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| | number = ML13107A093 | | | number = ML13107A093 |
| | issue date = 04/16/2013 | | | issue date = 04/16/2013 |
| | title = Braidwood Station, Units 1 and 2 - Annual Dose Report for 2012 | | | title = Annual Dose Report for 2012 |
| | author name = Enright D J | | | author name = Enright D |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
| | addressee name = | | | addressee name = |
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| | page count = 2 | | | page count = 2 |
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| | =Text= |
| | {{#Wiki_filter:April 16, 2013 10 CFR 20.2206(c) |
| | BW130036 REIRS Project Manager Office of Nuclear Regulatory Research U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-456 and STN 50-457 |
| | |
| | ==Subject:== |
| | Annual Dose Report for 2012 Pursuant to 10 CFR 20.2206, "Reports of individual monitoring," paragraph (c), the Annual Dose Report covering the previous year shall be submitted on or before April 30 of each year. The Annual Dose Report for 2012 provides the results of individual radiation monitoring carried out by Braidwood Station for each individual for whom radiation monitoring was provided during 2012. The data file containing this report was submitted electronically via the Radiation Exposure and Information Reporting System (REIRS) internet web page on April 5, 2013. |
| | The data file entitled "brw2012form5.dat" was generated on April 3, 2013, following the guidance provided in Regulatory Guide 8.7, "Instructions for Recording and Reporting Occupational Radiation Exposure Data," Revision 2, dated November 2005. |
| | During the spring of 2012, the 2010 Annual Dose Report was undergoing a final review before it was printed. It was discovered by the personnel at the Radiation Exposure and Information Reporting System (REIRS) data management group at Oak Ridge National Laboratory that Braidwood Station reported internal dose (CEDE) due to tritium in nanoCuries instead of microCuries, as is required by NRC Regulatory Guide 8.7. An Extent of Condition review determined that the Annual Dose Reports for 2008, 2009, and 2011 also contained the same error. |
| | The REIRS data management manager at Oak Ridge National Laboratory was contacted and the incorrect tritium internal dose (CEDE) data for 2010 and 2011 was corrected in the REIRS electronic database. This means that the correct data will be included in the hard copy NRC reports for 2010 and 2011. The REI RS data management manager also corrected the incorrect tritium internal dose (CEDE) data for 2008 and 2009 in the REIRS electronic database, but the hard copy NRC reports for these years have already been generated with the incorrect data. Exelon Corporate Regulatory Assurance personnel confirmed with the NRR Project Manager for Braidwood and one of the NRC resident inspectors for Braidwood that no additional actions are required to correct this issue. |
| | |
| | U. S. Nuclear Regulatory Commission Page 2 of 2 The Exelon Midwest Regional Operating Group RP procedure that provides instructions on generating and submitting the NRC Annual Dose Report required per 10CFR20.2206(c), RP-MW -280-1001, Generation of Occupational Exposure Reports in Passport, is in the process of being revised to provide greater detail to ensure complete compliance with NRC Regulatory Guide 8.7. This revision is being tracked through an assignment in Braidwood's Corrective Action Program. The 2012 Braidwood NRC Annual Dose Report was generated following guidance from NRC Regulatory Guide 8.7 and RP Desktop Instruction "Manual In-Vivo and In-Vitro Sample Requests, Manual Entry of Results, and Retrieval/Modification of Results," both of which require that the internal dose (CEDE) data submitted on the NRC Annual Dose Report is listed in the unit of microCuries. |
| | Should you have any questions concerning this information, please contact Mr. Chris VanDenburgh, Regulatory Assurance manager, at (815) 417-2800. |
| | Respectfu"y, Daniel J. Enright Site Vice President Braidwood Station cc: NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety US NRC Regional Administrator, Region III US NRC Senior Resident Inspector (Braidwood Station)}} |
Latest revision as of 20:34, 4 November 2019
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Category:Letter
MONTHYEARML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) 2024-08-09
[Table view] |
Text
April 16, 2013 10 CFR 20.2206(c)
BW130036 REIRS Project Manager Office of Nuclear Regulatory Research U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-456 and STN 50-457
Subject:
Annual Dose Report for 2012 Pursuant to 10 CFR 20.2206, "Reports of individual monitoring," paragraph (c), the Annual Dose Report covering the previous year shall be submitted on or before April 30 of each year. The Annual Dose Report for 2012 provides the results of individual radiation monitoring carried out by Braidwood Station for each individual for whom radiation monitoring was provided during 2012. The data file containing this report was submitted electronically via the Radiation Exposure and Information Reporting System (REIRS) internet web page on April 5, 2013.
The data file entitled "brw2012form5.dat" was generated on April 3, 2013, following the guidance provided in Regulatory Guide 8.7, "Instructions for Recording and Reporting Occupational Radiation Exposure Data," Revision 2, dated November 2005.
During the spring of 2012, the 2010 Annual Dose Report was undergoing a final review before it was printed. It was discovered by the personnel at the Radiation Exposure and Information Reporting System (REIRS) data management group at Oak Ridge National Laboratory that Braidwood Station reported internal dose (CEDE) due to tritium in nanoCuries instead of microCuries, as is required by NRC Regulatory Guide 8.7. An Extent of Condition review determined that the Annual Dose Reports for 2008, 2009, and 2011 also contained the same error.
The REIRS data management manager at Oak Ridge National Laboratory was contacted and the incorrect tritium internal dose (CEDE) data for 2010 and 2011 was corrected in the REIRS electronic database. This means that the correct data will be included in the hard copy NRC reports for 2010 and 2011. The REI RS data management manager also corrected the incorrect tritium internal dose (CEDE) data for 2008 and 2009 in the REIRS electronic database, but the hard copy NRC reports for these years have already been generated with the incorrect data. Exelon Corporate Regulatory Assurance personnel confirmed with the NRR Project Manager for Braidwood and one of the NRC resident inspectors for Braidwood that no additional actions are required to correct this issue.
U. S. Nuclear Regulatory Commission Page 2 of 2 The Exelon Midwest Regional Operating Group RP procedure that provides instructions on generating and submitting the NRC Annual Dose Report required per 10CFR20.2206(c), RP-MW -280-1001, Generation of Occupational Exposure Reports in Passport, is in the process of being revised to provide greater detail to ensure complete compliance with NRC Regulatory Guide 8.7. This revision is being tracked through an assignment in Braidwood's Corrective Action Program. The 2012 Braidwood NRC Annual Dose Report was generated following guidance from NRC Regulatory Guide 8.7 and RP Desktop Instruction "Manual In-Vivo and In-Vitro Sample Requests, Manual Entry of Results, and Retrieval/Modification of Results," both of which require that the internal dose (CEDE) data submitted on the NRC Annual Dose Report is listed in the unit of microCuries.
Should you have any questions concerning this information, please contact Mr. Chris VanDenburgh, Regulatory Assurance manager, at (815) 417-2800.
Respectfu"y, Daniel J. Enright Site Vice President Braidwood Station cc: NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety US NRC Regional Administrator, Region III US NRC Senior Resident Inspector (Braidwood Station)