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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:Technical
MONTHYEARRS-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 BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 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 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-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) 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) 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-16-057, 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-15-259, 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-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 ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology RS-14-064, Section 5 - Summary of Regulatory Commitments2014-03-31031 March 2014 Section 5 - Summary of Regulatory Commitments ML14091A0062014-03-31031 March 2014 Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report RS-14-064, Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report2014-03-31031 March 2014 Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report 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 RS-12-159, Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 12014-02-13013 February 2014 Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 1 ML14119A3772014-02-13013 February 2014 Enclosure 1 to RS-14-034 - Update Transmittal 2 (Annex B) Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic ML13338A6242013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Braidwood Station, Units 1 and 2, TAC Nos.: MF0895 and MF0896 ML11206B1802011-07-20020 July 2011 ARS1-11-01372 - Braidwood Water Sample Results RS-12-023, WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5).2011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). ML12083A1232011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). ML1117900382011-06-23023 June 2011 Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1117900422011-06-21021 June 2011 Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1110902792011-04-15015 April 2011 ARS1-10-02678, Revised Laboratory Analysis Report. ML0925202652009-09-0404 September 2009 Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) ML0918110302009-06-30030 June 2009 Startup Report for the Installation of Areva Np, Inc. Advanced Mark-BW(A) Fuel Assemblies in Braidwood Unit 1 Cycle 15 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML17255A8412008-06-30030 June 2008 Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted2008-06-30030 June 2008 Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted2008-06-20020 June 2008 Braidwood, Units 1 and 2 - Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted ML17255A8392008-06-20020 June 2008 Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted ML0910702272008-01-31031 January 2008 Guidance for Post Fire Safe Shutdown Circuit Analysis ML0802304842008-01-14014 January 2008 Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report RS-07-100, Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report2007-06-22022 June 2007 Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report RS-07-059, Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2.2007-05-0303 May 2007 Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2. ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier RS-06-039, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors2006-03-31031 March 2006 Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors RS-05-129, LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2.2005-08-31031 August 2005 LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2. ML0522900832005-08-19019 August 2005 Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors ML0503304802005-01-24024 January 2005 Pressure and Temperature Limits Reports (Ptlrs), Revision 3 2023-04-20
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Go Back Print l New Search l Home AR Number: 00792215 Linked ARs Aff Fac:BraidwoodAR Type: CRStatus:APPROVEDAff Unit: 00Owed To: A8952CAPDue Date:09/29/2017Aff System:
MSEvent Date:06/30/2008 CR Level/Class:
4/DDisc Date:06/30/2008 How Discovered:
H02 Orig Date:06/30/2008 Action Request Details
Subject:
MSLB CALC ENERGY RELEASE ERROR
Description:
Originator: Supv Contacted: Condition
Description:
During the EC 371293 evaluation, an error was discovered in the Unit 1main steam line break outside containment energy release calculation. ThisIR is the Braidwood parallel to Byron IR 792213. With the ReplacementSteam Generators (RSG), Framatome provided the Mass and Energy (M&E) release calculations which were used as input to the Reference 1 RSG containment evaluation and Main Steam (MS) tunnel evaluations in Appendix
B of Reference 2. In EC 371293 it was concluded that the energy releaseedits used in Reference 2 for Unit 1 were thermodynamic internal energy, not the required edit for enthalpy.The Reference 2 calculation did not document an evaluation for poweruprate. The Reference 1 Framatome calculation was analyzed for 102% of3411 MWt down to 30% of 3411 MWt for a steam line break inside containment. B/B units 1 and 2 are currently licensed to 3586.6 MWt.Reference 1 was analyzed to a conservative initial SG pressure of 1131.5psia which covers the current full power pressure. Hot zero power has higher SG pressure and larger initial water inventory in the SG than fullpower which was also not evaluated, although it may be non-limiting forpeak steam line tunnel pressure depending on the assumptions used.Therefore, the Reference 2 M&E used for Unit 1 had several items that needre-evaluation and documentation with respect to the current design basisM&E for the short term of a steam line break outside containment.In addition, while comparing M&E tables in the UFSAR with the M&E tablesin Reference 2, it was noticed that the UFSAR Tables 6.2-50 and 6.2-50ahave a typo listing Energy Rate units as (MBtu/Lbm) when the values shownshould have been labeled (MBtu/sec) .
