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Category:Environmental Monitoring Report
MONTHYEARML24135A1922024-05-14014 May 2024
2022 Annual Radioactive Effluent Release Report - Errata
ML24135A1912024-05-14014 May 2024
2023 Annual Radioactive Effluent Release Report
L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024
2023 Annual Radiological Environmental Operating Report
ML23291A1092023-10-23023 October 2023
Subsequent License Renewal Application Requests for Confirmation of Information Environmental Review
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
ML21133A4952021-05-13013 May 2021
2020 Annual Radiological Environmental Operating Report
L-MT-21-033, 2020 Annual Radioactive Effluent Release Report2021-05-13013 May 2021
2020 Annual Radioactive Effluent Release Report
L-MT-20-013, 2019 Annual Radiological Environmental Operating Report2020-05-14014 May 2020
2019 Annual Radiological Environmental Operating Report
L-MT-20-014, 2019 Annual Radioactive Effluent Release Report2020-05-14014 May 2020
2019 Annual Radioactive Effluent Release Report
L-MT-18-029, 2017 Annual Radiological Environmental Operating Report2018-05-10010 May 2018
2017 Annual Radiological Environmental Operating Report
L-MT-17-039, 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual(Enclosure 2)2017-05-10010 May 2017
2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual(Enclosure 2)
L-MT-16-035, Corrections to 2011, 2012, 2013, and 2014 Annual Radiological Environmental Operating Reports2016-10-20020 October 2016
Corrections to 2011, 2012, 2013, and 2014 Annual Radiological Environmental Operating Reports
L-MT-16-030, Transmittal of 2015 Annual Radiological Environmental Operating Report2016-05-12012 May 2016
Transmittal of 2015 Annual Radiological Environmental Operating Report
L-MT-16-022, Radioactive Effluent Release Report for 20152016-05-12012 May 2016
Radioactive Effluent Release Report for 2015
L-MT-16-024, Flood Hazard Reevaluation Report2016-04-21021 April 2016
Flood Hazard Reevaluation Report
L-MT-15-036, 2014 Annual Radiological Environmental Operating Report2015-05-12012 May 2015
2014 Annual Radiological Environmental Operating Report
ML15132A6222015-05-12012 May 2015
2014 Radioactive Effluent Release Report
L-MT-14-012, 2013 Radioactive Effluent Release Report2014-05-15015 May 2014
2013 Radioactive Effluent Release Report
L-MT-13-042, Submittal of 2012 Annual Radiological Environmental Operating Report2013-05-10010 May 2013
Submittal of 2012 Annual Radiological Environmental Operating Report
ML13135A0122012-12-31031 December 2012
Radioactive Effluent Release Report for January 1 - December 31, 2012
L-MT-12-042, Submittal of 2011 Annual Radiological Environmental Operating Report2012-05-10010 May 2012
Submittal of 2011 Annual Radiological Environmental Operating Report
L-MT-11-021, Submittal of 2010 Radioactive Effluent Release Report2011-05-12012 May 2011
Submittal of 2010 Radioactive Effluent Release Report
L-MT-11-020, 2010 Annual Radiological Environmental Operating Report2011-05-12012 May 2011
2010 Annual Radiological Environmental Operating Report
ML1013900582010-05-14014 May 2010
Monticello Nuclear Generating Plant - 2009 Annual Radiological Environmental Operating Report
L-MT-10-032, Annual Report to the Us NRC Radiological Environmental Monitoring Program2009-12-31031 December 2009
Annual Report to the Us NRC Radiological Environmental Monitoring Program
ML0920501892009-04-30030 April 2009
Parr Reservoirs Fisheries Surveys: Winter Final Report
L-MT-09-036, Annual Report for the NRC, Radiological Environmental Monitoring Program, January 1 - December 31, 20082008-12-31031 December 2008
Annual Report for the NRC, Radiological Environmental Monitoring Program, January 1 - December 31, 2008
ML0915405192008-05-14014 May 2008
Enclosures 1 and 2 - Radioactive Effluent Release Report and Off-Site Radiation Dose Assessment for January 1 - December 31, 2008
L-MT-07-031, Annual Radiological Environmental Operating Report2007-04-20020 April 2007
Annual Radiological Environmental Operating Report
ML0612806172006-05-0404 May 2006
2005 Annual Radiological Environmental Operating Report
ML0612902442005-12-31031 December 2005
Radioactive Effluent Release Report for January 1 - December 31, 2005
ML0532605652005-11-30030 November 2005
November 2005 Mississippi River Mussel Survey Summary Prepared by Nuclear Management Company, LLC
L-MT-05-042, ODCM-APP-C, Rev 0, Appendix C.2005-05-0909 May 2005
ODCM-APP-C, Rev 0, Appendix C.
