ-3D 0.3 +/- 2.0 0.6 +/- 2.2 1.8 +/- 4.4 0.3 +/- 2.0 12 + 24 895W005 PZ-3MA 0.4 2.0 0.9 2.0 -2.0 4.7 -0.2 1.9 14 +/- 18 895W006 MW-6 0.Oc 1.6 -0.7 1.7 -6.4 3.7 1.2 1.5 -3 + 24 ESSAP Sample NRC Region III Radionuclide Concentrationsa (pCiJL)
ID Sample ID Cs -152 Eu-154 Eu5 895W001 MW-9 0.2 1.8 -0.7 + 1.7 -1.6 + 4.4 -3.8 7.6 1.1 +/-3.6 895W002 PZ-3MB -1.5 2.5 -3.9 +/- 4.2 -2.9 + 5.5 -8 10 -0.9 4.9 895W003 PZ-5S 1.9 2.2 0.5 +/- 2.2 -3.0 +/- 4.9 -5.8 9.6 3.0 4.8 895W004 PZ-3D 0.4 2.2 0.0 +/- 4.4 1.9 5.5 -10.7 9.7 0.1 +/-4.6 895WO05 PZ-3MA -0.9 +/- 2.4 -0.8 + 2.1 -2.0 +/- 5.0 8.5 +/- 9.3 -3.4 +/- 4.6 895W006 MW-6 1.2 1.9 -1.3 +/- 1.7 2.2 4.3 -6.0 7.9 -1.7 3.5
'The average MDCs for a sixteen hour count of water in a 1.0 L Mnrinelli range from a low of 3.0 pCi/L for Ag- IlOm to a high of 37 pCi/L for 1-129.
bUncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero values are due to rounding.
ORISE TABLE 2 CONCENTRATIONS OF GROSS ALPHA AND BETA IN WATER SAMPLES BY LOW BACKGROUND ALPHA AND BETA COUNTING API, REVISION 14; CP3 REVISION 2 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN ESSAP ID NRC Region III j Concentrations (pCiIL)
SampleP I lGross Aplpaa JGross Betab 895WO01 MW-9 0.5 E 1.8c 8.6 +/- 2.8 895W002 PZ-3MB 2.4 4 3.6 13.1 4 3.1 895WO03 PZ-5S 3.4 + 4.3 17.1 + 5.6 895W004 PZ-3D 3.8 + 2.6 9.3 4 2.9 895WO05 PZ-3MA 3.3 +/- 2.8 6.5 +/- 2.7 895W006 MW-6 4 i 20 39 + 26
'The average MDC for gross alpha for a 200 minute count using sample quantities ranging from 0.01 L to 0.1 L is 10 pCi/L.
bThe average MDC forgross beta fora 200 minute count using sample quantities ranging from O.01 Lto 0.1 L is l pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
ORISE TABLE 3 CONCENTRATIONS OF AMERCIUM-241 and CURIUM 243/244 IN WATER SAMPLES BY ALPHA SPECTROSCOPY API1, REVISION 2; CP2 REVISION 11 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN Radionuclide Concentrations ESSAP Sample NRC Region III (pCi/L)
ID Sample ID Am-241a 1 Cm-243/244b 895WO01 MW-9 -0.06 +/- 0.21c 0.04 +/- 0.22 895W002 PZ-3MB -0.02 +/- 0.23 -0.26 +/- 0.23 895W003 PZ-5S 0.32 +/- 0.32 -0.11 +/- 0.23 895W004 PZ-3D 0.15 0.17 0.04 0.16 895W005 PZ-3MA 0.15 0.21 -0.13 0.18 895W006 MW-6 0.14 0.21 -0.11 +/-0.21
'The average MDC for a sixteen hour count of a 0.1 L sample for Am-241 is 0.40 pCiIL.
t'The average MDC for a sixteen hour count of a 0.1 L sample for Cm-243/244 is 0.42 pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
ORISE TABLE 4 CONCENTRATIONS OF PLUTONIUM RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY API1, REVISION 2; CP2, REVISION 11 AND LIQUID SCINTILLATION ANALYSIS NON-ROUTINE AP10, REVISION 2; CP4, REVISION 3 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN ESSAP Sample NRC Region III Radionuclide Concentrations (pCiUL)
ID Sample ID Pu-238 l Pu-239/240 l Pu-241 895WO01 MW-9 0.04 +/- 0.15c 0.06 +/- 0.09 7 +/- 20 895W002 PZ-3MB 0.00d +/-0.17 0.07 0.10 5 18 895W003 PZ-5S -0.18 +/- 0.14 0.02 +/- 0.09 -1 +/- 19 895W004 PZ-3D -0.08 +/- 0.14 0.06 +/- 0.07 -2 +/- 18 895WO05 PZ-3MA -0.23 +/- 0.15 0.02 +/- 0.07 11 +/- 19 895W006 MW-6 -0.02 +/- 0.15 -0.06 +/- 0.09 1 +/- 17
'The average MDC for Pu-238 and Pu-239/240 for a sixteen hour count using a 0.1 L sample is 0.25 pCi/L.
bThe average MDC for Pu-241 for a one hour count using a 0.1 L sample is 31 pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
dZero values are due to rounding.
ORISE TABLE 5 CONCENTRATIONS OF TRITIUM AND CARBON-14 IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 14; NON-ROUTINE AP9, REVISION 2; CP4, REVISION 3 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN
. Tritium C-14 ESSAP Sample NRC Region III Concentrationsa Concentrationsb ID Sample ID (pCi/L) (pCiIL) 895W001 MW-9 190 230c 13 +/- 22 895W002 PZ-3MB 290 230 37 +/- 22 895W003 PZ-5S 310 240 41 +/- 22 895W004 PZ-3D 770 250 15 +/- 22 895W005 PZ-3MA 2900 +/- 310 28 +/- 22 895W006 MW-6 2050 +/-290 32 +/- 22
'The average MDC for a one hour count of a 0.01 L sample for tritium is 390 pCi/L.
bfhe average M DC for a six hour count of a 0.05 L sample for C-14 is 37 pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
ORISE TABLE 6 CONCENTRATIONS OF IRON-55 AND NICKEL-63 IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS NON-ROUTINE AP12, REVISION 3; NON-ROUTINE AP13, REVISION 3; CP4, REVISION 3 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN ESSAP Sample NRC Region III Fe-55 Concentrationsa Ni-63 Concentrationsb ID Sample ID l (pCi/L) l (pCi/L) 895W001 MW-9 52 28c 24 +/- 13 895W002 PZ-3MB 46 +/- 27 23 + 13 895W003 PZ-5S 31 26 20 + 13 895W004 PZ-3D 25 i 26 21 +/- 13 895W005 PZ-3MA 41 27 -14 12 895W006 MW-6 35 26 11 13
'he average MDC for a one hour count of a 0.I L sample for Fe-55 is 42 pCi/L.
The average MDC for a one hour count of a0.1 L sample for Ni-63 is 21 pCi/L.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
ORISE TABLE 7 CONCENTRATIONS OF STRONTIUM-90 AS TOTAL STRONTIUM IN WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 12; CP3, REVISION 2 BIG ROCK POINT NUCLEAR PLANT CHARLEVOIX, MICHIGAN ESSAP Sample l NRC Region III l Sra9o a ID Sample ID Concentrations
_ _ __ __ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _(p C iIL )
895WO01 MW-9 0.9 1.7' 895W002 PZ-3MB 1.5 + 1.7 895W003 PZ-5S 0.Oc + 1.7 895W004 PZ-3D 0.2 +/- 1.4 895WO05, PZ-3MA 1.1 2.2 895WO06 MW-6 0.5 +/- 1.7 aThe average MDC for a one hour count of a 0.25 L sample for Sr-90 is 2.9 pCifL.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
cZero values are due to rounding.