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Category:Report
MONTHYEARML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion RA-22-0165, Inservice Inspection Program Owners Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owners Activity Report for Refueling Outage 24 RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16041A4352016-03-0101 March 2016 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 ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes 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 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 2024-02-22
[Table view] Category:Technical
MONTHYEARRA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. 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 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 ML12076A0632012-02-17017 February 2012 Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031 ML12076A0642012-02-17017 February 2012 Areva Document No. 51-9177315-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 11 to BSEP 12-0031 ML12076A0852012-02-17017 February 2012 Areva Document No. 51-9177314-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology, Enclosure 14 to BSEP 12-0031 ML12076A0862012-02-17017 February 2012 Areva Document No. 51-9177316-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 17 to BSEP 12-0031 BSEP 12-0040, ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis.2011-12-31031 December 2011 ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis. ML12100A0872011-05-31031 May 2011 ANP-2989(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR2011-03-31031 March 2011 Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR ML1111010202011-03-24024 March 2011 Reactor Pressure Vessel Flaw Evaluation BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars.2010-12-16016 December 2010 ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20.2010-10-12012 October 2010 ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. ML1019305492010-01-20020 January 2010 Impact of Tritium Leak on Public BSEP 09-0034, Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 20092009-01-31031 January 2009 Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 2009 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0909702482008-07-31031 July 2008 Enclosure 4 and 6 to BSEP 09-0034 - ANP-2729(NP), Rev. 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, and Areva Affidavit Withholding ANP-2727(P), Rev. 0 Form Public Disclosure ML0909702462008-06-30030 June 2008 Enclosure 7 and 9 to BSEP 09-0034 - ANP-2727(NP), Rev. 0, Brunswick, Unit 2, Cycle 19 Fuel Cycle Design, and Areva Affidavit Re Withholding ANP-2771(P), Rev. 0 from Public Disclosure BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel.2007-09-30030 September 2007 ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel. ML0728402192007-09-30030 September 2007 ANP-2642(NP), Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM-10 Fuel. ML0721803722007-07-31031 July 2007 Areva Report ANP-2658(NP), Revision 0, Brunswick Unit 1 Cycle 17 Fuel Cycle Design, Enclosure 3 BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 62007-07-31031 July 2007 Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6 2022-05-25
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Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Prepared by: Date Heather Baxter Groundwater Program Lead
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Mike Robinson Superintendent Reviewed by: Don Edwards, Contractor Mike Millinor, Brunswick Nuclear Power Plant Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page I K/AS
.. I Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Heather Baxter and Don Edwards Summary:
In 2009, the buried Cooling Tower Blowdown Line was discovered to be releasing water containing tritium into the surrounding soil. All of the leaking water and plume is contained within the site boundary, and based on studies performed by an independent hydrologist, offsite migration is not anticipated. A bounding estimate of the dose to a hypothetical individual member of the public was performed. In this theoretical calculation, if a child was to ingest a full year of drinking water from the Cooling Tower Blowdown Line they would receive 2.14 mrem total body dose. Since 2.14 mrem total body dose is less than the 10CFR50 Appendix I limits of 3 mrem total body, the hypothetical exposure would not violate any regulatory limits.
impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 2
On April 1, 2009, a hydrology study, conducted as part of the voluntary Industry Groundwater Protection Initiative, revealed that the buried Cooling Tower Blowdown Line was releasing water containing tritium into the surrounding soil. The maximum tritium activity level discovered was 2,120 picocuries per liter (pCi/L). Since the pipe is buried, the leak rate could not be determined; but appeared to be small.
According to Regulatory Guide 1.21 Revision 1 "Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases or Radioactive Material in Liquid and Gaseous Effluents from Light-Water-CooledNuclear Power Plants" the information on the identity and quality of radionuclides is needed to ascertain whether regulatory limits have been exceeded.