References:
1.FTI Document 32-1239267-00, RSG Evaluation of MSLB inside Containmentwith CONTEMPT and associated M&E transmittal FTI 32-1258100-00 (SUPERSEDEDWITH WESTINGHOUSE POWER UPRATE CONTAINMENT CALC)2.Design Analysis #3C8-0282-0001, Rev. 3, Main Steam Tunnel Pressure Studyfor Main Steam Line Break,Page 1of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet Immediate actions taken:
EC 371293 determined best estimate M&E releases for 3586.6 MWt currentfull power operability under ATI 790428-02. Informed Byron & BraidwoodDesign Engineering Supervisor and Corporate Design Engineering Supervisorof issue. Byron & Braidwood engineering already had S&L perform an immediate operability evaluation basis under ATI 790428-02 which includedthe EC 371293 corrected M&E tables.Recommended Actions:1.Byron & Braidwood engineering to have Westinghouse or others perform are-constituted calculation to support a corrected M&E input table and main steam line tunnel pressure calculation to replace 3C8-0282-0001 includingpower uprate and hot zero power evaluation.2.Byron & Braidwood regulatory assurance to correct typos in next UFSARupdate for Tables 6.2-50 and 6.2-50a to have Energy Rate units labeled (MBtu/sec)3.Byron & Braidwood engineering to perform a DCR type EC for revisions tothe Reference 2 calculations with the new M&Es and power uprate evaluation.What activities, processes, or procedures were involved?Corporate performing of EC 371293 to support ATI 790428-02What are the consequences?Analytical Unit 1 Main Steam tunnel pressure will increase under steam line break conditions when the error is corrected. There is a consequence to revise calculations.List of knowledgeable individuals:Operable Basis:Unit 1 and Unit 2 steam tunnel and AF tunnel hatches are Operable based onevaluation performed per Op Eval 07-007. The errors in the MSLBcalculation have been evaluated/compensated for in this Op Eval.
Reportable Basis:The EXELON Reportability Reference Manual decision tree was reviewed, and no reportability requirements were identified.SOC Reviewed by: 07/02/2008 08:39:25 CDTSOC Comments:(7/2/08 ) Design Eng.
Reviewed by: 07/02/2008 13:22:59 CDTReviewer Comments:
The following response was provid ed by the originator of IR 792215:The energy error only affects calc 3C8-0282-001. The error was onlypresent in Framatome Document Release Notice 32-1258100-00, which wasused for Unit 1 in calc 3C8-0282-001, Appendix B. The purpose of theinformation sent to ComEd B/B Units 1, which contained the energy error, was for SLB steam line break subcompartment analysis following high energy line breaks to be used by Sargent and Lundy for subcompartment analysis. Calc3C8-0282-001 is the only analysis which accomplishes this purpose.Correction of the energy error was determined in EC 371293. This EC alsodetermined "best estimate" mass releases to be used for operability. Whilethe energy was increased, a significant reduction in the Unit 1 steam linePage 2of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet break peak mass flows were obtained compared to the mass flows used incalc 3C8-0282-001, Rev.3. The two effects tend to offset each other basedon engineering judgment. The increased energy produces more pressure inthe MS tunnel; and the lower peak mass release reduces peak pressure inthe MS tunnel. The Mass & Energy releases in calc 3C8-0282-001, Rev. 3 for Unit 2 from Westinghouse remain bounding compared to the EC 371293 bestestimate mass and energy releases. The peak tunnel pressure of 19.7 psigfor Unit 2 in calc 3C8-0282-001 remains bounding for both units, if noother changes to the inputs in calc 3C8-0282-001 are considered. It is notknown which structural calcs used the output