Letter Sequence Supplement |
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MONTHYEARRS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside.2011-04-11011 April 2011 Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside. Project stage: Supplement ML11147A1872011-05-20020 May 2011 NRR E-mail Capture - Draft Supplemental Information Request for Braidwood Station, Units 1 and 2 - Relief Request I3R-08: Alternative Requirements to ASME Code Requirements for Class 1 Pressure Retaining Welds Project stage: Draft Other ML1112605322011-05-25025 May 2011 Unacceptable with Opportunity to Supplement Relief Request I3R-08, Alternative Requirements to ASME Code Requirements for Class 1 Pressure Retaining Welds Project stage: Other RS-11-087, Supplemental Information Supporting Relief Request 13R-08: Alternative Requirements to ASME Code Requirements for Class 1 Pressure Retaining Welds2011-06-0606 June 2011 Supplemental Information Supporting Relief Request 13R-08: Alternative Requirements to ASME Code Requirements for Class 1 Pressure Retaining Welds Project stage: Supplement ML1117200082011-06-17017 June 2011 NRR E-mail Capture - Braidwood Station, Units 1 and 2 - Acceptance Review of Relief Request I3R-08, Alternative Requirements to ASME Code for Class 1 Pressure Retaining Welds Project stage: Acceptance Review ML11266A0032011-09-22022 September 2011 NRR E-mail Capture - Draft RAI Braidwood - Relief Request I3R-08 (TAC Nos. ME6024 & ME6025) Project stage: Draft RAI ML1127005992011-10-12012 October 2011 Request for Additional Information Request for Relief I3R-08 Project stage: RAI RS-11-173, Response to Request for Additional Information Related to Relief Request I3R-082011-11-0202 November 2011 Response to Request for Additional Information Related to Relief Request I3R-08 Project stage: Response to RAI ML12052A3232012-02-21021 February 2012 E-Mail to Lisa Schofield Project stage: Other ML12058A0052012-02-24024 February 2012 Request for Additional Information E-Mail Project stage: RAI ML1206006032012-03-0909 March 2012 Request for Additional Information Regarding Request for Relief I3R-08 (TAC Nos. ME6024, and ME6025) Project stage: RAI RS-12-040, Response to Request for Additional Information Related to Braidwood Station Relief Request 13R-082012-03-12012 March 2012 Response to Request for Additional Information Related to Braidwood Station Relief Request 13R-08 Project stage: Response to RAI ML12108A1232012-04-19019 April 2012 Safety Evaluation in Support of the Third 10-Year Inservice Inspection Interval Request for Relief 13R-08 (Tac Nos. ME6024 and ME6025) Project stage: Approval 2011-06-06
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23305A0412023-11-0101 November 2023 Updated Steam Generator Tube Inspection Report RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23223A0542023-08-11011 August 2023 Attachment 1 - Braidwood Station, Unit 2: Form OAR-1 Owner'S Activity Report BW230019, Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 20222022-10-31031 October 2022 Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 BW220019, Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22)2022-04-27027 April 2022 Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22) ML22031A0442022-01-31031 January 2022 Form OAR-1 Owner'S Activity Report BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021 Revision to Unit 1 Inservice Inspection Summary Report ML21202A1932021-07-21021 July 2021 Owner'S Activity Report (OAR) for Refueling Outage A1R22 BW210032, Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 20282021-04-28028 April 2021 Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 2028 BW200095, Inservice Inspection Summary Report2020-12-0909 December 2020 Inservice Inspection Summary Report BW210002, Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 32020-11-25025 November 2020 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 3 RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2020-07-24024 July 2020 Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20017A1332020-01-17017 January 2020 Inservice Inspection Summary Report NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 RS-19-084, Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval2019-08-27027 August 2019 Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants ML19030B0872019-01-30030 January 2019 Submittal of Inservice Inspection Summary Report ML18264A1552018-09-21021 September 2018 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 1 ML18208A2942018-07-27027 July 2018 Fourth Ten-Year Interval Inservice Testing Program Plan ML18208A3272018-07-27027 July 2018 Lnservice Inspection Summary Report ML17236A4572017-08-24024 August 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 ML17244A2332017-08-18018 August 2017 Inservice Inspection Summary Report ML17058A0852017-02-27027 February 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 ML17024A3982017-01-24024 January 2017 Inservice Inspection Summary Report for Refueling Outage 19 (A1R19) ML16021A0802016-01-21021 January 2016 Inservice Inspection Summary Report ML15198A1952015-07-16016 July 2015 Inservice Inspection Summary Report RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2015-05-29029 May 2015 Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML14318A2112014-11-14014 November 2014 Steam Generator Tube Inspection Report for Refueling Outage 17 RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2014-09-0808 September 2014 Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML14232A3242014-08-20020 August 2014 Inservice Inspection Summary Report ML13358A4002013-12-20020 December 2013 Inservice Inspection Summary Report for Refueling Outage 17 ML13037A5062013-02-0606 February 2013 Inservice Inspection Summary Report ML12251A3592012-08-17017 August 2012 (Returned to DCD) Braidwood Station, Unit 1, Steam Generator Tube Inspection Report for Refueling Outage 15 ML12230A2262012-08-17017 August 2012 Inservice Inspection Summary Report ML11227A2532011-08-10010 August 2011 Inservice Inspection Summary Report RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-04-19019 April 2011 Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations RS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside.2011-04-11011 April 2011 Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside. ML1103505122011-02-0404 February 2011 Inservice Inspection Summary Report ML1003302732010-01-27027 January 2010 Inservice Inspection Summary Report ML0921105382009-07-27027 July 2009 Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval ML0920502512009-07-16016 July 2009 Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14) ML0920502592009-07-16016 July 2009 Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report ML0908607152009-03-25025 March 2009 Submittal of Third Inservice Inspection (ISI) Interval Program Plan RS-08-160, Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure .2008-12-10010 December 2008 Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure . ML0829007072008-08-13013 August 2008 Inservice Inspection Summary Report for: Interval 2, Period 3, Outage 2 A2R13 Outage ML0802205262008-01-22022 January 2008 Inservice Inspection Summary Report ML0801804372008-01-18018 January 2008 Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report ML0727403892007-10-17017 October 2007 Review of Twelfth Refueling Outage Steam Generator Tube Inservice Inspection Report ML0705403462007-02-23023 February 2007 Second 10-Year Inservice Inspection Interval, Relief Request I2R-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzle Safe-Ends and Associated Alternative Repair Techniques ML0702906712007-01-29029 January 2007 Inservice Inspection Summary Report 2023-08-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2021-05-27027 May 2021 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2020-07-15015 July 2020 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.2019-09-24024 September 2019 License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies. RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)2019-09-11011 September 2019 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS) RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) RS-19-081, Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-08-0909 August 2019 Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-19-008, Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-01-31031 January 2019 Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-129, Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2018-10-19019 October 2018 Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies RS-18-035, License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference2018-04-0202 April 2018 License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) RS-18-016, License Amendment Request to Utilize the TORMIS Computer Code Methodology2018-02-0101 February 2018 License Amendment Request to Utilize the TORMIS Computer Code Methodology RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1662018-01-31031 January 2018 Attachment 1B - Braidwood Station Units 1 & 2 - Clean Emergency Plan EP-AA-1000 Pages RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1652018-01-31031 January 2018 Attachment 1A - Braidwood Station Units 1 & 2 - Mark-up Emergency Plan EP-AA-1000 Pages ML18053A1792018-01-31031 January 2018 Enclosure 1 - Braidwood Station, Units 1 & 2 - Evaluation of Proposed Changes RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors.2017-09-0101 September 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. RS-17-081, License Amendment Request to Revise Control Room Ventilation Temperature Control System Technical Specification2017-06-30030 June 2017 License Amendment Request to Revise Control Room Ventilation Temperature Control System Technical Specification RS-17-058, License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements.2017-06-30030 June 2017 License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements. RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process 2023-09-29
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Nuclear RS-11-050 10 CFR 50.55a April 11, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-456 and STN-50-457
Subject:
Third 10-Year Inservice Inspection Interval Relief Request 13R-08, Alternative Requirements to ASME Section XI Appendix VIII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside Surface In Accordance with 10 CFR 50.55a(a)(3)(i)
In accordance with 10 CFR 50.55a, IICodes and standards," paragraph (a)(3)(i), Exelon Generation Company, LLC, (EGC) is requesting relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, IIRules for Inservice Inspection of Nuclear Power Plant Components, II on the basis that the proposed alternative would provide an acceptable level of quality and safety.