L-MT-05-041, 2004 Annual Radiological Environmental Operating Report2005-04-29029 April 2005
2004 Annual Radiological Environmental Operating Report
ML0520103862005-03-30030 March 2005
Xcel Energy'S Air Emission Inventory Reports for 2004 to the Minnesota Pollution Control Agency
ML0520104802005-01-31031 January 2005
Xcel Energy/Usfws Avian Protection Memorandum of Understanding, Semi-Annual Report: Covering July 1, 2004 Through December 31, 2004 Reporting Period
ML0520103272004-12-31031 December 2004
Offsite Radiation Dose Assessment for January 1 - December 31, 2004 for Monticello Nuclear Generating Plant
ML0532605692004-12-31031 December 2004
Minnesota Statewide Mussel (Bivalvia: Unionidae) Survey: 2003-2004
ML0520103032004-10-0505 October 2004
Letter from Minnesota Pollution Control Agency to Xcel Energy Forwarding Summary of Pollutant Emissions for 2003
ML0520104782004-07-30030 July 2004
Xcel Energy/Usfws Avian Protection Memorandum of Understanding, Semi-Annual Report: Covering January 1, 2005 Through June 30, 2004 Reporting Period
L-MT-04-030, 2003 Annual Radiological Environmental Operating Report2004-05-14014 May 2004
2003 Annual Radiological Environmental Operating Report
ML0520102422004-04-24024 April 2004
U.S. EPA Green Book - Nonattainment Status for Each County by Year from the Monticello Environmental Site Audit
ML0520103002004-03-30030 March 2004
Xcel Energy'S 2003 Air Emission Inventory Reports to the Mn Pollution Control Agency
ML0520105192004-01-28028 January 2004
Xcel Energy/Usfws Avian Protection Memorandum of Understanding, Semi-Annual Report #4: Covering August 3, 2003 Through December 31, 2003 Reporting Period
ML0520105082004-01-0101 January 2004
Environmental Monitoring Program: 2002 - 2003 Report
ML0520103072003-12-31031 December 2003
Offsite Radiation Dose Assessment for January 1 - December 31, 2003 for Monticello Nuclear Generating Plant
ML0520102992003-10-0606 October 2003
Letter from Minnesota Pollution Control Agency to Xcel Energy Forwarding Summary of Pollutant Emissions for 2002
2024-05-14
[Table view]
Category:Report
MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024
Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)
ML23172A1112023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022
Technical Specification 5.6.4 Post Accident Monitoring Report
ML21211A5962021-06-30030 June 2021
Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit
L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021
Nuclear Material Transaction Report
L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020
10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange
ML19308A0562019-10-0808 October 2019
Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS)
L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..
L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017
Steam Dryer Visual Inspection Report
L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017
Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4
ML17088A5272017-03-31031 March 2017
NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017
Mitigating Strategies Flood Hazard Assessment (MSA) Submittal
ML16302A2462016-10-28028 October 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima..
ML16221A2752016-07-31031 July 2016
ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I.
L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016
ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.
L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016
Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).
ML15274A4752015-09-29029 September 2015
Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary)
L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015
Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits
ML15274A4742015-09-29029 September 2015
Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints
ML15175A3362015-07-0808 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force
ML15169A3582015-06-11011 June 2015
PSP Rev 14 Technical Review 06-11-15
ML16035A1842015-01-30030 January 2015
Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds.
ML16035A1862015-01-30030 January 2015
54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3
ML16035A1852015-01-30030 January 2015
54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3
L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014
Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103
ML16005A1102014-09-25025 September 2014
Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant
L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014
LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8.
ML14269A3252014-09-0505 September 2014
LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process.
ML14269A3232014-09-0505 September 2014
LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data.
ML14204A6232014-07-18018 July 2014
Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
ML18100A1902014-05-22022 May 2014
Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records
ML14136A2892014-05-12012 May 2014
14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report.
L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014
ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.
ML14069A0052014-04-11011 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14014A2682014-02-28028 February 2014
Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan
ML14064A1862014-02-25025 February 2014
Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations
L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014
Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information
ML13358A3732013-12-31031 December 2013
Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013
Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit
ML13282A1422013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
ML13248A3442013-08-29029 August 2013
WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10
ML13248A3452013-08-29029 August 2013
WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11
ML13248A3462013-08-29029 August 2013
WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12
ML13248A3482013-08-29029 August 2013
WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13
L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 142013-08-29029 August 2013
WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14
ML13200A1962013-07-31031 July 2013
ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel.
ML13200A1922013-07-31031 July 2013
ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies.
2024-06-10
[Table view]
Category:Miscellaneous
MONTHYEARML23172A1112023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1
L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017
Steam Dryer Visual Inspection Report
ML17088A5272017-03-31031 March 2017
NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017
Mitigating Strategies Flood Hazard Assessment (MSA) Submittal
ML16302A2462016-10-28028 October 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima..