of the 3C8-0282-001 calc,however, assuming the 19.7 psig was adequate for the tunnel walls on Unit2, the Unit 1 walls with the same design can likely withstand the samepressure.The combined effects of the energy error with other issues are addressedin Braidwood Operability Evaluation 07-007 Revision 4 since thatoperability evaluation used the corrected best estimate mass and energyreleases.Other subcompartment analyses not affected are:Westinghouse calc CN-CRA-00-16 was performed to address Unit 1 outsidecontainment pressures and temperatures for Power Uprate. Westinghouse developed their own detailed M&E tables for various scenarios and performed the containment analysis. This calc did not use any of theFramatome M&E data.Westinghouse calc CN-CRA-00-18 was performed to address Unit 2 outsidecontainment pressures and temperatures for Power Uprate. Westinghouse developed their own detailed M&E tables for various scenarios and performed the containment analysis. This calc did not use any of theFramatome M&E data.Westinghouse calc CN-CRA-00-39 was performed to address peak MS tunneltemperatures for Power Uprate. Westinghouse used the CN-CRA-00-16 andCN-CRA-00-18 mass and energy tables. This calc did not use any of theFramatome M&E data.UFSAR section 6.2.1.2 based on WCAP-8082, WCAP-8264, and WCAP-8077(Section 6.2 ref 6,7,8) addressed MSLB in the pipe chase compartmentswithin containment. These WCAPs could not have used any of the FramatomeM&E data.In conclusion, Operability Evaluation 07-007 Revision 4 approved 7/1/08was not affected by the errors identified in IR 792215. No otheroperability concerns exist due to the errors identified in IR 792215.
Reviewed by: 07/02/2008 22:34:10 CDTReviewer Comments:Create corrective actions for revision of calculations and associated documentation.Department review performed by: 07/17/2008 15:38:42 CDTEvaluation Comments:Condition/Problem Statement:The originator identified an error in the calculation which establishesthe mass and energy release to evaluate a high energy line break in theMSIV RoomsStatement of Cause:Errors and assumptions were not correct in the calculation.Page 3of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet Extent of Condition:As discussed in the followup, this item only impacts the mass and energyrelease used to evaluate a high energy line break in the MSIV Rooms andnot any other design basis calculation.Evaluation of any SOC Comments:
As requested by the Shift Manager, actions need to be developed to correctthe calculation, UFSAR, and other supporting documentation. Assign an CAATI to A8952DER with a due date of 8/13/08 to coordinate with ByronEngineering to develop an action plan on resolving issues with thiscalculation. This is consistent with the actions initiated by ByronEngineering and discussed in IR 792213.Page 4of 10 Full Action Request Report 8/31/201 7 http://eamgenco.ceco.c om/cap/servlet/ReportFullARServlet Assign #: 01 AR #: 00792215 Aff Fac:BraidwoodAssign Type:TRKG Status:COMPLETEPriority:Assigned To:Due Date:07/18/2008Schedule Ref:Prim Grp:ACAPALLOrig Due Date:Unit Condition:Sec Grp:
Assignment DetailsSubject/Description:MSLB CALC ENERGY RELEASE ERROR Assignment CompletionIn Progress Notes:Completion Notes:Page 5of 10 Full Action Request Report 8/31/201 7 http://eamgenco.ceco.c om/cap/servlet/ReportFullARServlet Assign #: 02 AR #: 00792215 Aff Fac:BraidwoodAssign Type:
CA Status:COMPLETE Priority:Assigned To:
Due Date:08/13/2008Schedule Ref:
Prim Grp:A8952DEROrig Due Date:08/13/2008Unit Condition:Sec Grp: Assignment DetailsSubject/Description:Coordinate with Byron Engineering to develop an action pl an on resolving issues with this calculation and other supporting documentation.
