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| | author name = Condra D | | | author name = Condra D |
| | author affiliation = Oak Ridge Institute for Science & Education | | | author affiliation = Oak Ridge Institute for Science & Education |
| | addressee name = Snell W G | | | addressee name = Snell W |
| | addressee affiliation = NRC/RGN-III | | | addressee affiliation = NRC/RGN-III |
| | docket = 05000456 | | | docket = 05000456 |
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| | page count = 4 | | | page count = 4 |
| }} | | }} |
| See also: [[followed by::IR 05000456/2007004]]
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| =Text= | | =Text= |
| {{#Wiki_filter:ORISE OAK RIDGE INSTITUTE | | {{#Wiki_filter:O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION June 27,2007 hir. Kiham Snell U S . Nuclear Regulatory Commission Regon I11 3133 Warrenvdle Road Lisle, IL 60532-4351 |
| FOR SCIENCE AND EDUCATION June 27,2007 hir. K'iham | |
| Snell US. Nuclear Regulatory | |
| Commission | |
| Regon I11 3133 W'arrenvdle | |
| Road Lisle, IL 60532-4351 | |
| SUBJECT: LETTER REPORT FOR FOUR WATER SAMPLES FROM THE VICINITY OF THE BRAIDWOOD NUCLEAR
| |
| GENERATING
| |
| STATION, BRAIDWOOD, ILLINOIS
| |
| [INSPECTION
| |
| REPORT NO. 050-00456/2007-0041 (RFTA NO. 07-001) Dear Mr. Snell: The Oak hdge Institute for
| |
| Science and Education (ORISE) received four water samples associated
| |
| with the Braidwood
| |
| Generating
| |
| Station on June 1,2007.
| |
| ORISE analyzed the samples, for tritium, to an average minimum detectable concentration
| |
| of 190 pCi/L using a liquid scindation
| |
| analyzer with one exception. Sample BD-07-03-03 had a
| |
| very short count time due to the concentration
| |
| of tritium in the samples. The chain-of-custody
| |
| also identified
| |
| one water sample
| |
| to be analyzed by gamma spectroscopy
| |
| ((2s). The sample identifications and collection data are
| |
| presented
| |
| in Table 1. GS data are presented in Table 2 and the tritium data
| |
| are presented in
| |
| Table 3. Pertinent procedural
| |
| references
| |
| are provided in the specific tables. ORISE's Quality Control (QC) requirements
| |
| were met for these
| |
| analyses.
| |
| The QC files are avdable for your review upon request. hly contact information
| |
| is listed below.
| |
| You may also contact Wade
| |
| Ivey at 865.576.9183
| |
| with any questions
| |
| or comments.
| |
| Sincerely, Dale Condra, Manager Laboratory
| |
| C: RDC:K,TI:km
| |
| T. Carter, NMSS/DKMEP
| |
| 7J8 E. Knox-Davin, NRC/NMSS/TWFN
| |
| 8A23 E. Abelquist, ORISE S. Roberts, ORISE File 1744 ~~~~~~~~ Distribution approval and
| |
| concurrence
| |
| : Technical
| |
| Management Team hlember
| |
| I Initials i'oice: 865.241.3242
| |
| Fax: 865.24 1.3248
| |
| RECEIVED JUL 0 2 2007 E-mail: Dale.Condra@orau.org
| |
| TABLE 1 ORISE Sample ID 1744W0001
| |
| SAMPLE IDENTIFICATIONS
| |
| AND COLLECTION
| |
| DATA BRAIDWOOD NUCLEAR GENERATING STATION
| |
| BRAIDWOOD, ILLINOIS NRC Region I11 Collection
| |
| Collection
| |
| Sample ID Date Time BD-07-03-01
| |
| 05/31 /07 0800 1744W0002
| |
| 1744W0003
| |
| 1744W0004
| |
| ,. BD-07-03-02 05/31 /07
| |
| 0810 BD-07-03-04
| |
| 05/31/07 0925 BD-07-03-03 05/31 /07 , 0935 Hr;lldwood
| |
| Nuclear Generanrig
| |
| Station prqccts/ 1744/I>ata Tables/2007-06-27
| |
| Data Tables
| |
| TABLE 2 ORISE Sample ID 1744W0004 CONCENTRATIONS OF
| |
| SELECTED GAMMA EMITTING RADIONUCLIDES
| |
| IN SELECTED WATER SAMPLES
| |
| BY GAMMA SPECTROSCOPY
| |
| CP1, REVISION 15 BRAIDWOOD NUCLEAR GENERATING STATION
| |
| BRAIDWOOD, ILLINOIS NRC Region I11 Radionuclide Concentrationsa @Ci/L)
| |
| Sample ID CO-58 CO-60 cs-134 cs-w7 BD-07-03-04
| |
| 0.2 & 2.4b , 3.9 0.9 & 3.0 , 4.5 0.1 -t 2.8 , 4.1 -1.1 k 2.3 , 3.9 Braidwood
| |
| Nuclear Gcncrating
| |
| Station proiects/
| |
| 1744/Data
| |
| 'l'ablcs/2007-06-27
| |
| Data 'l'ablcs
| |
| TABLE 3 ORISE Sample ID 1744W0001
| |
| 1744W0002
| |
|
| |
|
| 1744W0003 | | ==SUBJECT:== |
| CONCENTRATIONS | | LETTER REPORT FOR FOUR WATER SAMPLES FROM THE VICINITY OF THE BRAIDWOOD NUCLEAR GENERATING STATION, BRAIDWOOD, ILLINOIS |
| OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION | | [INSPECTION REPORT NO. 050-00456/2007-0041 (RFTA NO. 07-001) |
| ANALYSIS AP2, REVISION 16 ; CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION | | |
| BRAIDWOOD, ILLINOIS NRC Region 111 Tritium Concentrations, Sample ID TPUs, and MDCS" @Ci/L) | | ==Dear Mr. Snell:== |
| BD-07-03-01 | | |
| 380 k 120b , 190 BD-07-03-02 | | The Oak h d g e Institute for Science and Education (ORISE) received four water samples associated with the Braidwood Generating Station on June 1,2007. ORISE analyzed the samples, for tritium, to an average minimum detectable concentration of 190 pCi/L using a liquid scindation analyzer with one exception. Sample BD-07-03-03 had a very short count time due to the concentration of tritium in the samples. The chain-of-custody also identified one water sample to be analyzed by gamma spectroscopy |
| 440 k 120 , 190 BD-07-03-03 | | ((2s).The sample identifications and collection data are presented in Table 1 . GS data are presented in Table 2 and the tritium data are presented in Table 3. |
| 1.523.000 | | Pertinent procedural references are provided in the specific tables. ORISEs Quality Control (QC) requirements were met for these analyses. The Q C files are avdable for your review upon request. |
| k 57.000 , 1.000 ~~ 1744W0004 BD-07-03-04 | | hly contact information is listed below. You may also contact Wade Ivey at 865.576.9183 with any questions or comments. |
| I 59,100 k 2,200 , 200 ~~ "hil>(:s arc after
| | Sincerely, Dale Condra, Manager Laboratory RDC:K,TI:km C: T. Carter, NMSS/DKMEP 7J8 E. Knox-Davin, NRC/NMSS/TWFN 8A23 E. Abelquist, ORISE S. Roberts, ORISE File 1744 I Initials |
| thc comma. "Uncertaintics | | ~~~~~~~~ |
| represent | | Distribution approval and concurrence : |
| the 95";) confidcncc | | Technical Management Team hlember RECEIVED JUL 0 2 2007 ioice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org |
| led, based on total propaptcd
| | |
| unccrtantics. | | TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region I11 Collection Collection Sample ID Sample ID Date Time 1744W0001 BD-07-03-01 , ./07 05/31 0800 1744W0002 BD-07-03-02 05/31 /07 0810 1744W0003 BD-07-03-03 05/31 /07 , 0935 1744W0004 BD-07-03-04 05/31/07 0925 Hr;lldwood Nuclear Generanrig Station p r q c c t s / 1744/I>ata Tables/2007-06-27 Data Tables |
| Hrdwood Nuclear (kncraung
| | |
| Station | | TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N SELECTED WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region I11 Radionuclide Concentrationsa@Ci/L) |
| }} | | Sample ID Sample ID CO-58 CO-60 cs-134 cs-w7 1744W0004 BD-07-03-04 0.2 & 2.4b , 3.9 0.9 & 3.0 , 4.5 0.1 -t 2.8 , 4.1 -1.1 k 2.3 , 3.9 Braidwood Nuclear Gcncrating Station proiects/ 1744/Data 'l'ablcs/2007-06-27 Data 'l'ablcs |
| | |
| | TABLE 3 CONCENTRATIONS OF TRITIUM I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 16 ;CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region 111 Tritium Concentrations, Sample ID Sample ID TPUs, and MDCS"@Ci/L) 1744W0001 BD-07-03-01 380 k 120b , 190 1744W0002 BD-07-03-02 440 k 120 , 190 1744W0003 BD-07-03-03 1.523.000 k 57.000 , 1.000 I |
| | ~~ |
| | 1744W0004 BD-07-03-04 59,100 k 2,200 , 200 |
| | ~~ |
| | "hil>(:s arc after thc comma. |
| | "Uncertaintics represent the 95";) confidcncc l e d , based o n total p r o p a p t c d unccrtantics. |
| | H r d w o o d Nuclear (kncraung Station}} |
|
---|
Category:Environmental Monitoring Report
MONTHYEARBW240053, Revised 2022 Annual Radioactive Effluent Release Report2024-09-0606 September 2024 Revised 2022 Annual Radioactive Effluent Release Report BW240026, Annual Radiological Environmental Operating Report (1 January Through 31 December 2023)2024-05-15015 May 2024 Annual Radiological Environmental Operating Report (1 January Through 31 December 2023) BW240027, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for April 2023 to March 20242024-05-15015 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for April 2023 to March 2024 BW240019, Annual Radioactive Effluent Release Report2024-05-0101 May 2024 Annual Radioactive Effluent Release Report ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites BW230024, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2023-05-12012 May 2023 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW220029, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20212022-05-31031 May 2022 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2021 BW220028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-05-13013 May 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW220026, Annual Radioactive Effluent Release Report (ARERR)2022-04-29029 April 2022 Annual Radioactive Effluent Release Report (ARERR) BW210060, National Pollutant Discharge Elimination System2021-08-20020 August 2021 National Pollutant Discharge Elimination System ML21118A8322021-05-0101 May 2021 Annual Radioactive Effluent Release Report (ARERR) BW200037, Annual Radiological Environmental Operating Report2020-05-31031 May 2020 Annual Radiological Environmental Operating Report ML19121A4632018-12-31031 December 2018 Annual Radioactive Effluent Release Report ML18145A0852018-05-25025 May 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML17135A1412017-05-15015 May 2017 National Pollutant Discharge Elimination System (NPDES) Permit No. IL0048321 ML17118A0572017-04-28028 April 2017 Transmittal of 2016 Radioactive Effluent Release Report ML16137A0552016-05-16016 May 2016 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML16132A1732016-05-11011 May 2016 Transmittal of 2015 Annual Radiological Environmental Operating Report ML16118A3742016-04-27027 April 2016 Transmittal of 2015 Radioactive Effluent Release Report ML15134A2952015-05-31031 May 2015 Annual Radiological Environmental Operating Report, 1 Janaury Through 31 December 2014 ML15118A8732015-04-30030 April 2015 Radioactive Effluent Release Report ML14136A3132014-05-14014 May 2014 2013 Annual Radiological Environmental Operating Report ML13137A1052013-05-14014 May 2013 Submittal of 2012 Annual Radiological Environmental Operating Report ML13134A0492013-04-30030 April 2013 Submittal of 2012 Radioactive Effluent Release Report RS-14-029, Braidwood Station, Kankakee River Fish Monitoring Program, 20122013-02-28028 February 2013 Braidwood Station, Kankakee River Fish Monitoring Program, 2012 ML14030A2732013-02-28028 February 2013 Kankakee River Fish Monitoring Program, 2012 RS-14-029, Braidwood Station, 2011 Benthos Monitoring and Historical Fish and Benthos Comparisons2012-07-31031 July 2012 Braidwood Station, 2011 Benthos Monitoring and Historical Fish and Benthos Comparisons ML14030A2742012-07-31031 July 2012 2011 Benthos Monitoring and Historical Fish and Benthos Comparisons ML12137A3042012-05-14014 May 2012 Submittal of 2011 Annual Radiological Environmental Operating Report ML12130A1982012-04-26026 April 2012 2011 Radioactive Effluent Release Report RS-14-029, Braidwood Station Kankakee River Fish Monitoring Program, 20102011-12-31031 December 2011 Braidwood Station Kankakee River Fish Monitoring Program, 2010 ML14030A2792011-12-31031 December 2011 Braidwood Station Kankakee River Fish Monitoring Program, 2010 ML11137A0482011-05-13013 May 2011 Annual Radiological Environmental Operating Report ML11122A1092011-04-29029 April 2011 2010 Radioactive Effluent Release Report ML1013904752010-05-14014 May 2010 Annual Radiological Environmental Operating Report ML1012503352010-04-28028 April 2010 Radioactive Effluent Release Report ML1017501232010-02-17017 February 2010 Memo-Analytical Results of Water Samples from the Vicinity of the Braidwood Nuclear Power Station ML0916906572009-05-27027 May 2009 Email Correspondence Between S. Orth USNRC R3 and W. Alderson on 5/27/09 Braidwood End of Cycle Meeting ML0913501882009-05-14014 May 2009 2008 Annual Radiological Environmental Operating Report, Submitted in Accordance with Technical Specification 5.6.2 ML0913303722009-04-30030 April 2009 2008 Radioactive Effluent Release Report Submitted in Accordance with 10 CFR 50.36a ML0915206432009-04-21021 April 2009 Tritium Groundwater Sample Results from American Radiation Services, Inc. for Braidwood 1st Quarter, March 10 and 11, 2009 ML14030A2662009-02-25025 February 2009 Response to NRC Request for Additional Information, Dated December 20, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Braidwood Station Applicant'S Environmental Report ML0814300312008-05-15015 May 2008 Annual Radiological Environmental Operating Report ML0812904082008-04-30030 April 2008 Transmittal of 2007 Radioactive Effluent Release Report ML0809403982008-03-31031 March 2008 Oak Ridge Institute for Science and Education - Braidwood ML0718005002007-06-27027 June 2007 Oak Ridge Institute for Science and Education, Braidwood Water Samples Report No. 050-00456/2007-004 ML0714202592007-05-31031 May 2007 Annual Radiological Groundwater Protection Progam Report for 2006 ML0714202552007-05-31031 May 2007 Annual Radiological Environmental Operating Report for 2006 ML0612904652006-05-0404 May 2006 Oak Ridge Institute for Science and Education, Analytical Results for Thirteen Water Samples, Batch Four, from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois ML0612103762006-04-28028 April 2006 Radioactive Effluent Release Report 2024-09-06