ML16221A2752016-07-31031 July 2016
ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I.
L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016
ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.
ML15175A3362015-07-0808 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force
ML15169A3582015-06-11011 June 2015
PSP Rev 14 Technical Review 06-11-15
ML14204A6232014-07-18018 July 2014
Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7
ML14136A2892014-05-12012 May 2014
14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report.
ML14014A2682014-02-28028 February 2014
Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013
Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit
ML13282A1422013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 142013-08-29029 August 2013
WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14
ML13248A3482013-08-29029 August 2013
WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13
ML13248A3462013-08-29029 August 2013
WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12
ML13248A3452013-08-29029 August 2013
WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11
ML13248A3442013-08-29029 August 2013
WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10
ML13205A0852013-07-12012 July 2013
Enclosure 2 - Westinghouse Electric Co. Letter LTR-A&SA-13-14, NP-Attachment, Revision 0, Responses to the U.S. NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #5
L-MT-13-053, 0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)2013-01-31031 January 2013
0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)
ML13039A2002013-01-21021 January 2013
Enclosures 1 & 2 to L-MT-12-114 - Responses to the Gap Analysis and Marked Up Page Changes to EPU Documentation Based on the Gap Analysis Results, Part 1 of 3
ML13039A2022013-01-21021 January 2013
Enclosures 1 & 2 to L-MT-12-114 - Responses to the Gap Analysis and Marked Up Page Changes to EPU Documentation Based on the Gap Analysis Results, Part 2 of 3
ML12356A1722012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 3 of 8
ML12356A1692012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 8 of 8
ML12356A1702012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 1 of 8
ML12356A1712012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 2 of 8
ML12356A1742012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 4 of 8
ML12340A4302012-11-30030 November 2012
Enclosure 2, Presentation Materials Used During the Course of the NRC Audit of General Electric - Hitachi Held on October 24-25, 2012 - Non-Proprietary
L-MT-12-112, Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 7 of 82012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 7 of 8
ML12356A1752012-11-30030 November 2012
Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 5 of 8
L-MT-12-103, Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012
Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12146A1132012-06-0808 June 2012
Letter Approving Deviation from Response Schedule Imposed by 10 CFR 50.54(f) Letter Re. NTTF Issue R9.3
L-MT-11-076, 2011 Report of Changes and Errors in ECCS Evaluation Models2011-12-22022 December 2011
2011 Report of Changes and Errors in ECCS Evaluation Models
ML1127000692011-09-26026 September 2011
Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
ML1027903732010-09-28028 September 2010
Enclosure 2, GE-MNGP-AEP-1913 R1, GEH Responses to Reactor Systems RAIs
ML1016705842010-06-10010 June 2010
Inservice Inspection Examination Plan, Rev. 4, Fourth Interval, May 1, 2003 Through May 31, 2012
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1007104442010-03-0404 March 2010
Monticello, Enclosure 2, GE-MNGP-AEP-1687, Rev. 1, GEH Responses to NRC Supplemental Requests 1, 3, and 4
ML0936200242008-12-18018 December 2008
Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate.
ML0915405192008-05-14014 May 2008
Enclosures 1 and 2 - Radioactive Effluent Release Report and Off-Site Radiation Dose Assessment for January 1 - December 31, 2008
ML0805901332008-02-28028 February 2008
U.S. Dept. of Homeland Security/Final Report for the November 6, 2007, Radiological Emergency Preparedness (REP) Full Participation Plume Exposure Pathway Exercise for the Monticello Nuclear Generating Plant/Report
ML0613903922006-06-0808 June 2006
Web References for Monticello Dseis: Aquatic Ecology Part 1
ML0602304312006-01-23023 January 2006
ITS Conversion Beyond Scope Issue 7
ML0520104982005-07-0505 July 2005
Minnesota Department of Natural Resources Web Page 2000 Minnesota Bald Eagle Survey
ML0520104942005-07-0505 July 2005
the Raptor Center (University of Minnesota) - Raptor Facts Bald Eagle
ML0613901282005-06-0808 June 2005
Web References for Monticello Dseis: Terrestrial Ecology
ML0613902252005-06-0808 June 2005
Web References for Monticello Dseis: Water Use/Water Quality
L-HU-05-012, Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 22005-06-0303 June 2005
Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 2
2023-06-21
[Table view] |
Text
ENCLOSURE 1 RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 - DECEMBER 31, 2008
NUCLEAR MANAGEMENT COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Supplemental Information
- 1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases :
5 mrad/quarter gamma radiation 10 mrad/quarter beta radiation B. Long Lived Iodines, Particulates, and Tritium 7.5 mrem/quarter dose to any organ C. Liquid Effluents 1.5 mrem/quarter dose to the total body 5.0 mrem/quarter dose to any organ
- 2. Maximum Permissible Concentrations A. Noble Gases 10 CFR Part 20, Appendix B, Table II, Column 1 B. Long Lived Iodines, Particulates, and Tritium 10 CFR Part 20, Appendix B, Table II, Column 1 C. Liquid Effluents :
10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases
- 3. Average Energy (Not Applicable)
Page 2 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Supplemental Information (continued)
- 4. Measurements and Approximations of Total Radioactivity A. Noble Gases :
Continuous gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams. Weekly isotopic analysis of exhaust streams.