Assignment CompletionIn Progress Notes:****COMPLETE FOLLOWING STEPS PRIOR TO COMPLETION OF ASSIGNMENT****1. Prior to start of work on the completion of any CA, ensure you havereviewed the associated CR, investigation, this assignment, and ifnecessary contact the originator to ensure a complete understanding of therequested action.2. Implement the requested actions. (e.g. Procedure should beimplemented not submitted for change)3. Document completion of action by completing each field in thefollowing form or marking NA.
- 4. Additional guidance is provided by clicking here .. :Record of Extensions: (Note: Record the date, justification and approvalreceived for each extension)
NoneDocument Corrective Action: (Note: Restate the requested action)Coordinate with Byron Engineering to develop an action plan on resolvingissues with this calculation and other supporting documentation.Document the Resolution: (Note: Clearly document the implementation ofthe Corrective Action to the requirements of LS-AA-125 Attachment 2."That which is not documented is not done.")Consistent with Byron ATIs 653093-15 and -16 that will track theformalization of a design analysis for the mass and energy release andsteam tunnel pressurization, a Braidwood ATI will track these two actionsunder a single ATI. Additional action items will be generated to tracksubsequent documentation changes following the completion of the formaldesign analyses.Document any changes to the intent of the original Actions (Includeappropriate Department Head Approv al): (Note: Document any deviationfrom the specific action and document the name of the SeniorManager/Director that authorized the deviation)
None.Page 6of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet Document additional assignment determined during evaluation: (Note(s):Do not close to a promise - CA Type Assignments can only be closed toanother CA Type Assignment on a CR)CA ATI 792215-03 (due 11/21/08), Track completion of design analyses forthe steam line fault mass and energy release and steam tunnelpressurization. Initiate additional actions to revise supporting documentation such as the UFSAR.Quality Signoff: (Note: Document the name of the person who isaccountable for the completion of this assignment.)
Name: Date: 8/7/08Document Additional Details here:Completion Notes:Page 7of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet Assign #: 03 AR #: 00792215 Aff Fac:BraidwoodAssign Type:ACIT Status:ACC/ASG Priority:Assigned To:
Due Date:09/29/2017Schedule Ref:
Prim Grp:A8952MECHOrig Due Date:11/21/2008Unit Condition:Sec Grp: Assignment DetailsSubject/Description:Track completion of design analyses for the steam line fault mass and energy release and steam tunnel pressurization. Initiate additional actions to revise supporting documentation such as the UFSAR.
Assignment CompletionIn Progress Notes:ATI being extended to September based on technical evaluation related tothe issue being expected to be completed in August. Further actions to revise formal calculations will be developed at that time.This ATI and ATI 1599160-01 are being extended to 8/18/17. Braidwoodengineering is currently planning a face to face meeting with ByronEngineering to determine the appropriate course of action for closure ofthis issue.ATI is extended to 7/31/2017 due to issues that need to be addressed byCorp and outside expertise. approved this extension on6/28/2017.
- ATI is extended to 6/30/2017 due to issues that need to be addressed byCorp and outside expertise. approved this extension on5/25/2017.
- ATI is extended to 2/23/2017 based on the following:
Due to Emergent Issues and the A1R19 Refueling Outage, additional time isneeded to review the issue and the extensive analyses. This ATI is being extended to 2/23/2017. ( 11/7/2016). The acting manager,, approves the extension.
- Update by , BRZYP, 8/30/2016
- The Responsible Engineer has been transferred to Plant Engineering,Primary Group. This assignment has been re-assigned to
.Additional time is necessary for to review the issue and the extensive analyses. The due date is extended to 11/18/2016. The DesignEngineering Senior Manager has approved this extension.
ATI Assignee Change - 3/1/16 - Re-assigned to based on retirement.
ATI is extended based on the action plan presented below:ATI extended to 8/31/2016.