While Reg Guide 1.21 Rev 1 discusses abnormal release pathways it does not address monitoring for a leak or spill. Regulatory Guide 1.21 was recently revised (Reg Guide 1.21 Revision 2) and includes guidance for monitoring leaks and spills. While Harris Nuclear Plant is not committed to the actions and statements in Reg Guide 1.21 Rev 2, this document provides a framework to address the impact of the Cooling Tower Blowdown Line leak.
The first element in Regulatory Guide 1.21 Rev 2 Section 1.5 is to obtain the necessary information for the Annual Radioactive Effluent Release Report.
"Leaks or spills to the ground will be diluted on contact with soil and water in the environment. Samples of the undiluted liquid (from the source of the leak or spill) and samples of the affected soil (or surface water or groundwater) should be analyzed." (RG 1.21 Rev 2 Sec 1.5 page 11)
The Cooling Tower Blowdown Line is used for liquid effluent dilution as part of permitted radioactive releases. The permitted liquid effluent release point is the discharge from the.Cooling Tower Blowdown Line into Harris Lake. The concentration of the water inside the Cooling Tower Blowdown Line varies depending upon permitted radioactive releases, secondary waste discharges, and the concentration of tritium in Harris Lake. For 2008 the annual average tritium concentration of the undiluted liquid from the source of the leak was 20,516 pCi/L.
During the hydrogeologic evaluation of the impacted area, soil, surface water, and vegetation samples were obtained. The soil samples were analyzed for gamma emitters by the Harris Nuclear Plant Count Room to the environmental lower limit of detection. Only naturally occurring, non plant related, gamma emitters were identified, consistent with background radiation. The surface water samples were analyzed for tritium by the Harris Energy and Environmental Center to an a priori lower limit of detection of 250 pCi/L. The concentration of tritium was less than the lower limit of detection. Finally, vegetation i.e. grass, weeds, tree leaves, were analyzed for tritium by General Engineering Lab to a minimum detectible concentration of 250 pCi/kg and no tritium was detected, indicating there was little plant uptake of the contaminated liquid.
Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 3
The second element in Regulatory Guide 1.21 Rev 2 Section 1.5 is to identify the extent of the plume.
"The location and estimated volume of the leak or spill should be recorded to identify the extent of the impacted area and predict size or extent of the contaminated plume". (RG 1.21 Rev 2 Sec 1.5 page 11)
The leak is located onsite, on a peninsula, surrounded on three sides by Harris Lake, upstream of the permitted release point. The nearest site boundary is 1.79 miles away, with the closest residence nearly 2.0 miles away. All of the leaking water and plume is contained within the site boundary, and based on studies performed by an independent hydrologist, offsite migration is not anticipated. The location is not accessible to the public and there are no drinking water sources, crops, or irrigation in the vicinity of the leak.
The third element in Regulatory Guide 1.21 Rev 2 Section 1.5 is to evaluate a bounding exposure to a member of the public.
"For leaks for spills involving the discharge of radioactive material to the unrestricted area, the dose to members of the public from the leak or spill should be evaluated using realistic or bounding exposure scenarios. However, for leaks or spills that occur on site, a realistic dose assessment to an offsite member of the public may become complicated especially if (1) no radioactive material has entered the unrestricted area and (2) there are no members of the public on site..." (RG 1.21 Rev 2 Sec 1.5 page 12)
A realistic dose assessment to an offsite member of the public is difficult because this is no real exposure pathway. An independent hydrologist concluded that offsite migration was unlikely. The leak and contamination plume are isolated to a wooded region on-site were very few people go. The contamination plume is below the ground surface and does not impact the atmosphere. The water is not used to irrigate crops or drink. Neither meat nor milk producing livestock feed or forage upon the site's vegetation. Finally, the groundwater is not a source of potable water.