B. Iodines in Gaseous Effluent :
Continuous monitoring with charcoal cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
C. Particulates in Gaseous Effluent Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
D. Tritium in Gaseous Effluent Weekly grab samples from Reactor Building Vent and Plant Stack exhaust streams.
E. Liquid Effluents Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release.
- 5. Batch Releases A. Liquid
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases 0.0 min
- 3. Maximum Time Period for a Batch Release 0.0 min
- 4. Average Time Period for a Batch Release 0.0 min
- 5. Minimum Time Period for a Batch Release 0.0 min
- 6. Average River Flow During Release 0.0 cf/sec B. Gaseous
- 1. Number of Batch Releases 2
- 2. Total Time Period for Batch Releases 1357.0 min
- 3. Maximum Time Period for a Batch Release 996.0 min
- 4. Average Time Period for a Batch Release 678.5 min
- 5. Minimum Time Period for a Batch Release 361.0 min
Page 3 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Supplemental Information (continued)
- 6. Abnormal Releases A. Liquid :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci B. Gaseous :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci
Page 4 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error, %
A. Fission & Activation gases
- 1. Total Release Ci 1. 43E+02 2 . 54E+02 2.0E0l1
- 2. Averaqe Release Rate uci/sec 1. 84E+01 3 . 23E+01
- 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 066.43E-02 1.15E-01 Beta Radiation %_ _ 2.34E-02 3.89E-02 B. Iodines
- 1. Total 1-131 Release Ci 8.45E-04 2.19E-03 1.OOE+01
- 2. Average 1-131 Release Rate uci/sec 1.09E-04 2.79E-04 C. Particulates
- 1. Total Particulates Ci 2.87E-04 1.52E-03 3.OOE+01
- 2. Average Release Rate uci/sec 3.70E-05 1.93E-04
- 3. Gross Alpha Radioactivity Ci 1.14E-06 4.79E-07 D. Tritium
- 1. Total Release Ci 6.05E+00 6.29E+00 1.OOE+01 1 2. Averaqe Release Rate I uci/sec I 7.78E-01 I 7.99E-01 E. Percent Qtrly Tech Spec Reporting Levels
- 1. and Iodines, Tritium Particulates, % 1.34E-01 I 3.69E-01
Page 5 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, %
A. Fission & Activation gases
- 1. Total Release Ci 2.65E+02 3.97E+02 2.OOE+01
- 2. Average Release Rate uci/sec 3.34E+01 5.OOE+0l
- 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation % 1.34E-01 3.07E-01 Beta Radiation %6 3.83E-02 8.06E-02 B. Iodines
- 1. Total 1-131 Release Ci 4.19E-03 5.08E-03 L1.OOE+01
- 2. Average 1-131 Release Rate uci/sec 5.27E-04 6.39E-04 C. Particulates
- 1. Total Particulates Ci 5.88E-04 8.71E-04 3.OOE+01
- 2. Average Release Rate uci/sec 7.40E-05-[ 1.10E-04
- 3. Gross Alpha Radioactivity Ci 5.51E-07 5.78E-07 D. Tritium
- 1. Total Release Ci 9.07E+00 9.87E+00 l1.OOE+01 I 2. Average Release Rate I uci/sec 1 1.14E+00 I 1.24E+00 - I E. Percent Qtrly Tech Spec Reporting Levels
- 1. Iodines, Particulates, and Tritium 5.35E-01 0 .0E+00
Page 6 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table lB Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr I 2nd Qtr 1st Qtr I 2nd Qtr
- 1. Fission Gases KR-85M Ci 4.08E-01 4.22E-01 0.OOE+00 0.OOE+00 KR-87 Ci 2.09E+00 2.47E+00 0.OOE+00 0.OOE+00 KR-88 Ci 1.59E+00 1.74E+00 0.OOE+00 0.00E+00 KR-89 Ci 6.22E+00 1.73E+01 0.00E+00 0.OOE+00 XE-133 Ci 3.64E+01 7.55E+01 0.OOE+00 0.OOE+00 XE-133M Ci 5.77E-01 2.16E+00 0.OOE+00 0.OOE+00 XE-135 Ci 4.94E+00 1.23E+01 0.OOE+00 0.OOE+00 XE-135M Ci 9.03E+00 1.97E+01 0.OOE+00 0.OOE+00 XE-137 Ci 5.16E+01 7.81E+01 0.OOE+00 0.OOE+00 XE-138 Ci 2.66E+01 3.68E+01 0.OOE+00 0.OOE+00 Total for Period Ci 1.39E+02 2.46E+02 0.OOE+00 0.OOE+00
