Similar Documents at Byron |
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Category:Report
MONTHYEARML23321A0452023-11-17017 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 BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 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 BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment2022-10-13013 October 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment 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 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 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 BYRON 2020-0085, 10 CFR 50.59 Summary Report2020-12-10010 December 2020 10 CFR 50.59 Summary Report BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report2020-12-10010 December 2020 10 CFR 72.48 Evaluation Summary Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1592020-07-10010 July 2020 Attachment 1 - Description and Assessment 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 ML20195B1612020-06-25025 June 2020 Attachment 6 - Intertek Report No. Aim 200510800-2Q-1(NP), Byron Unit 2 Operational Assessment Addressing Deferment of B2R22 Steam Generator Tube Examinations to B2R23, April 2022 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18192C1522018-07-18018 July 2018 Review of Fall 2017 Steam Generator Tube Inservice Inspection Report ML17355A5612017-12-21021 December 2017 Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000454/2017009; 05000455/2017009 (DRS-N.Feliz-Adorno) ML17234A4782017-08-22022 August 2017 Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE 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 ML16344A0062016-12-0909 December 2016 10 CFR 72.48 Evaluation Summary of Biennial Report of Changes, Tests, or Experiments, Performed 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. 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) ML16356A0202016-10-0707 October 2016 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. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. RS-16-122, Spent Fuel Pool Evaluation Supplemental 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 of Insights from Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental 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 of Insights from Fukushima Dai-ichi Accident 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-16-088, 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)2016-07-15015 July 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-16-073, 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 RS-15-267, 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)2015-11-30030 November 2015 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-15-072, Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 542015-02-12012 February 2015 Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 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 ML14128A5562014-06-30030 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 ML14085A5332014-05-29029 May 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 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 BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill2014-03-27027 March 2014 Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill ML14079A4232014-03-12012 March 2014 Enclosure 1, Byron Nuclear Generating Station, Flood Hazard Reevaluation Report, Revision 0 ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event RS-14-082, ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report2014-02-27027 February 2014 ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report BYRON 2014-0003, Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-02-13013 February 2014 Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate ML13225A5952013-12-17017 December 2013 Interim Staff Evaluation Related to Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) 2023-09-29
[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 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 ML18192C1522018-07-18018 July 2018 Review of Fall 2017 Steam Generator Tube Inservice Inspection Report ML17355A5612017-12-21021 December 2017 Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000454/2017009; 05000455/2017009 (DRS-N.Feliz-Adorno) 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 ML16344A0062016-12-0909 December 2016 10 CFR 72.48 Evaluation Summary of Biennial Report of Changes, Tests, or Experiments, Performed 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. RS-16-122, Spent Fuel Pool Evaluation Supplemental 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 of Insights from Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental 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 of Insights from Fukushima Dai-ichi Accident 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-16-088, 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)2016-07-15015 July 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-16-073, 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-15-072, Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 542015-02-12012 February 2015 Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 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 ML14128A5562014-06-30030 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 ML14085A5332014-05-29029 May 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 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 ML13225A5952013-12-17017 December 2013 Interim Staff Evaluation Related to Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13182A0312013-07-0303 July 2013 Transmittal of Final Byron Station, Unit 2, Accident Sequence Precursor Analysis 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 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 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 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 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 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 RS-12-162, Company, LLCs 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Company, LLCs 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12341A1622012-11-0707 November 2012 Byron Generation Station, Unit 1, 12Q0108.20-R-002 Rev. 1, Seismic Walkdown Checklist (Swc). Part 2 of 2 RS-12-161, Byron Generation Station, Unit 1, 12Q0108.20-R-002 Rev. 1, Seismic Walkdown Checklist (Swc). Part 2 of 22012-11-0707 November 2012 Byron Generation Station, Unit 1, 12Q0108.20-R-002 Rev. 1, Seismic Walkdown Checklist (Swc). Part 2 of 2 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 1 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 1 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 RS-12-161, Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 22012-11-0707 November 2012 Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 2 ML12341A1662012-11-0707 November 2012 Enclosure 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2, Report No: 12Q0108.20-R-002, Revision 1 ML12341A1652012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 ML12341A1642012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 ML12341A1612012-11-0707 November 2012 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 1, Report No. 12Q0108.20-R-001, Revision 1 2023-11-17
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01,Glo Back Print, I New Search I kome, Go Back Print.I New Search I Home AR 00200745 Repo t Aff Fac: Byr0o AR Type:. status: H/APPR AfflUniit: NA OWed'To: AcAOALL Due bate:
AfftSystem: ,FW Event.
iOate,0 : 02/06/ý2..1004' CR Disc' Date!: 02/09/2004ý HoW rig Date: 0*2/102004 0101 Discovered:
Action RequestDetails,*
Subject:
- FeedwatrFlow eTr-acer Test!.Preliminary.esults Delscripticon:
'Identifie-d byi'(Name):
fBliANR L.EDGER
,Condition D*escriiti6h:
'Th'T~~erTes'Prlirinai~yresults ~sho6W'that'-the venturi measured- low Is 06% loiwer than -thestracer measured unitv ,*andthe hfiowfo-ui:
measured floW q.2,% lower than the tracer. measured low forý,unit.2. ThefW.