According to Regulatory Guide 1.21 Rev 2:
"For leaks and spills, licensees may choose to use bounding assessments to estimate the potential hazard. For example, if a leak occurs on site and radioactive material is released at or below the ground surface, the licensee may choose to assess the potential hazard by assuming that a conservatively large (e.g bounding) volume of water is part of an assumed exposure pathway (e.g.
drinking water). "(RG 1.21 Rev 2 Sec 1.5 page 12)
Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 4
So, in order to establish a bounding estimate of dose, it is assumed that a hypothetical member of the public will "stick a straw" into the Cooling Tower Blowdown Line discharge and consume their total annual intake of water from that source.
Because of permitted radioactive releases, secondary waste discharges, and Harris Lake.
water reuse, the concentration of tritium in the Cooling Tower Blowdown Line fluctuates. In order to give a more realistic picture of the pipe contents, the radioactive release permits and secondary waste discharge data from 2008 were evaluated and the weighted average of tritium concentration during the discharges was determined.
The tritium concentration in the Cooling Tower blowdown is due to the reuse of Harris Lake water. Weather conditions and previous radioactive discharges will cause lake tritium to vary. Per the Off-site Dose Calculation Manual, a composite sample from the Cooling Tower's blowdown weir is obtained and analyzed for tritium monthly. Table 1 shows the 2008 monthly tritium composite results.
Liquid effluent discharges from the radioactive waste system are permitted prior to release to ensure compliance with 10CFR Part 20 limits. In 2008 there were 28 liquid release permits. Table 1 shows the average concentration of tritium for the liquid release permits in a given month. In February, March, and December 2008 there were no radioactive liquid releases. Typically, the discharge flows 23-28 gallons per minute into a Cooling Tower Blowdown Line dilution flow.
The plant's secondary waste is discharged through the secondary waste treatment system. Diffusion of the Steam Generator tubing causes secondary waste to contain low levels of tritium, as seen in Table 1. Roughly 1-1Y2 million gallons of secondary waste is batch released monthly from the plant's Settling Basin at 600 gpm into the Cooling Tower Blowdown flow.
The combination of the Cooling Tower blowdown and makeup water pumps generates a discharge flow of 10,000 to 12,000 gallon per minute along the pipe. The Cooling Tower's blowdown provides a significant dilution of radioactive and secondary releases. As a result, the typical concentration of tritium in the Cooling Tower Blowdown Line is approximately a magnitude larger than the Cooling Tower Blowdown Composite. Table 1 shows the calculated weighted average for a given month.
Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page S
Table 1 - Resulting Tritium Concentration in Cooling Tower Blowdown Line Cooling Tower Monthly Blowdown Average CTBD Composite Radioactive Secondary I Tritium Conc (pCi/L) Release (pCi/L) Waste(pCi/L) (pCi/L)
January 5320 8.90E+07 10,125 20,061 February 7690 no releases 20,574 7,720 March 5440 no releases 21,008 5,478 April 6020 2.52E+07 32,410 8,979 May 5090 1.37E+08 35,067 30,729 June 3690 5.82E+07 31,797 11,044 July 3870 1.04E+07 28,270 5,292 August 5060 3.03E+08 26,898 66,224 September 4470 2.73E+08 13,591 43,508 October 4060 3.15E+08 13,394 T 30,039 November 6510 1.04E+08 16,171 11,786 December 5280 no releases 14,996 5,297 Regulatory Guide 1.109 "Calculationof Annual Dose to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix /" provides the equations for estimating radiation exposure for the principle effluent pathways.