Specifically, for examinations of dissimilar metal (DM) welds, EGC is requesting authorization to apply the difference between the examination vendor's achieved root mean square (RMS) error (currently 0.189-inch) and the Code Case N-695 allowed 0.125-inch RMS error to measure flaw depths when depth sizing of indications is required.
For examinations of both the DM weld and the adjacent austenitic weld, EGC is requesting authorization to apply the difference between the examination vendor's achieved RMS error (currently 0.245-inch) and the Code Case N-696 allowed 0.125-inch RMS error to measured flaw depths when depth sizing of indications is required.
The details of the 10 CFR 50.55a request are enclosed.
EGC requests approval of this request by April 11, 2012, in support of the Braidwood Unit 1 spring refueling outage (A1 R16).
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Ms. Lisa A. Schofield at (630) 657-2815.
April 11, 2011 U. S. Nuclear Regulatory Commission Page 2 Jeffre~ . ansen Manager - Licensing Exelon Generation Company, LLC
Attachment:
10 CFR 50.55a Request Request 13R-08, Revision 0 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRR Project Manager, Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety
lSI Program Plan Braidwood Station Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-OS Revision 0 (Page 1 of 5)
Proposed Alternative Requirements to ASME Section XI Appendix VIII (Supplements 2 and 10) Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside Surlace In Accordance with 10 CFR 50.55a(a)(3)(i)
- 1. ASME CODE COMPONENT(S) AFFECTED:
Code Class: 1 Examination Categories: See Table 1 Item Numbers: See Table 1 Component Numbers: See Table 1 Drawing Numbers: See Table 1
- 2. APPLICABLE CODE EDITION AND ADDENDA:
The current inservice inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition with 2003 Addenda. Ultrasonic examination of applicable Class 1 and 2 components is governed by Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the ASME Code,Section XI, 2001 Edition in accordance with 10 CFR 50.55a(b)(2)(xv).
- 3. APPLICABLE CODE REQUIREMENTS:
The ultrasonic (volumetric) examination of Class 1 and 2 piping welds are required to be performed using procedures, personnel, and equipment qualified to the criteria of the ASME Code,Section XI, 2001 Edition, Appendix VIII, Supplement 10, IIQualification Requirements for Dissimilar Metal Piping Welds," and Supplement 2, "Qualification Requirements for Wrought Austenitic Piping Welds," for the examination of Reactor Pressure Vessel (RPV) nozzle-to~safe end welds and RPV austenitic safe end welds, respectively.
Paragraph 3.2, "Sizing Acceptance Criteria," subparagraph (b) of Supplement 10 states that the lIexamination procedures, equipment, and personnel are qualified for depth sizing when the RMS (root mean square) error of the flaw depth measurements, as compared to the true flaw depths, is less than or equal to 0.125~inch (3.2mm)."
Paragraph 3.2, "Sizing Acceptance Criteria," of Supplement 2 also allows an RMS error less than or equal to 0.125~inch in order for examination procedures, equipment, and personnel to be qualified for depth sizing.