- 2. Iodines 1-131 Ci 4.63E-04 1.13E-03 0.OOE+00 0.OOE+00 1-133 Ci 4.40E-03 1.22E-02 0.OOE+00 0.OOE+00 1-135 Ci 8.13E-03 2.26E-02 0.OOE+00 0.OOE+00 Total for Period Ci 1.30E-02 3.60E-02 0.OOE+00 0.OOE+00
- 3. Particulates CO-60 Ci 6.32E-07 5.61E-07 0.OOE+00 0.OOE+00 BA-140 Ci 5.02E-05 1.01E-04 0.OOE+00 0.OOE+00 SR-89 Ci 1.72E-05 2.63E-06 0.OOE+00 0.OOE+00 SR-90 Ci 1.24E-07 9.68E-09 0.OOE+00 0.OOE+00 Total for Period Ci 6.81E-05 1.04E-04 0.OOE+00 0.OOE+00
Page 7 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table lB Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode-Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr
- 1. Fission Gases KR-85M Ci 4.73E-01 8.02E-01 1.09E-01 0.OOE+00 KR-87 Ci 2.65E+00 4.07E+00 0.OOE+00 0.OOE+00 KR-88 Ci 1.70E+00 2.69E+00 3.76E-02 0.OOE+00 KR-89 Ci 2.91E+01 5.62E+01 0.OOE+00 0.OOE+00 XE-133 Ci 6.77E+01 7.93E+01 2.07E+01 1.33E-02 XE-133M Ci 1.87E+00 2.31E+00 4.01E-01 0.OOE+00 XE-135 Ci 1.08E+01 1.26E+01 3.G6E+00 0.OOE+00 XE-135M Ci 1.17E+01 2.OOE+01 0.OOE+00 0.OOE+00 XE-137 Ci 7.16E+01 1.38E+02 0.OOE+00 0.OOE+00 XE-138 Ci 3.42E+01 5.78E+01 0.OOE+00 0.OOE+00 Total for Period Ci 2.32E+02 3.74E+02 2.49E+01 1.33E-02
- 2. Iodines 1-131 Ci 2.49E-03 1.75E-03 5.64E-07 7.11E-09 1-133 Ci 1.54E-02 1.81E-02 1.60E-06 0.OOE+00 1-135 Ci 2.67E-02 3.39E-02 9.75E-07 0.OOE+00 Total for Period Ci 4.46E-02 *5.37E-02 3.14E-06 7.11E-09
- 3. Particulates CR-51 Ci 3.23E-06 0.OOE+00 0.OOE+00 0.OOE+00 MN-54 Ci 1.35E-07 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 Ci 8.13E-08 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 Ci 1.13E-06 0.OOE+00 0.OOE+00 0.OOE+00 ZN-65 Ci 1.62E-07 0.OOE+00 0.OOE+00 0.OOE+00 NB-95 Ci 4.91E-08 0.OOE+00 0.00E+00 0.OOE+00 CS-137 Ci 3.10E-06 9.85E-08 0.OOE+00 0.OOE+00 BA-140 Ci 1.67E-04 1.81E704 0.OOE+00 0.OOE+00 CE-141 Ci 2.42E-07 7.69E-08 O.OOE+00 0.OOE+00 CE-144 Ci 9.77E-07 1.81E-07 0.OOE+00 0.OOE+00 SR-89 Ci 1.75E-04 6.83E-05 0.00E+00 O.OOE+00 SR-90 Ci 3.41E-07 4.58E-07 O.OOE+00 O.OOE+00 Total for Period Ci 3.51E-04 2.50E-04 O.OOE+00 O.OOE+00
Page 8 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr I 2nd Qtr 1st Qtr I 2nd Qtr
- 1. Fission Gases XE-135 Ci 3.47E+00 5.81E+00 0.OOE+00 0.OOE+00 XE-135M Ci 0.OOE+00 1.73E+00 0.OOE+00 0.OOE+00 Total for Period Ci 3.47E+00 7.54E+00 0.OOE+00 0.OOE+00
- 2. Iodines 1-131 Ci 3.81E-04 1.06E-03 0.OOE+00 0.OOE+00 1-133 Ci 2.55E-03 9.38E-03 0.OOE+00 0.OOE+00 1-135 Ci 0.OOE+00 1.51E-02 0.OOE+00 0.OOE+00 Total for Period Ci 2.93E-03 2.55E-02 0.OOE+00 0.OOE+00
- 3. Particulates CO-60 Ci 7.91E-05 1.22E-04 0.OOE+00 0.OOE+00 CS-137 Ci 9.07E-05 3.91E-05 0.OOE+00 0.OOE+00 BA-140 Ci 2.37E-05 9.76E-05 0.OOE+00 0.OOE+00 SR-89 Ci 2.58E-05 1.15E-03 0.OOE+00 O.OOE+00 SR-90 Ci 0.OOE+00 8.40E-06 0.OOE+00 0.OOE+00 Total for Period Ci 2.19E-04 1.41E-03 0.OOE+00 0.OOE+00
Page 9 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr
- 1. Fission Gases XE-133 Ci 1.49E+00 2.00E+00 0.OOE+00 0.OOE+00 XE-135 Ci 4.22E+00 9.04E+00 0.OOE+00 0.OOE+00 XE-135M Ci 2.94E+00 1.23E+01 0.OOE+00 0.OOE+00 XE-138 Ci 0.OOE+00 2.62E-01 0.OOE+00 0.OOE+00 Total for Period Ci 8.65E+00 2.36E+01 0.00E+00 0.OOE+00