- Tracer*'test',was
- ccrnducted oi*:n '*6,2004.
,Specific Pireliminary*resultsofhe.trace indicat'the following:
Planrit: eeading'r(ntUt-fiYUitC'1 15 96500' lb/hr Un ,it2, 2i158910i 0lbJI/h~r Tracer- result. Unit ,l.16 , 060'644 lb/hr, Unit 1 2' 15,9268S371 lb/1r Stahd. deviationh tracee-Unit 1 0.4,.% Unit 2 0'-3%/o Devl planttr~ager, tnit' -0.6 % Unijt~2. 2`1'%
Preli!ini 'AMAG, drossfl6w hM'easurerni'"e'nts:.'dur"in'g the race- testfunit 1.
a re. 18lWer'fl~pw thahi.invet'uri, and ,on wilt 2are 'P/a 6ibi~etha~nVentn.
'There; is!.,no 'immIediate Ipla.ntiip -Act bdc'a~se:th'e-&r6c~ereul aeti the uncerain6y.ofthe square' rbootsumn bf.:the:'squar-es!'wit. verit~riir.-AMG Crossfl, 'urre ntl *in use): readings'sare .not within ;the uncertainty o:6ftthesquaýre ro~t'sumr of the"sQ'souares ,with:'the ,tracier testý:an~d therefore.
-should not beusedw e A din* tO theudsecision tree thtat .was, developedfor data' comparison, Tracer fellinto case_2., ase 2 state'sitheaith,a'htthue -is* cod'rnE'is;o rrect and&rossflow s*ouid not:
be implemented.
A'preliminay rtnari review (Exe!16n E'ngineer~ing, A.`31B, Westingh'ouse) Ofthe
,tra~er*st~lhs in~ tb~een ii blezt fi nd.,any dijsrepancy-th~t .would invalidatei the. reseiults "of the tra'ce'r ýe A~susch-; n'oftirther'tracer~test' is plannedat Byron.
Final report of iesults1Willrbe by rEC evaluatioh. This, E' will contain final, reports1 informatibn;frorn Tracer TstesEVrnturi Flow da't, and Westinghouse/AM.ýG final report n Crossflow Measurement:
1,rtn :/ccc mvaO.1 :6 l2.3iservler.Reno~rtAR 2/1.0/200'4 h(tr):HcCcmva01-6I B/serviet/ken6ftAR
How-discovered:
Uiata:Ta en. during iWtracerSPO-O
'Immediate actions taken:
Perfomed. a team reviewiof the results.
MWestinghou se~isJý, preparingPa n a ction planh to..address ýthe industry`impct.,
Namejl&-o'rga'niz'ation:If'supervis r,,pprs nai ntfied to perfbrrm
'SupervisoryReview:
~ Optional Setion *****
Whatactivities, processes,-or piroedues were involved?
SPP o4,ýao1:
-:WYhydid the.cdhditi-on happeh?...
Results* 'ere :obtainied 'with'in*tihe b iuhdn .oa 1provel' mrethod of determining.
f.eed'water fl~ow With- Na24, trac'e-..
What aýre the cdnsequenices?:!
Preliminary tracer res'ultsare consistent',with' ven'turi flow measuerements,:
but not AMAG Cros-sflopw mneasuremenlý.,
- Were-any p~r cepdurialý trequi rerrierntsiýrpacted?'
None Were ihysical eohditibon[ý?
&6hedeanyadve"S Identi, who was.notified?
D.]Spitzer, B. Adarns, D..Eder, T. Printz,. .Drowle'y;, W..Kuba T.a, Drai (B WD)
"Listo, knowledgea6le individuals:-
D- Sp tze B. Adams; D. Eder, T. Printz,:. Drowley, W. Kouba 3..TrauLb (ABB):
Repeat*orsimilar; conditionr?
No. FW "flo'wtracetesiý.(t has "no.tIbeen.perform.ed previously at. Byron .o Braidwood.
- upe'r.Visoiy Reviewe4r :C~rnr~ient~s S'ection,*****
.Name of(Supervisory, Reviewei: 'Brian Ledger provide~a'clear-statemefit fi the Pro'b15fi afiCoSqpece, .ifnecessary:
No additional information..
