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Category:Drawing
MONTHYEARML21137A2072021-05-17017 May 2021 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 2.3, Figures, Part 1 of 2-Redacted ML17255A8512017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 700 - 749, Part 12 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 600 - 649, Part 10 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 600 - 649, Part 10 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 650 - 699, Part 11 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 650 - 699, Part 11 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 700 - 749, Part 12 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 700 - 749, Part 12 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 750 - 799, Part 13 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 750 - 799, Part 13 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 800 - 849, Part 14 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 800 - 849, Part 14 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 850 - 904, Part 15 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 850 - 904, Part 15 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 151 - 200, Part 1 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 151 - 200, Part 1 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 201 - 250, Part 2 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 201 - 250, Part 2 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 251 - 300, Part 3 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 251 - 300, Part 3 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 4 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 4 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 5 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 5 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 401 - 450, Part 6 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 401 - 450, Part 6 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 451 - 499, Part 7 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 451 - 499, Part 7 of 15 RS-17-119, Braidwood and Byron, Units 1 and 2 - Figures 500 - 549, Part 8 of 152017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 500 - 549, Part 8 of 15 ML17255A8552017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 151 - 200, Part 1 of 15 ML17255A8502017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 650 - 699, Part 11 of 15 ML17255A8522017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 750 - 799, Part 13 of 15 ML17255A8542017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 850 - 904, Part 15 of 15 ML17255A8532017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 800 - 849, Part 14 of 15 ML17255A8592017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 251 - 300, Part 3 of 15 ML17255A8662017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 500 - 549, Part 8 of 15 ML17255A8652017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 451 - 499, Part 7 of 15 ML17255A8612017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 4 of 15 RS-17-119, Units 1 and 2 - Figures 550 - 599, Part 9 of 152017-09-0101 September 2017 Units 1 and 2 - Figures 550 - 599, Part 9 of 15 ML17255A8492017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 600 - 649, Part 10 of 15 ML17255A8632017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 301 - 350, Part 5 of 15 ML17255A8572017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 201 - 250, Part 2 of 15 ML17255A8642017-09-0101 September 2017 Braidwood and Byron, Units 1 and 2 - Figures 401 - 450, Part 6 of 15 RS-14-338, Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 2.0 Figures - Braidwood - Part 2 of 22014-12-15015 December 2014 Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 2.0 Figures - Braidwood - Part 2 of 2 ML15055A3902014-12-15015 December 2014 Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 2.0 Figures - Braidwood - Part 2 of 2 ML0609605042006-03-17017 March 2006 Drawing Showing Braidwood Station, Essex Road, Blowdown Structure at Rive Screen House and 11 Ocw Numbered Items ML0609605122006-03-17017 March 2006 Figure 1 Site Plan and Well Locations Braidwood Station ML0609605022006-03-17017 March 2006 Figure 2.5-25 Geologic Section H-H Braidwood Station Updated Final Safety Analysis Report ML0610204282006-01-31031 January 2006 Drawing Figure 2, Draft Average Groundwater Contours Shallow - January 2006. ML0618400862006-01-30030 January 2006 Figure 5 - Estimated Tritium Results Deep Groundwater Zone - Braidwood Station ML0618400872006-01-30030 January 2006 Figure 4 - Estimated Tritium Results Shallow Groundwater Zone - Braidwood Station ML0610705292006-01-30030 January 2006 Drawing 1, Groundwater Monitoring Locations. ML0610705262006-01-30030 January 2006 Drawing 6, Site Specific Hydrogeologic Profile January 2006 (A-A') ML0610106762005-12-16016 December 2005 Potential Source Release and Transport Theories ML0610106882005-12-16016 December 2005 Tritium Concentrations in the Deeper Monitoring Wells ML0610106942005-12-16016 December 2005 Schematic of Regional Hydrogeology ML0618400692005-12-0909 December 2005 E-mail from Habighorst to Lynch, Braidwood Tritium - Recent Contamination Contours, Etc ML0618400592005-12-0808 December 2005 E-mail from Orth to Braidwood Communication Team, Braidwood Tritium - Recent Contamination Contours, Etc ML0609706062005-12-0606 December 2005 Draft - Figure Version 2 Select Locations - Hand Contours December 6, 2005 Braidwood Station ML0609706052005-12-0606 December 2005 Figure Estimated Tritium Concentrations December 6, 2005, Braidwood Station ML0609706032005-12-0606 December 2005 Figure Estimated Tritium Concentration December 6, 2005, Braidwood Station ML0609706022005-12-0606 December 2005 Figure Estimated Tritium Concentrations December 6, 2005, Braidwood Station ML0609706002005-12-0606 December 2005 Drawing M-33, Diagram of Circulation Water Make-up Unit 1 and 2. 2021-05-17
[Table view] Category:E-Mail
MONTHYEARML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23321A2012023-11-17017 November 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML23311A1682023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections (L-2023-LLR-0053 and L-2023-LLR-005 ML23311A1692023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Exam Categories B-B, B-D, and C-A SG Pressure Retaining Welds and Full Penetration Welded Nozzles (L-2023-LLR-0055 and L-2023-LLR-00 ML23304A0222023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Braidwood 1 & 2 - Exemption from Security Rule (L-2023-LLE-0030) ML23187A0092023-07-0606 July 2023 NRR E-mail Capture - NRC Acceptance Review of Byron and Braidwood Request to Adopt TSTF-370 ML23103A4692023-04-12012 April 2023 NRR E-mail Capture - NRC Acceptance Review of Braidwood Request for Amendment to Revise TS 3.7.9 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22255A0132022-09-0909 September 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, Calvert Cliffs, Ginna - License Amendment Request to Adopt TSTF-577 ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22189A0602022-07-0707 July 2022 NRR E-mail Capture - Draft RAI for Byron/Braidwood TSTF-501 ML22136A2722022-05-16016 May 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood and Byron Adoption of TSTF-501 ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22116A0242022-04-25025 April 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, and Ginna Request to Adopt TSTF-246 ML22105A0722022-04-15015 April 2022 NRR E-mail Capture - Braidwood/Byron Verbal Authorization for Proposed Alternative I4R-15/I4R-21 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22088A1562022-03-0202 March 2022 NRR E-mail Capture - Byron, Braidwood, Calvert Cliffs, and Ginna - Non-acceptance of Application to Revise Technical Specifications 5.6.5.b, the Core Operating Limits Report (COLR) ML22091A0842022-02-24024 February 2022 NRR E-mail Capture - Braidwood and Byron - Withdrawal of Draft RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML23089A0172022-01-0505 January 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood - Proposed Alternative for Examinations of Categories B-B, B-D, and C-A SG Welds and Nozzles ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21272A1492021-09-29029 September 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood and Byron - Proposed Alternative for Examinations of Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0172021-09-0303 September 2021 NRR E-mail Capture - NRC Acceptance Review - Braidwood - License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink ML21252A0042021-08-26026 August 2021 NRR E-mail Capture - NRC Acceptance Review - Braidwood/Byron/Clinton - Adoption of TSTF-273, Safety Function Determination Program Clarifications ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21154A0162021-06-0202 June 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood - Proposed Alternative for Exam of Pzr Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Shell Welds ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21123A2442021-05-0303 May 2021 NRR E-mail Capture - NRC Acceptance Review of Braidwood/Byron/Ginna - Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5 and NSAL-15-1 (L-2021-LLA-0066) ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21033A8552021-02-0202 February 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request to Expand the Use ASME Codes Cases N-878 and N-880 ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20350B5582020-12-14014 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Alternative Request for Documentation of Replacement of Pressure Retaining Bolting ML20346A1012020-12-11011 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for an Alternative to Use ASME Code Case N-893 (EPIDs L-2020-LLR-0147 and L-2020-LLR-0148) ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20266G3032020-09-22022 September 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI ML20261H4122020-09-11011 September 2020 NRR E-mail Capture - (External_Sender) License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML21145A0572020-08-18018 August 2020 NRR E-mail Capture - NRC Acceptance Review for Braidwood Relief Request I4R-11 2023-07-06
[Table view] Category:Report
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-12-0707 December 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16250A5182016-04-30030 April 2016 Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds ML16014A1882016-01-22022 January 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 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015 Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 ML14349A6572014-12-15015 December 2014 CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14141A1332014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology ML14101A4452014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095) ML14101A3522014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14127A1742014-05-0707 May 2014 Startup Report for the Measurement Uncertainty Recapture Power Uprate ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses 2023-04-20
[Table view] Category:Miscellaneous
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML16014A1882016-01-22022 January 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 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 ML14349A6572014-12-15015 December 2014 CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application ML14141A1332014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14101A4452014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095) ML14101A3522014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14127A1742014-05-0707 May 2014 Startup Report for the Measurement Uncertainty Recapture Power Uprate ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event ML14059A1242014-02-28028 February 2014 Pressure and Temperature Limits Reports (Ptlrs) IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12349A3632012-12-14014 December 2012 10 CFR 50.59 Summary Report for June 19, 2010 Through June 18, 2012 ML12339A2172012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 1 of 5 ML12339A2182012-11-16016 November 2012 12Q0108.10-R-002, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 2. Part 5 of 5 ML12339A2192012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 2 of 5 ML12339A2202012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 3 of 5 ML12339A2212012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 4 of 5 ML12339A2222012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 5 of 5 2023-11-17
[Table view] |
Text
Steven Orth - Fwd. CRs re: trtium leak frm vac brkrs Page1 From: Richard Skokowski / 1 /
To: Steven Orth Date: Wed, Nov 30, 2005 3:58 PM
Subject:
Fwd: CRs re: trtium leak frm vac brkrs
%I
\16
I Steyen pth - CRs re: trtium leak frm vac brkrs Paae 1U Ii From: "NXS@NRC.GOV" <nxs~nrc.gov>
To: 'RAS@NRC.GOV" <ras©nrc.gov>
Date: Wed, Nov 30, 2005 3:08 PM
Subject:
CRs re: trtium leak frm vac brkrs
v' Cionle another Novi Issuo tz0.Create another Issue from'0042811138' lrtinl Close w~indow/
- AS REQUIRED, PRINT ISSUE REPORT AND PROVIDE TO YOUR SUPERVISOR**
Note: This is your only notice. You will not have -an opportunity to print this confirmation later.
Exelon Nuclear Issue - Statement of Confirmation Issue S: 0O428606 Originator: ALLAN AtHAEGER - SubmilDale: November30,2005 Basic Information -Ck xZr currvaer t, Iraidwond Alfected Facility: #-#"V1' .JXWfqd "Veem DsCv Date:. 1i30/2005 11:50 howz Discovered Codr6S 1102 Event Date: 11/30/2O05 11:50 Affected Unit: 00 Afeccted Sys:
Subject:
ELEV/tED TRlTIUM LEVELS IN 'ON-SITE MONITORING WELLS Required Information Condition
Description:
Elevated levels of tritium htave iocently been Identified in certain on-site groundwater sampling wells:
The oxact source has not been located nor has (tnsourco been dletennined to be activo or historical.
Immediate actions talken: An issue management leam has beon formed to address IIis'issue. Tl6 team vwill address characterization of tle exlent of the elevated Iitium levolsIncluding Ithe potontial for elevated levets off-sile; identificidion arid eliminalion of tile source if still active; reniedialioni of the affect ed areas; communications With government agencies and nrty polontially affecctel nmnibtrs of the public; nnd regulatory Interlace.
Recommendattion for acilon: Thn issues rtaffgtonmol leam will iiddrois the iminediate actions requioredl or tiis issue. A rool 6use should be iritiakid to document the immediate actions, as well its to capture thofcauso, tdditionil extent of condition Invesliga ions, anrd corrective nc ions to prevent recurrence. Also, thle stalion's documentalioni of previous lIaks in accoidan=6 with 10 CFR 50?5.(g) nedo(s to lIJ revieVicd.
SSupervisor Verbally John Moser Contacted Optional Additional Information Whlai activities, processes, or :nie elevaled levels o eie dib6%vered in monitoring weils that were reccnily installed to providre.
-roe lnvoivetl? enhanced b ground water monitoring capability, procedures wore Involved? ii9 aabliy Wily did tIhe &oridlilbn Unkitown. Il ls believed Ithe soutce may be from historiisal vacuum break:or teaks, but this needs utohi happen? confimied. -
Whiat are the consequences? Undesired clevaded irilium levels on site property. potential for Ihtese olevhled levels to have unlgrated off-sile.
Any procedural requirements None.
impacted?
Identily any adverse physical As described above.
conditions:
List of Ktnowiedgeable John Moser Individuals: Jim Gosnell Dale Ambler Is this a repeat or similar The discovery is part of an oxpanded sampling program as discussed above.
condition?
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'IuI9r GWP jaw foR PIF #: A2000-04281 ORIGINATOR l
Title:
Failed Circ Water Blowdown Vacuum Breaker Caused Unplanned Flooding Outside of the Power Blocl Event Date: 11106/2000 EventTime: 02:30 PM Discovery Date: 11/06/2000 Discovery Time: 03:00 PM Unit: 00 Unit Mode: 1 % Power: System: CW
,EPN: 'OCW1 35.OCWi 36 Location: OTHER OCCUREDIDISCOVERED WHILE PERFORMING:
ARV: WR#: WRTASK#:
SURV #: RWP # . QRI/RIN #f:
OOS # : PCE #: OTHER# Followup inspection OTHER DESCRIPTION Circ Water blowdown corridor-east of plant PROBLEM DESCRIPTION I RECEIVED A CALL FROM THE ILLINOIS ENVIRONMENATAL PROTECTION AGENCY (BILL PAPADAKIS) ABOUT A REPORT OF WATER STANDING INTHE DITCH AT SMILEY ROAD. HE SAID THIS HAS BEEN THERE FOR A WHILE AND WE HAVEN'T HAD ANY RAIN UNTIL TODAY. HE ASKED IFI HAD ANY IDEA WHERE IT MIGHT-BE COMING FROM. I SAID I DIDNTKNOW BUT WOULD LOOK INTO IT AND GET BACK TO HIM. I NOTIFIED CAL WALRATH (2202) OF THE CALL AND SAID I WAS GOING OUT TO LOOK, AND THAT I SUSPECTED IT MAY BE A VACUUM BREAKER PROBLEM ON THE BLOWDOWN LINE, WHEN I APPROACHED THE VACUUM BREAKER (CONTAINING VALVES 0CW135 &0CW136), I NOTICED WATER POURING OUT FROM THE MANHOLE COVER. THE ENTIRE AREA WAS SATURATED. UPON ARRIVAL BACK AT THE PLANT- I UPDATED THE OCC WITH THE RESULTS. ARRANGEMENT BEGAN TO PUT TOGETHER THE APPROPRIATE WORK PACKAGES AND OPERATING BEGAN LOOKING INTO ISOLATION 'OF THE BLOWDOWN FLOW.
KNOWLEDGEABLE PERSONS: Louis Rhoden, Carl Dunn, Mark Trusheim, Bill Vandermyde IMMEDIATE ACTION TAKEN I NOTIFIED BILL POPADAKIS (IEPA) OF WHAT I HAD FOUND. I EXPLAINED THE SOURCE OF THE WATER AND.A DESCRIPTION OF THE.AREA. HE STATED THAT HE WOULD NOT NEED ANY WRITTEN FOLLOW UP AT THIS TIME AND SINCE THE WATERWAS CONTAINED IN THE DITCH. WE DID NOT NEED TO SAMPLE. THERE WERE NO NPDES PROBLEMS. I TOLD HIM I WOULD UPDATE HIM WEDNESDAY MORNING. OPERATiNG FOLLOWED UP BY SHUTTING DOWN BLOWDOWN FLOW.
AR # : WR #: WR TASK# :
TIFITRR # : 'PROCEDURE # ER #:
HOLD TAG # : REJECT TAG #:
ORIGINATOR: Joseph Tidmore EXT: 2299 DEPT: *CH ORIGINATED DATE: 11107/00
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16- 1916 32 49X 49X 1716 45X 49Y 49X 1316 33X 60X GOY 1216 454 55X 55%
SIZES 3 & SMALLER. SEEOULEttlN 586 LARGER SIZES nEADILY AVAILABLE - CONTACT FACTORV.
ISteven Orth -Re: CW Blowdown vacuum breakers Pg1 From: Richard Skokowski To: Gregory Roach Date: Wed, Nov 30, 2005 4:18 PM
Subject:
Re: CW Blowdown vacuum breakers thanks
>>> Gregory Roach 11/30/05 4:17 PM >>>
Rick, A quick synopsis with a copy of 2000 root cause CAPR's and 2005 IR response to NRC inquiry to follow.
In 2000 the licensee experienced a failure of the #2 vacuum breaker(VB) in the CW blowdown system which resulted in flooding of the area in the vicinity of the VB. The licensee determined that the VB failed to due to fatigue failure (# of cycles over lifetime) of the valve float assembly. This was exacerbated by the lack of surge protection for the float assembly which seals the valve shut when the piping is full of water. A water hammer appears to have damaged the unprotected float preventing it from sealing shut, allowing an estimated 3 million gallons of water to escape. The CAPR's included installing a surge protection feature on the VB's and modifying the preventative maintenance program for the VB's.
In May 2005 the licensee identified a 20 dpm leak from the pilot valve of VB-1. Tritium contamination was limited to the VB-1 well which is in the vicinity of the switchyard with no tritium leaving the site boundaries.
The escape path for the water through the pilot valve is significantly smaller than that of the main valve, hence the much smaller release of water. Following NRC inquiry, the licensee responded that the elastomer components In the pilot valves are subjected to higher pressures and are subject to the corrosive effects of the raw water they are exposed to. The licensee's response to the NRC RIO inquiry stated that they were making additional modifications to their PM program and again increased the rate of visual inspections.
CAPR's and IRto follow.
Greg CC: Steven Orth
§Steven! Orth - Re: Tritium Contacts Pg ¶ From: Richard Skokowski To: Nirodh Shah Date: Wed, Nov 30, 2005 4:26 PM
Subject:
Re: Tritium Contacts Thanks
>>> Nirodh Shah 11/30/05 4:25 PM >>>
Rick, here are the people that Bwd contacted re: the tritium:
IEMA: Asst. Director Wright Cecil Settles (no title provided)
Mike Parker, Nuclear Facilities Mgr. (Cecil's boss)
Rich Allen, Environmental Manager Corinne Gordon, Illinois District Representative (i.e., State Congresswoman)
Tom Dahl, Illinois State Senator Mayor of Braidwood The licensee did not contact county officials or the mayor of Godley. The licensee was in the process of contacting the IEPA and should get the names to us by the morning.
thanks..N CC: Roland Lickus; Steven Orth