Extension concurred with MECH Design Branch Manager
.MSIV Pressurization issue Closure Plan.Page 8of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet Action Assigned to: Status Completion dateCollect Review Comments from Byron*/Cantera and Sargent & Lundy for In-progress 2/19/2016 EXELON Comment Review meet ing 2/29/2016Exelon/ENERCON comment resoluti on 3/3/10/2016Byron/Braidwood OAR BRW:BYR: (TBD, ) 03/17/2016Revise MECH/Structural Calcs1. 3C8-0282-001 (MECH)2. 5.3.2-BRW-13-0206-S
- 3. 5.6.1-BRW-13-0204-S
- 4. 5.6.3-BRW-08-0040-S
- 5. 5.6.3-BRW-08-0045-S
- 6. 5.6.3-BRW-13-0205-SAddress Analysis 5.6.3-BRW-07-0051-S/5.6.3-BYR07-040.This 2007 calc uses analysis 3C8-0282-001 Rev 3 which has been replaced byRevision 4. Revision 4 will be superseded BRW: TBDBYR: (TBD, ) 07/28/2016Close ATI 01599160-01 BRW: 07/28/2016 Byron/Braidwood 50.59 Eval Prep:
Review. : 08/01/2016Byron/Braidwood UFSAR Change (DRP) 08/01/2016Byron EC 404484 (TBD, ) TBDBraidwood EC 396348 ( ) 08/30/2016Close ATI 00792215-03 BRW: 08/31/2016 Byron Point of Contact (Not officially assigned to theproject) - December 14, 2015 - Moved due date to 2/11/16 - justreceived product, need to do OAR and get corporate review, booked untilthat time. - August 28, 2015 - Amended requested due date to12/15/15 - no ATIs allowed to be placed between 12/15/15 and 1/15/16 due to being a high vacation use / holiday zone. 08/28/15The design analyses associated with this action are currently evaluatedwith respect to the licensing basis of the plant. There are critical parameters (Break type) in the calculation that has significant impact on the results of the calculation. RFPs have been requested and scope is under development to establish a new analysis.
Targeted Completion is expected by December 30, 2015. Extension has been concurred with MECH design supervisor on 8/28/2015 05/20/15The design analyses associated with this action are currently evaluatedwith respect to the licensing basis of the plant. There are critical parameters (Break type) in the calculation that has significant impact on the results of the calculation. Review of the licensing basis is in progress and expected to be completed by end of June. Based on theconclusion of the licensing review, the analyses will be revisedaccordingly and completion is expected by August 28, 2015. Extension hasbeen concurred with MECH design supervisor on 5/20/15
- This legacy issue continues to be addressed by AES. The analysis has notPage 9of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet yet been completed. This ATI is extended 3 months to allow tracking ofits completion. 10/31/13
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This legacy issue continues to be addressed by AES. The analysis has notyet been completed. This ATI is extended 3 months to allow tracking ofits completion. 07/31/13.
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This legacy issue continues to be addressed by AES. The analysis has notyet been completed. This ATI is extended 6 months to allow tracking ofits completion. 01/31/13.
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Moved to accommodate vacation, holidays. 12/20/12
.MS tunnel pressurization is considered a legacy issue and is being addressed in conjunction with several other issues. This ATI will remainopen to track final disposition and documentation of the solution to this legacy issue. The resolution to this issue is expected this year. Duedate of this ATI changed to 12/31/2012.
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ATI assignment 01284054-02 was closed to 01284054-03. Due date changed tocorrespond with the Byron ATI currently tracking this issue (ATI 01284054-03). 01/30/2012.
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Due date changed to correspond with the Byron ATI currently tracking this issue (ATI 01284054-02). 12/09/2011.
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Due date revised to 10/04/2011 to allow tracking of actions documented under Byron ATI 653093-19. 06/10/2011.
.Due date revised to coincide with Byron activity (see XREF ATI's).
.Due date extended to 3/31/2017 to allow time to resolve issues with the bases for the MS line break location and size.
Extension concurred by Design Branch Manager on 2/20/2017.Completion Notes:Page 10of 10 Full Action Request Report 8/31/201 7http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet