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Category:Environmental Monitoring Report
MONTHYEARML23128A1092023-05-0808 May 2023 Independent Spent Fuel Storage Installation - 2022 Annual Radiological Environmental Monitoring Program Report ML23128A0922023-05-0808 May 2023 2022 Annual Radioactive Effluent Report ML23053A1572023-02-16016 February 2023 Independent Spent Fuel Storage Installation - Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 2022 ML22130A1472022-05-10010 May 2022 2021 Annual Radiological Environmental Monitoring Program Report ML22130A3882022-05-10010 May 2022 2021 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML22049B5442022-02-18018 February 2022 Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 2021 ML21134A0052021-05-14014 May 2021 2020 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML21039A6392021-02-0808 February 2021 Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 2020 ML20136A0162020-05-15015 May 2020 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML20049C5192020-02-18018 February 2020 Screenshots/Referenced Used in Environmental Assessment Prepared for the Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation (Dkt No. 72-10) ML18134A0122018-05-14014 May 2018 2017 Annual Radiological Environmental Monitoring Program Report ML17130A9692017-05-0808 May 2017 Submittal of 2016 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML17130A9542017-05-0808 May 2017 Independent Spent Fuel Storage Installation - 2016 Annual Radiological Environmental Monitoring Program Report L-PI-17-008, Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 20162017-02-22022 February 2017 Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 2016 L-PI-16-037, Transmittal of 2015 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2016-05-0505 May 2016 Transmittal of 2015 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual L-PI-16-038, ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report2016-05-0505 May 2016 ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report L-PI-16-014, ISFSI - Annual Effluent Report, January Through December 20152016-02-26026 February 2016 ISFSI - Annual Effluent Report, January Through December 2015 L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report2015-05-11011 May 2015 ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report L-PI-15-038, 2014 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)2015-05-0505 May 2015 2014 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM) ML14175B1932014-05-0909 May 2014 Enclosure 2 - Annual Radioactive Effluent Report Supplemental Information, January 1, 2013 - December 31, 2013 L-PI-14-043, Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report2013-12-31031 December 2013 Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report L-PI-13-037, Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)2013-05-0303 May 2013 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM) L-PI-13-042, Independent Spent Fuel Storage Installation - 2012 Annual Radiological Environmental Monitoring Program (REMP) Report2013-05-0303 May 2013 Independent Spent Fuel Storage Installation - 2012 Annual Radiological Environmental Monitoring Program (REMP) Report ML13133A2472012-12-31031 December 2012 Xcel Energy Corp Prairie Island Nuclear Generating Plant Annual Report to NRC, Radiological Environmental Monitoring Program January 1 to December 31, 2012 ML12135A2882012-05-11011 May 2012 Independent Spent Fuel Storage Installation - Submittal of 2011 Annual Radiological Environmental Monitoring Program (REMP) Report L-PI-11-040, Independent Spent - 2010 Annual Radiological Environmental Monitoring Program (REMP) Report2011-05-12012 May 2011 Independent Spent - 2010 Annual Radiological Environmental Monitoring Program (REMP) Report L-PI-11-036, 2010 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)2011-05-12012 May 2011 2010 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM) L-PI-11-009, Independent Spent Fuel Storage Installation Annual Effluent Report, January Through December 20102011-02-24024 February 2011 Independent Spent Fuel Storage Installation Annual Effluent Report, January Through December 2010 ML1013803022010-05-12012 May 2010 Independent Spent Fuel Storage Installation, Submittal of 2009 Annual Radiological Environmental Monitoring Program Report L-PI-10-028, Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM)2010-05-12012 May 2010 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM) L-PI-10-011, Independent Spent Fuel Storage Installation - Submittal of Annual Effluent Report, January Through December 20092010-02-25025 February 2010 Independent Spent Fuel Storage Installation - Submittal of Annual Effluent Report, January Through December 2009 L-PI-09-103, Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report2009-10-0707 October 2009 Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report L-PI-09-058, Submittal of 2008 Annual Radiological Environmental Monitoring Program (REMP) Report, Technical Specification) 5.6.2, Appendix a2009-05-13013 May 2009 Submittal of 2008 Annual Radiological Environmental Monitoring Program (REMP) Report, Technical Specification) 5.6.2, Appendix a L-PI-09-055, 2008 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2009-05-12012 May 2009 2008 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML0833802242008-12-0303 December 2008 PINGP - SEIS Reference - NOAA Regional Climate Centers 2008e ML0834001502008-12-0202 December 2008 PINGP License Renewal: EPA Office of Solid Waste. Refer. 2008f L-PI-08-027, Nuclear Management Company, Inc. 2007 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2008-05-13013 May 2008 Nuclear Management Company, Inc. 2007 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual L-PI-08-033, 2007 Annual Radiological Environmental Monitoring Program (REMP) Report2008-05-13013 May 2008 2007 Annual Radiological Environmental Monitoring Program (REMP) Report L-PI-07-033, 2006 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2007-05-14014 May 2007 2006 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual L-PI-07-035, 2006 Annual Radiological Environmental Monitoring Program (REMP) Report2007-05-0707 May 2007 2006 Annual Radiological Environmental Monitoring Program (REMP) Report L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report2006-05-0606 May 2006 Annual Radiological Environment Environmental Monitoring Program (REMP) Report ML0612800402006-05-0505 May 2006 2005 Annual Radiological Environmental Monitoring Program (REMP) Report ML0613700962005-12-31031 December 2005 Off-Site Radiation Dose Assessment for January 01, 2005 - December 31, 2005 L-PI-05-046, Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2005-05-16016 May 2005 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual L-PI-05-043, SNM-2506 - 2004 Annual Radiological Environmental Monitoring Report2005-05-12012 May 2005 SNM-2506 - 2004 Annual Radiological Environmental Monitoring Report L-PI-04-061, Annual Radiological Environmental Monitoring Report2004-05-14014 May 2004 Annual Radiological Environmental Monitoring Report ML0414205042003-12-31031 December 2003 2003 Annual Radioactive Effluent Report for Prairie Island Nuclear Generating Plant Units 1 and 2 L-PI-03-051, 2002 Annual Radiological Environmental Monitoring Report for Prairie Island Nuclear Generating Plant2003-05-15015 May 2003 2002 Annual Radiological Environmental Monitoring Report for Prairie Island Nuclear Generating Plant ML0037146542000-05-0404 May 2000 Annual Radiological Environmental Monitoring Report 2023-05-08
[Table view] Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
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U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42, DPR-60 2004 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual Pursuant to the applicable Prairie Island Nuclear Generating Plant Technical Specifications (TS), Appendix A to Operating Licenses DPR-42 and DPR-60, and the requirements of the Offsite Dose Calculation Manual (ODCM), the Nuclear Management Company, LLC (NMC) by this letter submits the 2004 Annual Radioactive Effluent Report which comprises the following reports: contains the Off-Site Radiation Dose Assessment for January through December 2004 in accordance with the requirements of the ODCM; contains the Annual Radioactive Effluent Report, Supplemental Information, Revision 0, for the period January I , 2004 through December 31, 2004 in accordance with the requirements of TS 5.6.3 and the ODCM; and contains the Effluent and Waste Disposal Annual Report, Solid Waste and Irradiated Fuel Shipments, in accordance with the requirements of TS 5.6.3 and the ODCM.
TS 5.5.1 .c requires submittal of a complete copy of the entire ODCM and a summary of changes to the ODCM, when there are changes. The ODCM has not been changed since 2003 and the current revision was submitted last year. Hence, no copy of the ODCM is being submitted.
1717 Wakonade Drive East a Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
Document Control Desk Page 2 Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
Generating Plant Units 1 and 2 Enclosures (3) cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Tim Donakowski, State of Minnesota
ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT FOR January throunh December 2004 (8 pages follow)
An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2004 was perfonned in accordance with the Offsite Dose Calculation Manual as required by Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Off-site dose calculation formulas and meteorological data fi-om the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report prepared for NRC review for the year of 2004.
Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Gaseous release doses are a small percentage of Appendix I Guidelines.
Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guidelines.
Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off-shore from the plant buildings (ESE at 0.2 miles). The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine 131, Iodine-133, tritium and long-lived particulates were calculated for this location and occupancy time. These doses are reported in Table 1.
- 1. Uncontrolled release of gases from vent header into Auxiliary Building:
From June 21-24, 2,430 cubic feet of vent header gases were released into the Auxiliary Building during maintenance activities. A control valve used for isolation leaked. The release was via the Auxiliary Building normal ventilation system. There was no detectable activity on grab samples collected in the area of the leak and there was no detectable increase on the applicable radiation stack monitors.
Cause: Leaking valve.
Corrective Based on gas decay tank activity, the radioactive gases released totaled:
Action:
Kr 5.65E+04 uCi Xe-133 - 5.83E+02 uCi Based on the conservative assumption that the gas was released evenly, out the unit's stack over the entire period of release, the dose off site as a result of this release was:
Gamma Dose - 1.26E-06 mRad Beta Dose - 1.19E-04 mRad Release files RACO 115 and RACO 116 were created to document this release.
Result: The dose from the activity released represented a small percentage of the total dose and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.
The event was captured in the site's Action Request Process, CAP-037271 The event was reported to the NRC Region 3 Radiation Protection (RP) Inspector, at the time of the event.
- 2. Uncontrolled release of gases from Chemical Volume Control System due to relief valve leak:
From June 25-30, 16,350 cubic feet of vent header gases were released while diverting to 121 Chemical and Volume Control System (CVCS) Holdup Tank during a down power evolution. A relief valve on the 121 CVCS Holdup Tank leaked. Release from the plant was via the Auxiliary Building normal ventilation system. There was no detectable activity on grab samples collected in the area of the leak and there was a slight increase (10-15 CPM) above background on the applicable radiation stack monitors.
Cause: Leaking relief valve Corrective Based on gas decay tank analysis, the radioactive gases released totaled:
Action:
Kt- 3.80E+05 uCi Xe- 133 - 3.92E+03 uCi Based on the conservative assumption that all the gases escaped evenly out a single units vent stack over the entire period of the release the dose off site as a result of this release was:
Gamma Dose - 8.47E-06 mRad Beta Dose - 7.09E-04 rnRad Release files RAC0137 and RAC0138 were created to document this release.
Result: The dose from the activity released represented a small percentage of the total dose and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.
The event was captured in the site's Action Request Process CAP-037309.
The event was reported to the NRC Region 3 RP Inspector at the time of the event.
- 3. Temporary filter installed in Spent Fuel Pool exhaust without tritium monitor:
A high efficiency particulate air filter (HEPA) unit installed by RP in the Spent Fuel Pool (SFP) area discharged outside the SFP and did not measure or account for the tritium released. The Chemistry department was not informed of the ventilation change and there were no samples collected for the airborne tritium removed from the SFP area IAW the ODCM, Table 3.1. The HEPA was in place from Aug 13,2004 at 07:OO through Sep 08,2004 at 17:08.
Cause: RP was unaware of the requirement and did not contact the Chemistry department, who is responsible for the effluent requirements and would have ensured the required samples were collected.
Corrective Action: The period of release was conservatively determined to be the entire period of Aug 13, 04 07:OO to Sep 08,04 17:08.
Tritium activity was based on SFP Normal Ventilation routine measurements.
Hours were adjusted in the release files, to compensate for the difference in flow of the HEPA and SFP Normal Ventilation.
Release files RAC0167, RAC0168, RAC0169, RAC0170 and RAC0175 were created to document this release.
RP was counseled on this issue.
Result: The dose from the activity released represented a small percentage of the total dose, and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.
The event was captured in the site's Action Request Process, CAP-038133.
The event was reported to the NRC Region 3 RP Inspector, at the time of the event.
- 4. Inadequate controls of airflow from Unit 1 Containment while equipment hatched removed:
Between September 18,2004 and September 22,2004, there was a period of 27.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> when the Unit 1 Equipment Hatch was removed, with no Inservice Purge or Large Containment Purge fans in service.