- 2. Iodines 1-131 Ci 1..70E-03 3.33E-03 0.00E+00 O.OOE+00 1-133 Ci 1.19E-02 3.81E-02 0.00E+00 0.OOE+00 1-135 Ci 1.92E-02 9.04E-02 0.OOE+00 O.OOE+00 Total for Period Ci 3.28E-02 1.32E-01 0.OOE+00 0.OOE+00
- 3. Particulates CR-51 Ci 0.OOE+00 2.69E-06 0.OOE+00 0.OOE+00 CO-60 Ci 4.10E-05 4.21E-05 0.OOE+00 0.OOE+00 CS-137 Ci 2.54E-05 3.02E-05 0.OOE+00 0.OOE+00 BA-140 Ci 1.27E-04 4.40E-04 0.OOE+00 0.OOE+00 CE-141 Ci 1.20E-06 6.10E-06 0.OOE+00 0.OOE+00 SR-89 Ci 4.20E-05 9.97E-05 0.OOE+00 0.OOE+00 Total for Period Ci 2.37E-04 6.21E-04 0.OOE+00 0.OOE+00
Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total UnitsError, A. Fission & Activation products
- 1. Total Release (not including tritium, gases, alpha) Ci 0.00E+00 0.OOE+00 0.00E+00 2: Avg Diluted Concentration uci/ml 0.00E+00 0.OOE+00 B. Tritium
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg Diluted Concentration uci/ml 0.OOE+00 0.00E+00_I C. Dissolved and Entrained Gases
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg Diluted Concentration uci/ml 0.00E+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level
- 1. Whole Body Dose % I0.OOE+00 0.OOE+00_
- 2. Organ Dose % 0.OOE+00 0.OOE+00 E. Gross Alpha Radioactivity
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.00E+00 F. Volume of Waste Released Liters 0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used7 Liters I 0.OOE+00 I 0.OOE+00 I 0.00E+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit I1st Qtr. 1 2nd Qtr 1st Qtr I 2nd Qtr None Released This Period
Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2008 Table 2A Liquid Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, '6 A. Fission & Activation products
- 1. Total Release (not including .1 tritium, gases, alpha) Ci 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg Diluted Concentration uci/ml 0.OOE+00 0.OOE+00 B. Tritium
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg Diluted Concentration uci/ml 0.OOE+00 0.0OE+00 C. Dissolved and Entrained Gases
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg Diluted Concentration uci/ml 0.OOE+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level
- 1. Whole Body Dose % I 0.OOE+00 0.OOE+00
- 2. Organ Dose 36 0.OOE+00 0.OOE+00 E. Gross Alpha Radioactivity
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 IF. Volume of Waste Released Liters 0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used7 Liters 0.OOE+00 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr None Released This Period
Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)
- 1. Type of Waste Units 12-month Est. Total Period Error, A. Spent resins, filter sludges, Cu. Meter 1.17E+01 evaporator bottoms, etc. Ci (est) 2.03E+01 3.70E+01 B. Dry compressible waste, Cu. Meter 2.63E+02 contaminated equipment, etc. Ci (est) 9.OOE+00 3.50E+01 C. Irradiated components, Cu. Meter 7.05E+00 control rods, etc. Ci (est) 2.86E+04 3.50E+01 D. Other (describe) Cu. Meter 1.57E+01 Ci (est) l.25E+01 3.50E+01
- 2. Estimate of major nuclide composition (by type of waste)