Recommendedsig nificane.ILevel ndI~Cl:a, (providi a basis for Level 3'andl Ealbove):
.4D:
Identify. additional acttions taken teo 6e taken (For' actions not already completed inc ude Action de5scr ption.,'"quired Assignee, ahd-proposeddiIe Formalize the r~esults.
h .tp./cc/Cnva0 l:61 23/servlelt/R epcrtAR 2/10/2004
,SUbje IctlDescriptio n:
Assign #: 06, Assigned, To: StatU!: INPROG Aft Fac: ,Byron Prim:G'rp: ACAPALL Due Pate:
'Assign Type:' CA Sec Grp:T Oig'Date:
Priority:,
Schedule. Ret:,
Unit,-Cndition:
Subject/Description: Corrective Ac'tio',
Aissign. 67,Asge o Status: IRQG Aff Fac: Byron Prim Grp: AC.AAPALL Due Date:
Assign TyOpe:. EFR Sec Grp: Qrig Date::
Priority:
.Schedule R-ef:
Unit :Condition:::
,EffectiVeness.Review* (Rev;2) 1Every'CAPR! mst beevaluated by.'its own .EFRs Subject/Description: assignment.. 2'. Collective EFK, revilew requireddisper RC"invetigatidnrvlC approval is equired fo:
........ ectiVe EfRs: ,Extensionst'o.Collective EFRs that have eben,.hallenged 08 MAssign.# Assigned To:- Status: INPROG:
Aft Fac:i Byron Prim Grp: ACAPALLDue'Date:
Assign Type:, OPDB Sec Gr'p orig. ate:
Priority:
Schedule 1fet:
Unit C6nditiofn:'
Subj6ct/Descriptio n: Opefability Detenffiiriati6h Assignl#:: 'Io Assigned To: Status:, NPROG Aft FaC: Byron Prim Grp: ACAIALL Due Date,:
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'Assign #: 141 Assigned'To: Status- INPROG Aft Fac: By~ron Prim Grp: ACAPALL Due Date:
Assign Type: ::EACE Sec 'Grp: Orig Date':
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Unit Condition:
,Subjiect/Descriptirn: Equipment Apparent Cause Eva uatidin ý(EACE) (Rev. -37)
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Priority:,
Scheduie Ref:
UnitCondit ion:
SubjectDescription: Performi ACE (Rev. 3 Assign #1 13 Assigned To: Status: INPROG Aft Fac: Byrn Prim Grp: A.APALL Due Date:
Assign Type: RCR Sec Grp: Orig DAte:
Priority:
Schedule Ref!
Unit Condition:,
Subject/Description: Perform Root:Cause Analysis,0f.Coridition (Rev. 33) Ektensiohnsof -thihs assignimentrequjire b~~j s c d ,Vo :
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Assign #1 14 AssignedT:: ;StatUSi INPROG Aft Fac: Byron Prim'Grp: ACAPALL 044e6Date:
AssigfiType: CCA SecIGrp: Orig Date:
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UnfitCohdition:
Perform'a Co6mmon .CausieA'Analis (Rev,,ý.2) Extension~ofi*,this .assinment reqUir-eSMRC Subjet/Decripion:Approval Assign*'#: 15 AssgnddTo: -Sats INPRO Aft Fac: Byo6n Prim Garp: ACAIALL Due&Date:
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Subject/Description: Sto Develop;a R6otCause Cha'rfterrev. 3).Completion of a Root Cause Charteris expected be comp.leted within two buisiniess days of ive'6t screening "
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Assign #6 __ Assigned To: Status,, INPROG AffFac: Byon Prim Grp: ACAPALL Due Date:
Assign Type. ACE Sec Girp: Orig Date:,
Priority:
- Sche~dul!e Ref}.,
UnitCo*nditi6n:,
Subject/Description: Perfo'rm, ACE (Rev..4)
Assign #: 17 AssignedlT.: Status: , INPROGd Aff.Fac:; Byr n. Prim .Grp: ACAPALL Due Date:
Assign Type: kDt:e ACE Sec Grp: Orig Priority!:
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SiubieclD~esc~ription:: *Per*form-Qiu~ic.k AE(Rv E(e* 4)
Assign #-: ý18 Assigned To: Status:: INPROG AftFac:. ByronB Prim Grp: ACAPALL Due.Date:
.AssignrType: EACE Sec Grp: Orig Date:
Priority:..
"Schedule:Ret:
Unit'Conrdition:
'Subjet/Description: Perform"EACE (Rev. 4'4)
Assign #i 149 Assigned To: -Status. INPROGý AffFac: BRAOn Prim :hGrpi: AcAPALL Dube a*te:,
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Schedul. ,Ref:-
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SUbject/Descriptibn:: NPe*f*ormCCA(Rev* 3).
Assign§: 20, AssigneddTo:. Status:: INPROG Akff-ac:: Byron Prim Grp:.. ACAPALL Due"Date:
Assign Type: RcRk Orig .Date:
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Subject/Description: Perform-RCA (RepS> 4)
,Assign.#: 21 Assigned To: Status: INPROG Aft Fac: Byron Priim Grp:
t ACAPALL Due Date:
Assign Type: RCCH secGrp: Ori!igDate:
.Priority:t
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UntC6oiidition:
SubjecDescri'ption:; hComplete.Root Ca*ue§ Chae r ,rter,(Rev.
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