One train of Shield Building Ventilation and Shield Building Recirculation Fans were providing ventilation to the Shield Building, exhausting to the Shield Building Exhaust Stack.
During periods when the West Fuel Receipt Rollup Door was opened and certain weather conditions existed, it is believed that movement of air may have been out of containment.
Cause: Control of the roll-up door was not considered for its potential impact on containment air flow.
Corrective All air samples collected in the vicinity of the Equipment Hatch were reviewed. Only Actions: one particulate filter had activity. The air sampler was an AMS-4, located at the hatch, just inside the hatch. Activity was 1.5E-12 uCi/cc Co-58 and 3.7E-14 uCi/cc Nb-95.
This activity was assigned to the release. Tritium level, for the release, was assigned based on silica gel tritium sampling for Unit 1 Shield Building Stack.
A release file (RAC0236) was created for Effluent Surveillance Week 37, to document the release. The conservative estimates of a release flow rate of 1000 CFM, a release duration of 27.6 were used in calculating release volume. Release volume was 4.69E+10 cc. Conservative maximum activity and maximum off site dose are calculated as follows:
Co-58 7.03E-02 uCi 9.78E-08 mRem Nb-95 1.74E-03 uCi 1.35E-09 rnRem H-3 5.77E+02 uCi 1.03E-06 mRem Total 1.13E-06 mRem Additional controls were placed on the roll up door, during outage.
Result: The dose from the activity released represented a small percentage of the total dose and were a very small percentage of limits. The dose did not impose upon the health and safety of the public.
The event was captured in the site's Action Request Process, CAP-038784.
The event was reported to the NRC Region 3 RP Inspector, at the time of the event.
The calculated dose from the release of radioactive materials in liquid or gaseous effluents d U m t exceed twice the limits of IOCFRSO, Appendix I, therefore compliance with 40CFR190 i s .required to be assessed, in this report.
The minimum sampling frequency, minimum analysis frequency and lower limit of detection (LLD) requirements, as specified in ODCM Tables 2.1 and 3.1 H Yexceeded.
There yverew occurrences when less than the minimum required radioactive liquid andlor gaseous effluent monitoring instrumentation channels were operable as required by ODCM Tables 2.2 and 3.2.
No fuel casks were loaded and placed in the storage facility during the 2004 calendar year. The total number of casks in the ISFSI is seventeen. There has been no release of radioactive effluents from the ISFSI.
The Offsite Dose Calculation Manual was revised in 2004. The current revision is 18. The revision date is June 26,2003. A copy was submitted with last year's report.
There were changes made to the Process Control Program in 2004. Current manual is revision 8, August 8, 1999.
Table 1 OFF-SITE RADIATION DOSE ASSESSPENT - PRAIRIE ISLAND PERIOD: JANUARY through DECEMBER 2004 10 CFR Part 50 Appendix I Guidelines for a 2-unit site per year Gaseous Releases Maximum Site Boundry Gamma Air Dose (mrad)
Maximum Site Boundry Beta Air Dose (mrad)
Maximum Off-site Dose to any organ (mrem)*
Offshore Location Gamma Dose (mrad)
Total Body (mrem)*
Organ (mrad)*
Liquid Releases Maximum Off-site Dose Total Body (mrem) 1.873-03 Maximum Off-site Dose Organ - GI TRACT (mrem) 4.813-03 Limiting Organ Dose Organ - TOTAL BODY (mrem) 1.873-03
- Long-Lived Particulate, 1-131, 1-133 and Tritium
Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANIIARY t h r o u g h -
Maximum Site Boundary Dose Location (From Building Vents)
Sector Distance (miles)
Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways Plume, Ground, Inhalation, Vegetables Age Group Child Maximum Off-site Dose Location Downstream Pathway Fish
ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT 01JAN-04 THROUGH 31-DEC-04 SUPPLEMENTAL INFORMATION (8 pages follow)
2004 Annual Radioactive Effluent Report REV. 0 Page 1 of 8 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-04 THROUGH 31-DEC-04 SUPPLEMENTAL INFORMATION Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits
- 1. Liquid Effluents:
- a. The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:
for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ
- 2. Gaseous Effluents:
- a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:
noble gases 5 500 mrem/year total body 53000 mrem/year skin 1-131, 1-133, H-3, LLP 51500 mrem/year to any organ
- b. The dose due to radioactive gaseous effluents released from the site shall be limited to:
noble gases 510 mrad/quarter gamma (20 mrad/quarter beta S20 mrad/year gamma (40 mrad/year beta 1-131, 1-133, H-3, LLP (15 mrem/quarter to any organ (30 mrem/year to any organ
2004 Annual Radioactive Effluent Report Rev. 0 PAGE 2 B. Water Effluent Concentration
- 1. Fission and activation gases in gaseous releases:
10 CFR 20, Appendix B I Table 2, Column 1
- 2. Iodine and particulates with half lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B I Table 2, Column 1
- 3. Liquid effluents for radionuclides other than dissolved or entrained gases:
10 CFR 20, Appendix B, Table 2, Column 2
- 4. Liquid effluent dissolved and entrained gases:
2.OE-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.