Type A Type B Type C Type D Nuclide percent percent percent percent H-3 5.56E-01 5.63E-01 3.04E-03 C-14 7.42E-01 7.02E-01 9.49E-03 Cr-51 4. 87E-04 Mn-54 3.83E+00 3.86E+00 1.83E+00 3.18E+00 Fe-55 2.50E+01 2.51E+01 4.56E+01 3.41E+01 Co-58 2.66E-01 2.80E-01 9.39E-02 Fe-59 8.28E-05 Ni-59 1.32E-04 2.55E-02 Co-60 2.94E+01 2.99E+01 4.60E+01 3.76E+01 Ni-63 1.53E+00 1.49E+00 5.38E+00 1.03E+00 Zn-65 3.11E+00 3.23E+00 2.50E-03 4.59E+00 Sr-89 1. 49E-03 Sr-90 5.20E-02 5.61E-02 6.24E-06 Tc-99 5.28E-06 2.50E-05 Agll0m 2.61E-0l ,262E-01 Sb-124 1.OOE-02 9.56E-03 Sb-125 3.50E-02 3.25E-02 Cs-134 1. 39E-04 Cs-137 3.50E+01 3.42E+01 1.12E-04 1.82E+01 Ba-140 1.OOE-03 6.63E-03 Ce-141 2.20E-02 2.46E-02 Ce-144 1.53E-01 1.52E-01 Np-237 5 47E-06 Pu-238 1.OOE-03 1.09E-03 Pu-239 1.OOE-03 1.03E-03 Am-241 5.00E-03 5.28E-03 Pu-241 2.20E-02 2.64E-02 4.24E-05 Cm-242 1.OOE-03 9.78E-04 Cm-243 2.30E-02 1.99E-03
Page 13 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2008 Table 3 Solid Waste and Irradiated Fuel Shipments
- 3. Solid waste disposal Number of Mode of Destination Shipments Transportation 3 Truck Chem-Nuc Inc., Barnwell, SC.
4 Truck Envirocare, Clive, UT.
6 Truck RACE Inc., Memphis, TN.
B. Irradiated Fuel Shipments
- 1. Disposition Number of Mode of Destination ShipmentsI Transportation None This Period C. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 08-06 3.79E+01 1.49E-01 B L N 08-07 5.89E+01 2.40E-01 B L N 08-15 5.83E+00 8.48E+00 A L D 08-11 4.26E+01 4.75E-03 B L N 08-13 5.83E+00 8.51E+00 B L D 08-18 3.78E+00 8.92E+01 C B N 08-21 1.64E+00 1.27E+04 C B N 08-31 1.64E+00 1.58E+04 C B N 08-38 5.89E+01 4.92E-02 B L N 08-59 4.70E+00 1.25E+01 D A N 08-62 1.10E+01 1.09E-02 D L N 08-66 5.89E+01 4.81E-02 B L N 08-69 5.83E+00 1.18E+01 A L D Waste type Codes : Container Codes Solidification Codes A - Spent resins, sludges L - LSA C - Cement B - Dry waste, equipment A - Type A U - Urea Formaldehyde C - Irradiated components B - Type B D - Dewatering D - Other (describe) Q - Large Quantity N - Not Applicalble
Table 5.3 MISSED COLLECTIONS AND ANALYSES All required samples were collected and analyzed as scheduled with the following exceptions:
Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, M-02 5/28/2008 Sampler pump failure, Sampler pump was 1-131 open fuse. replaced.
AP/AI Beta, M-05 7/9/2008 Sampler pump failure, Sampler pump was 1-131 sampler head leakage. replaced.
Ml Gamma, M-28 4/9/2008- Hoglund Farm no longer Pasture grass collections 1-131 12/31/2008 in the dairy business, were initiated at locations M-41, M-42, M-43 in Sept. 2008 TLD Ambient M-01B 1st. Qtr. Missing in the field None required.
Gamma 2008 TLD Ambient M-01S 2nd. Qtr. Missing in the field None required.
Gamma 2008 TLD Ambient M-01S 4th. Qtr. Missing in the field None required.
Gamma 2008 BO Gamma M-08, Oct., 2008 Collection missed due to None required.
M-09 unsafe river conditions.
SW Surface Water M-08 Jan, Feb, Mar, Missed due to unsafe ice. None required.
Gamma 2008 M-08 Dec, 2008 Three of five weekly samples None required.
missed due to unsafe ice.
14
ENCLOSURE 2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1,- DECEMBER 31, 2008
MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2008 An assessment of radiation dose due to releases from the Monticello Nuclear'Generating Plant during 2008 was performed in accordance with the Offsite Dose Calculation Manual (ODCM). Computed doses were well below the 40 CFR 190 Standards and 10 CFR Part 50, Appendix I Guidelines.
Offsite dose calculation formulas and meteorological data from the Offsite Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Radioactive Effluent Release Report for 2008.
Offsite Dose from Gaseous Releases (ODCM -08.01 section 2.1.3)
Computed dose due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ dose are reported in Table 2. Whole body and organ dose due to gaseous releases are a small percentage of Appendix I Guidelines.
Offsite Dose From Liquid Releases (ODCM -08.01 section 2.1.3)
Dose from liquid releases are listed in Table 1.
Dose to Individuals Due to Their Activities Inside the Site Boundary (ODCM -08.01 section 2.1.3)
Computed dose to the whole body, skin and organ (thyroid), are reported in Table 1. There are several groups of concern, Security Officers training at the rifle range at the old EPA station, cleaning contractors atthe new Receiving Warehouse and XCEL Energy Company transmission and distribution crews working in the substation. Use of a very conservative assumption of 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/week spent inside the site boundary by these groups would conservatively represent the most exposed individual. The annual whole body, skin and organ dose was computed using plant stack and reactor building vent X/Q and D/Q values for the Substation (a bounding location due to predominant wind direction and nearness to the release points) as input to the GASPAR code. This computed dose was reduced by the factor of 40/168 to account for limited occupancy.
Page I of 5
Dose to the Likely Most Exposed Member of the General Public from Reactor Releases and Other Nearby Uranium Fuel Cycle Sources (ODCM -08.01 section 2.1.4)
There are no other uranium fuel facilities in the vicinity of the Monticello site. The only artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactor and the steam turbines.
An Independent Spent Fuel Storage Facility (ISFSI) was constructed west of the plant in 2007. Preoperational monitoring for gamma and neutron dose has been completed. The initial loading campaign was completed in 2008 with 10 HCM's loaded with spent fuel.
Environmental TLDs were used to provide data on direct and skyshine radiation dose and the GASPAR code was used to provide data on dose from airborne pathways.
TLD results from the area of the site boundary and the 5 mile ring show no significant differences between these TLD's and the control TLD's.
Therefore, the likely most exposed member of the general public will not receive an annual radiation dose from reactor effluent releases and all other fuel cycle activities in excess of 40 CFR 190 standards of 25 millirem to the whole body, 75 millirem to the thyroid, and 25 millirem to any other organ.
Changes in Land Use-and Non Obtainable Milk or Vegetable Samples (ODCM -08.01 sections 2.1.8 and 2.1.9)
There were no changes in land use resulting in significant increases in calculated doses. Milk samples were unavailable at sample location M-28 (Hoglund Farm) after 4/09/08 due to the farm going out of business. Land use census results show that there were no other indicator sample locations to replace this farm. As a result of the last dairy farm going out of business, control milk samples at location M- 10 were discontinued at the end of 2008. Vegetation sampling was initiated at locations M-41, M-42 and M-43 in September 2008 as a replacement for milk sampling.
Page 2 of 5
Table 1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31,2008 Maximum Site Boundary (amma Air Dose (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.018 (mrad/year) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.084 15 Maximum Doseto the Likely Most Exposed Member of the General Public (mrem/year)
Whole Body 0.036 5 Skin 0.035 15 Max Organ (Thyroid) 0.084 15 Maximum Off-Site Dose (mrem)
Whole Body 0.00 3 Thyroid 0.064 75 Max Other Organ (Skin) 0.048 25 Page 3 of 5
Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2008 Mviaximum bite bounclary Dose Location (from Reactor Building Vents)
Sector SSE Distance (miles) 0.40 Substation Sector S Distance from Plant Stack (miles) 0.2 Distance from Reactor Building Vents 0.2 Critical Receptor Location Sector SSW Distance from Reactor Building Vents (miles) 0.64 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ THYROID St. Paul Drinking Water Intake Location Pathways Drinking Water Drinking Water, Fish Age Group Infant Adult Organ Whole Body GI Tract Dilution Factor (drinking water) 7:1 7:1 Page 4 of 5
Bases for Radiation Dose Statements Thermoluminescent dosimeters (TLD) are stationed around MNGP to measure the ambient gamma radiation field. Monitoring stations are placed near the site boundary and approximately five (5) miles from the reactor, in locations representing sixteen (16) compass sectors. Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places and population centers. Control sites are located further than ten (10) miles from the site, in areas that should not be affected by plant operations. The
-results from the TLD's are reported in the Annual Radiological Environmental Monitoring Report (REMP).
The results from this effortindicated no excess dose to offsite areas.
Additionally, NUREG-0543, METHODS FOR DEMONSTRATING LWR COMPLIANCE WITH THE EPA URANIUM FUEL CYCLE STANDARD (40 CFR PART 190) states in section IV, "As long as a nuclear plant site operates at a level'below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with 40 CFR Part 190". The organ and whole body doses reported in Table 1 are determined using 10 CFR 50 Appendix I methodology. The doses reported are well below the limits of Appendix I.
Page 5 of 5