The generalized equation for calculating radiation dose is:
'Raipj = Cip Uap Daipj Where:
Cip the concentration of nuclide i in the media of pathway p, in pCi/I Daipi the dose factor, specific to age group a , radionuclide I, pathway p and organ j, in mrem/pCi from Reg Guide 1.109 Table E-11 Uap the exposure time or ingestion rate (usage) associated with pathway p for age group a, in liter/yr from Reg Guide 1.109 Table E-5 Raipj the annual dose to organ j of an individual of age group a from nuclide i via pathway p, in mrem/yr Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 6
Age group Drinking Water Single Day Ingestion Dose Factors Ingestion Rate (L/yr) Rate (L/day) using (mrem/pCi)
(Using Reg Guide Reg Guide 1.109 (Reg Guide 1.109 1.109 Table E-5) Table E-5) Table E-11 total body and all organs except
_ _ _ _ _,__ bone)
Adult + 730 730/365 = 2.0 1.05E-07 Teen 1 510 510/365 = 1.4 1.06E-07 Child 1 510 510/365 = 1.4 2.03E-07 Infant 330 330/365 = 0.9 3.08E-07 Note I - bone does not have a dose factor for tritium Using the generalized equation and the monthly concentrations from Table 1, the dose to hypothetical members of the public can be computed. The tables below show monthly and annual hypothetical dose for each of the different receptor age groups.
Table 2 - Adult Total Body and All Organs Dose from Ingestion of Cooling Tower Blowdown Line Water Monthly Average Number of Adult Daily Adult Dose Adult Monthly CTBD Days per Water Factor Drinking Water Tritium Month Consumption From H-3 Total Body Dose Month Conc (pCi/L) (days/month) (liters/day) (mrem/pCi) (mrem/month)
January 20,061 31 2.00 1.05E-07 1.31E-01 February 7,720 28 2.00 1.05E-07 4.54E-02 March 5,478 31 2.00 1.05E-07 3.57E-02 April 8,979 30 2.00 1.05E-07 5.66E-02 May 30,729 31 2.00 1.05E-07 2.OOE-01 June 11,044 30 2.00 1.05E-07 6.96E-02 July 5,292 31 2.00 1.05E-07 3;45E-02 August 66,224 31 2.00 1.05E-07 4.31E-01 September 43,508 30 2.00 1.05E-07 2.74E-01 October 30,069 31 2.00 1.05E-07 1.96E-01 November 11,786 30 2.00 1.05E-07 7.43E-02 December 5,297 31 2.00 1.05E-07 3.45E-02 Total Annual _ 1.58 mrem Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 7
Table 3 - Teen Total Body and All Organs Dose from Ingestion of Cooling Tower Blowdown Line Water Monthly I I Average- Number of Teen Daily I Teen Dose Teen Monthly CTBD Days per I Water Factor Drinking Water Tritium Month Consumption From H-3 Total Body Dose Month Conc (pCi/L) (days/month) (liters/day) I(mrem/pCi) (mrem/month)
January 20,061 31 1.40 1.06E-07 9.23E-02 February 7,720 28 1.40 1.06E-07 3.21E-02 March 5,478 31 1.40 1.06E-07 2.52E-02 April 8,979 30 1.40 1.06E-07 4.OOE-02 May 30,729 31 1.40 1.06E-07 1.41E-01 June 11,044 30 1.40 1.06E-07 4.92E-02 July 5,292 31 1.40 1.06E-07 2.43E-02 August 66,224 31 1.40 1.06E-07 3.05E-01 September 43,508 30 1.40 1.06E-07 1.94E-01 October 30,069 31 1.40 1.06E-07 1.38E-01 November 11,786 30 1.40 1.06E-07 5.25E-02 December 5,297 31 1.40 1.06E-07 2.44E-02 Total Annual _ _1.12 mrem Table 4 - Child Total Body and All Organs Dose from Ingestion of Cooling Tower Blowdown Line Water Monthly 1 Average Number of Child Daily Child Dose Child Monthly CTBD Days per I Water Factor Drinking Water Tritium Month Consumption From H-3 Total Body Dose Month j Conc (pCi/L) (days/month) (liters/day) (mrem/pCi) (mrem/month)