D. Measurements and approximations of total activity
- 1. Fission and activation gases Total Gem +25%
in gaseous releases: Nuclide Gem
- 2. Iodines in gaseous releases: Total Gem +25%
Nuclide Gem
- 3. Particulates in gaseous releases: Total Gem +25%
Nucl ide Gem
- 4. Liquid effluents Total Gem +25%
Nuclide Gem E. Manual Revisions
- 1. Offsite Dose Calculations Manual latest Revision number: 18 Revision date : 6/26/03
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2004 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 6 TABLE 1A L I Q U I D EPFLUEHTS - SUHHATIOU OF ALL RELEASES I QTR: 01 1 QTR: 02 1 QTR: 03 1 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 17.0 VOLUME OF DILUTION WATER (LITERS) 18.0 P I S S I O U AUD ACTIVATIOU PRODUCTS 18.1 TOTAL RELEASES W/O H-3, RADGAS, ALPHA (CI) 18.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 19.0 TRITIUW 19.1 TOTAL RELEASE (CI) 19.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 20.0 D I S S O L V E D AUD EUTRAIUBD GASES 20.1 TOTAL RELEASE (CI) 20.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 21.0 GROSS ALPHA (CI) 22.0 TOTAL TRITIUM, FISSION 6 ACTIVATION PRODUCTS (UCI/ML) 23.0 TOTAL BODY DOSE (MREM) 24.0 C R I T I C A L ORGAN 24.1 DOSE (MREM) 1.26E-03 4.95E-04 5.733-04 2.383-03 24 - 2 ORGAN G I TRACT TOT BODY TOT BODY GI TRACT 25.0 PERCENT OF TECHNICAL SPECIFICATIONS LIMIT ( % )
26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT ( % )
2004 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 7 TABLE 21 L I Q U I D EFPLUERTS - SUIIIUTIOII OP ALL RELEASES (CI) 27.0 IHDIVIDUAL L I Q U I D EPPLUBUT CONTINUOUS MODE BATCH MODE I I QTR: 01 /
I QTR: 02 II QTR: 03 1 I
QTR: 04 1 I
QTR: 01 /
I QTR: 0 2 /
I QTR: 03 1 I
QTR: 04 I I
AG-108M CI 6.39E-06 AG-11OM CI 1.353-03 2.553-04 1.09E-04 1.31E-03 BE-7 CO-5 7 C1 CI
- c. 2.14E-06 6.803-07 3.093-06 7.463-06 1.24E-04 CO-58 CI 1.58E-05 1.03E-03 1.973-04 4.06E-03 3.053-02 CO-6 0 CI 3.363-04 8.43E-05 1.78E-04 6-943-04 c
I I I I 1 CR-51 CI 1.41E-04 7.31.-06 9.278-04 1-1OE-03 CS-137 CI 1.6 0E-06 FE-55 CI 1.293-05 4.35E-03 3.263-03 3.29E-03 2.693-02 FE-5 9 CI 7.773-05 6.453-06 1.15E-05 7.193-04 MN-54 CI 4.60E-06 3.443-06 5.35E-05 NA-24 NB- 9 5
=I CI c
I I I I I 4.703-06 4.44E-06 3.11E-04 NB-97 SB-122 C1 CI
/ 6*54E-07 1.12E-06 1.623-05 3.773-06 2.083-06 SB-124 CI 3.393-04 1.34E-04 6.78E-06 1.663-03
- I SB-125 CI 3.123-03 1.30E-03 8.79E-04 4.943-03 1
SN-113 3.003-05 SR-9 2 2.79E-05 3.29E-06 2.03E-06 2.123-05 TE-123M CI 3.34E-04 2.163-05 3.65E-05 3.56E-04 TE-125M CI 8.90E-03 6.543-05 1.31E-02 I I TE-132 CI 4.66E-06 ZR-95 CI 4 -708-06 1.71E-04 TOTALS CI 2.00E-02 5-273-03 9.613-03 8.203-02