[Table view] Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 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) 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 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 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 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 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 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 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) 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 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, 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 RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] |
Text
O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION June 27,2007 hir. Kiham Snell U S . Nuclear Regulatory Commission Regon I11 3133 Warrenvdle Road Lisle, IL 60532-4351
SUBJECT:
LETTER REPORT FOR FOUR WATER SAMPLES FROM THE VICINITY OF THE BRAIDWOOD NUCLEAR GENERATING STATION, BRAIDWOOD, ILLINOIS
[INSPECTION REPORT NO. 050-00456/2007-0041 (RFTA NO.07-001)
Dear Mr. Snell:
The Oak h d g e Institute for Science and Education (ORISE) received four water samples associated with the Braidwood Generating Station on June 1,2007. ORISE analyzed the samples, for tritium, to an average minimum detectable concentration of 190 pCi/L using a liquid scindation analyzer with one exception. Sample BD-07-03-03 had a very short count time due to the concentration of tritium in the samples. The chain-of-custody also identified one water sample to be analyzed by gamma spectroscopy
((2s).The sample identifications and collection data are presented in Table 1 . GS data are presented in Table 2 and the tritium data are presented in Table 3.
Pertinent procedural references are provided in the specific tables. ORISEs Quality Control (QC) requirements were met for these analyses. The Q C files are avdable for your review upon request.
hly contact information is listed below. You may also contact Wade Ivey at 865.576.9183 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:K,TI:km C: T. Carter, NMSS/DKMEP 7J8 E. Knox-Davin, NRC/NMSS/TWFN 8A23 E. Abelquist, ORISE S. Roberts, ORISE File 1744 I Initials
~~~~~~~~
Distribution approval and concurrence :
Technical Management Team hlember RECEIVED JUL 0 2 2007 ioice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region I11 Collection Collection Sample ID Sample ID Date Time 1744W0001 BD-07-03-01 , ./07 05/31 0800 1744W0002 BD-07-03-02 05/31 /07 0810 1744W0003 BD-07-03-03 05/31 /07 , 0935 1744W0004 BD-07-03-04 05/31/07 0925 Hr;lldwood Nuclear Generanrig Station p r q c c t s / 1744/I>ata Tables/2007-06-27 Data Tables
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N SELECTED WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region I11 Radionuclide Concentrationsa@Ci/L)
Sample ID Sample ID CO-58 CO-60 cs-134 cs-w7 1744W0004 BD-07-03-04 0.2 & 2.4b , 3.9 0.9 & 3.0 , 4.5 0.1 -t 2.8 , 4.1 -1.1 k 2.3 , 3.9 Braidwood Nuclear Gcncrating Station proiects/ 1744/Data 'l'ablcs/2007-06-27 Data 'l'ablcs
TABLE 3 CONCENTRATIONS OF TRITIUM I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 16 ;CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region 111 Tritium Concentrations, Sample ID Sample ID TPUs, and MDCS"@Ci/L) 1744W0001 BD-07-03-01 380 k 120b , 190 1744W0002 BD-07-03-02 440 k 120 , 190 1744W0003 BD-07-03-03 1.523.000 k 57.000 , 1.000 I
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1744W0004 BD-07-03-04 59,100 k 2,200 , 200
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"hil>(:s arc after thc comma.
"Uncertaintics represent the 95";) confidcncc l e d , based o n total p r o p a p t c d unccrtantics.
H r d w o o d Nuclear (kncraung Station