January 20,061 31 1.40 2.03E-07 1.77E-01 February 7,720 28 1.40 2.03E-07 6.14E-02 March 5,478 31 1.40 2.03E-07 4.83E-02 April 8,979 30 1.40 2.03E-07 7.66E-02 May 30,729 31 1.40 2.03E-07 2.71E-01 June 11,044 30 1.40 2.03E-07[ 9.42E-02 July 5,292 31 1.40 2.03E-07 4.66E-02 August 66,224 31 1.40 2.03E-07 5.83E-01 September 43,508 30 1.40 2.03E-07 3.71E-01 October 30,069 31 1.40 2,03E-07 2.65E-01 November 11,786 30 1.40 2.03E-07 1.OOE-01 December 5,297 31 1.40 2.03E-07 4.67E-02 Total Annual 2.14 mrem Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 8
Table 5 - Infant Total Body and All Organs Dose from Ingestion of Cooling Tower Blowdown Line Water Monthly Average Number of Infant Daily Infant Dose Infant Monthly CTBD Days per Water Factor Drinking Water Tritium Month Consumption From H-3 Total Body Dose Month Conc (pCi/L) (days/month) (liters/day) (mrem/pCi) (mrem/month)
January 20,061 31 0.90 3.08E-07 1.72E-01 February 7,720 28 0.90 3.08E-07 5.99E-02 March 5,478 31 0.90 3.08E-07 4.71E-02 April 8,979 30 0.90 3.08E-07 7.47E-02 May 30,729 31 0.90 3.08E-07 2.64E-01 June 11,044 30 0.90 3.08E-07 9.18E-02 July 5,292 31 0.90 3.08E-07 4.55E-02 August 66,224 31 0.90 3.08E-07 5.69E-01 September 43,508 30 0.90 3.08E-07 3.62E-01 October 30,069 31 0.90 3.08E-07 2.58E-01 November 11,786 30 0.90 3.08E-07 9.80E-02 December 5,297 31 0.90 3.08E-07 4.55E-02 Total Annual _ _ __ _ 2.09 mrem In this scenario the hypothetical critical receptor is a child who received 2.14 mrem of total body and organs dose.
A second more realistic scenario, but equally hypothetical, would be for a member of the public to drink from a groundwater well located within the contaminant plume. The source water will be diluted on contact with soil and water in the environment. While the 2008 the annual average tritium concentration of the undiluted source liquid was 20,516 pCi/L; the highest observed concentration of tritium in the groundwater was only 2,120 pCi/L, roughly a tenth of the source concentration.
Table 6 shows the annual dose a member of the public would receive if they were to consume their full annual intake from the tritiated groundwater.
Impact of Cooling Tower Blowdown Line Leak upon a Member of the Public Page 9
I I P, Table 6 -Total Body and All Organs Dose from Ingestion of.Groundwater Drinking Water Dose Factors Annual Age group Ingestion Rate (mrem/pCi) (RegGOuide!.-09 Concentration Dose (L/yr) (using Reg Guide -Table E.11 total body and all organs (pCi/L) ( ose except bone)
(mrem) 1.109 Table E-5)
Adult 730 1.05E-07 2120 0.162 Teen 510 1.06E-07 2120 0.115 Child 510 2.03E-07 2120 0.219 Infant 330 3.08E-07 2120 0.215 Note 1 - bone does not have a dose factor for tritium In this case, the critical receptor in the case is a child who would receive 0.22 mrem from this exposure pathway.
In 2008, the total body dose from all pathways was 0.351 mrem. 10CFR50 Appendix I limits for liquid effluents for any individual in an unrestricted area from all pathways of exposure is 3 mrem total body or 10 mrem to any organ. The total dose received by a child in the first bounding calculation would be 2.491 mrem total body (2.14 mrem + 0.351 mrem).
While the total dose received in the second bounding calculation would be 0.57 mrem (0.219 mrem + 0.351 mrem). Since these doses are less than the 10CFR5O Appendix I limits the exposure to the leaking Cooling Tower Blowdown Line does not violate any regulatory limits.
Despite the calculated doses, there is no real exposure pathway to a member of the public. The hazard assessments presented above are bounding estimates of the dose to a hypothetical individual member of the public. No actual exposure was received by a member of the public and the Annual Radioactive Effluent Release Report does not need to be revised to include these dose.
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