2004 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 8 TABLE PA L I Q U I D EFFLUEHTS - SUllMATIOIW OF ALL RELEASES (CI) (COIWTIIOUED) 28.0 DISSOLVED AlsD EBTRAIIOBD GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 03 QTR: 04 QTR: 01 QTR: 02 QTR: 03 QTR: 04 I I I I I I I I I I I I XE-133 CI 1.223-04 4.183-04 5.303-05 XE-133M XE-135 TOTALS CI CI CI c.
I 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
3.283-06 1.26E-04 4.563-05 4.643-04 3.423-06 5.643-05
ENCLOSURE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (7 pages follow)
PlNGP 753, Rev. 7 Page 1 of 7 Retention: Life PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: OI/OI/O~-12/31/04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
- 1. Solid Waste Total Volumes and Total Curie Quantities:
C. Non-Compacted m' 4.35E+02 1280 ft3 1.54E+04 Ci 3.41E-01 2.50E+01 D. Filter Media m3 ft3 Ci S. Other (furnish description) m3 4.79E+02 4071 Old Steam Generators ft3 1.69E+04 4384 Ci 1.25E+03 2.50E+01 and activity of the low-level waste leaving the Prairie Island site.
ance is made for off-site volume reduction prior to H:\word~documents\Documents\2004PlNGP 753.dot
PlNGP 753, Rev. 7 Page 2 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 2. Principal Radionuclide Composition by Type of Waste:
(Bold letter designation from Page 1)
TYPE Percent %
Abundance Nuclide
- = Inferred - Not Measured on Site
PlNGP 753, Rev. 7 Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 2. Principal Radionuclide composition by Type of Waste (Continuation):
(Bold letter designation from Page 1)
TYPE Percent %
Abundance (O.OOE0)
- = Inferred - Not Measured on Site
PlNGP 753, Rev. 7 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 3. Solid Waste Disposition:
Number of Shipments Mode Destination RACE Logistics RACE, LLC Canadian Pacific Envirocare of Utah Railroad Perkins Envirocare of Utah
PlNGP 753, Rev. 7 Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 4. Shipping Container and Solidification Method:
Disposal No. Volume Activity Type of Container Solidif.
(~t~lrn~) (Ci) Waste Code Code 43841124.14 8.38E+02 S DOT-E 13401 NIA 43841124.14 4.14E+02 DOT-E 13401 NIA 40711115.28 NIA 407111 15.28 NIA NIA NIA NIA TOTAL 10 3230019 14 1250.34 CONTAINER CODES: L - LSA (Shipment type) A -- TYpe A B - Type B Q - Highway Route Controlled Quantity SOLIDIFICATION CODES: C - Cement TYPES OF WASTES: A -- Resins B -- Dry Compacted C - Non-Compacted D - Filter Media S - Other
PlNGP 753, Rev. 7 Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Mode Destination 0
PlNGP 753, Rev. 7 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-04112-31-04 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE: Process Control for SolidificationIDewateringof Radioactive Waste from Liquid Systems Current Revision Number: 8 Effective Date: 812511999 ChangesIJustification: NIA