Code Case N~695, "Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division 1," provides alternative requirements to Appendix VIII, Supplement 10, and is unconditionally approved for use through Regulatory Guide 1.147, Revision 16.
Paragraph 3.3(c) of Code Case N~695 states "Examination procedures, equipment, and personnel are qualified for depth sizing when the RMS error of the flaw depth measurements, as compared to the true flaw depths, do not exceed 0.125 in. (3 mm)."
Code Case N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface,Section XI, Division 1,11 provides alternative requirements to Appendix VIII Supplements 2, 3, and 10 examinations conducted from the inside surface.
lSI Program Plan Braidwood Station Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-08 Revision 0 (Page 2 of 5)
Code Case N-696 is unconditionally approved for use through Regulatory Guide 1.147, Revision 16. Supplement 3 (Qualification Requirements for Ferritic Piping Welds) is not applicable to the welds referenced under this relief request.
Paragraph 3.3(d) of Code Case N-696 states, "Supplement 2 or Supplement 3 examination procedures, equipment, and personnel are qualified for depth sizing when the flaw depths estimated by ultrasonics, as compared to true depths, do not exceed 0.125 in. (3 mm) RMS, when they are combined with a successful Supplement 10 qualification."
- 4. REASON FOR THE REQUEST:
Exelon Generation Company, LLC, (EGC) will be performing volumetric examinations of all nozzle-to-safe end welds dissimilar metal (OM) welds and adjacent safe end-to-pipe or safe end-to-elbow welds (austenitic welds) from the inside diameter (10) surface during the spring 2012 (A1R16) and fall 2012 (A2R16) refueling outages when all reactor vessel nozzle-to-safe end OM welds will be mitigated against primary water stress corrosion cracking (PWSCC) through application of the Mechanical Stress Improvement Process (MSIP). Upon completion of application of MSIP, additional volumetric examinations will be performed during subsequent outages as dictated by the current industry (Reference 8.1) or through future regulatory requirements. For volumetric examination of the OM welds, EGC will use the NRC approved requirements of Code Case N-695 for qualification requirements along with a proposed alternative, and for volumetric examination of the adjacent austenitic welds, EGC will use Code Case N-696 to perform a combined qualification along with a proposed alternative.
EGC proposes using an alternative RMS error depth sizing requirement as compared to the 0.125-inch RMS error value stated in Code Cases N-695 and N-696. EGC contacted the Electric Power Research Institute (EPRI) NOE Center on February 7,2011, and confirmed that no vendor has successfully demonstrated compliance with the Code-allowed 0.125-inch RMS value for qualification tests for examinations conducted from the inside diameter surface (Le., stand-alone Supplement 10 or combined Supplement 2 and 10 qualifications).
EGC has verified through the EPRI NOE Center that the current examination vendor selected to perform the scheduled examinations at Braidwood Station has achieved a 0.189-inch RMS error (as addressed in Code Case N-695) for the stand-alone Supplement 10 qualification and a 0.245-inch RMS error for the combined Supplement 2 and 10 qualification (as addressed in Code Case N-696).
- 5. PROPOSED ALTERNATIVE AND BASIS FOR USE:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested for an alternative requirement that will provide an acceptable level of quality and safety.
For examinations limited to OM welds (adjacent austenitic weld is not being examined), EGC proposes to apply the difference between the examination vendor's achieved RMS error (currently 0.189-inch) and the Code Case N-695 allowed 0.125-inch RMS error to measure flaw depths when depth sizing of indications is required.
For examinations of both the OM weld and the adjacent austenitic weld, EGC proposes to apply the difference between the examination vendor's achieved RMS error (currently 0.245-inch) and the Code Case N-696 allowed 0.125-inch RMS error to measured flaw depths when depth sizing of indications is required.
lSI Program Plan Braidwood Station Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-OS Revision 0 (Page 3 of 5)
If, through later qualification attempts, the current examination vendor (or a different vendor is selected) and the examination vendor demonstrates an improved depth sizing RMS error prior to any scheduled examinations, the excess of that improved RMS error over the allowed 0.125-inch RMS error, if any, will be added to the measured value for comparison with applicable Acceptance Standards and/or Acceptance Criteria to determine the acceptability of the indication.
Applying the difference between the allowed RMS error and the achieved RMS error to the actual flaw being sized will ensure a conservative bounding flaw depth value is used for dissimilar metal and austenitic welds examined at Braidwood Station.
In addition to performing ultrasonic examination of these welds during A1 R16 and A2R16, the currently selected NOE vendor will use surface geometry profiling software (profilometry) in conjunction with a focused immersion ultrasonic transducer positioned to permit accurate profile data across the examination volume, in order to help the examiner confirm locations where the raw data indicates lack of transducer contact due to problematic surface geometry.
Eddy current examination will be used to supplement ultrasonic examination where there is sufficient surface roughness to call into question the applicability of the ultrasonic examination qualification to detect axial flaws. The ultrasonic examinations, as supplemented by eddy current examinations and profilometry, will be conducted to the maximum extent practical. EGC intends to examine all OM nozzle-to-safe end and adjacent austenitic piping welds using this process.
For A 1 R16 and A2R16, the following eddy current techniques will be utilized:
- Two plus point probes on each detection sled applied circumferentially on the inside surface in scan increments of 0.08 inches circumferentially (for axial flaws) and 0.25 inches axially (for circumferential flaws).
- Automated systems for data collection and analysis.
The target flaw size for the eddy current procedure is 0.28 inches long is well within the ASME Code linear flaw acceptance standards of 0.45 inches for austenitic material (Table IWB-3514-2) and 0.625 inches for ferritic material (Table IWB-3514-4).
The use of ultrasonic profilometry and eddy current examination, in conjunction with procedures and personnel qualified through the blind tests to supplement Appendix VIII qualified ultrasonic procedures and personnel will provide additional assurance that surface connected flaws (if present) will be detected in the presence of potential surface roughness.
EGC concludes that the proposed alternatives of adding the difference between the ASME Code-allowed RMS error and the demonstrated RMS error to the measured through-wall extent, in addition to the use of the appropriate acceptance standards specified in Section XI of the ASME Code, will provide additional assurance of structural integrity of the subject welds.
For planar indications, which are determined not to be connected to the inside surface, the amended through-wall depth will be compared with the appropriate IWB-3500 Acceptance Standard.
For planar indications, which are determined to be connected to the inside surface, the amended through-wall depth will be evaluated in accordance with the appropriate IWB-3600 Acceptance Criteria.
lSI Program Plan Braidwood Station Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R-OS Revision 0 (Page 4 of 5)
This proposed alternative will ensure that there is reasonable assurance of the structural integrity of the subject welds, and thus will continue to provide an acceptable level of quality and safety.
- 6. DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the remainder of the Third Ten-Year lSI Interval for Braidwood Station, Units 1 and 2, which is currently scheduled to end July 28, 2018, for Unit 1, and on October 16, 2018, for Unit 2.
- 7. PRECEDENTS:
The NRC has authorized similar relief requests to use the same methodology and selected inspection vendor proposed by EGC for Braidwood Station as indicated below:
- 1) Letter from Doug/as A. Broaddus (U. S. NRC) to Christopher Burton (Carolina Power & Light Company), "Shearon Harris Nuclear Power Plant, Unit 1 - Relief Request for Approval of an Alternative Inservice Inspection Method for Six Pressure Retaining Dissimilar Metal Welds in the Reactor Pressure Vessel Nozzles (TAC No. ME3894)," dated December 29,2010 (ADAMS Accession ML102910129)
- 2) Letter from Gloria Kulesa (U. S. NRC) to Mark J. Anjuni (Southern Nuclear Operating Company, Inc.), IIVogtle Electric Generating Plant, Units 1 and 2, Safety Evaluation of Relief Request VEGP-ISI-ALT-03, Version 3.0, for Reactor Vessel Nozzle to Safe-End Weld Examinations (TAC Nos. ME3752 and ME3753),1I dated November 16, 2010 (ADAMS Accession ML102870030)
- 3) Letter from Michael T. Markley (U. S. NRC) to David J. Bannister (Omaha Public Power District), II Fort Calhoun Station, Unit 1 - Relief Request for Use of an Alternate Depth-Sizing Qualification (TAC No. ME2512)," dated August 20,2010 (ADAMS Accession ML102210133)
- 4) Letter from Michael T. Markley (U. S. NRC) to John T. Conway (Pacific Gas and Electric Company), "Diablo Canyon Power Plant, Unit No.1 - Approval of Relief Request for Relief NDE-RCS-SE-1 R16 from Examination Requirements of ASME Code,Section XI, Appendix VIII, Supplement 10, Root Mean Square Error (TAC No. ME3942)," dated July 23, 2010 (ADAMS Accession ML101750640)
- 8. REFERENCES 8.1 Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139), Revision 1
lSI Program Plan Braidwood Station Units 1 & 2, Third Interval 10 CFR 50.55a RELIEF REQUEST 13R.. 08 Revision 0 (Page 5 of 5)
TABLE 1: Applicable Components at Braidwood Station FORMER ASME CURRENT COMPONENT DRAWING CATEGORY RI-ISI DESCRIPTION NUMBER NUMBER B-FIB-J XI ITEM CATEGORY R-A NUMBER ITEM NUMBER (Note 1)
Unit 1 1RV-01-022 RPV Nozzle-to-Safe End Hot leg, loop C 1RV-01 85.10 Ri.i5 1RV-01-030 RPV Safe End-to-Pipe Hot leg, loop C 1 RV-Oi 89.11 R1.20 1 RV-01-023 RPV Nozzle-to-Safe End Cold leg, loop C 1RV-01 85.10 R1.15 1RV-01-031 RPV Safe End-to-Elbow Cold leg, loop C 1RV-01 89.11 R1.20 1RV-01-024 RPV Nozzle-to-Safe End Cold leg, loop 0 1RV-01 85.10 R1.15 1RV-01-032 RPV Safe End-to-Elbow Cold leg, loop 0 1RV-01 89.11 Ri.20 1 RV-01-025 RPV Nozzle-to-Safe End Hot leg, loop 0 1RV-01 85.10 Ri.i5 1RV-01-033 RPV Safe End-to-Pipe Hot leg, loop 0 1RV-01 89.11 Ri.20 1RV-01-026 RPV Nozzle-to-Safe End Hot leg, loop A 1RV-01 85.10 Ri.15 1RV-01-034 RPV Safe End-to-Pipe Hot leg, loop A 1RV-01 89.11 R1.20 1RV-01-027 RPV Nozzle-ta-Safe End Cold leg, loop A 1RV-01 85.10 R1.i5 1RV-01-035 RPV Safe End-to-Elbow Cold leg, loop A 1RV-01 89.11 Ri.20 1 RV-01-028 RPV Nozzle-to-Safe End Cold leg, loop 8 1RV-Oi 85.10 R1.15 1RV-01-036 RPV Safe End-to-Elbow Cold leg, loop 8 1RV-01 89.11 R1.20 1 RV-Ol-029 RPV Nozzle-to-Safe End Hot leg, loop 8 1RV-Oi 85.10 R1.i5 1 RV-01-037 RPV Safe End-to-Pipe Hot leg, loop 8 1RV-01 89.11 R1.20 Unit 2 2RV-01-022 RPV Nozzle-to-Safe End Hot leg, loop 0 2RV-01 85.10 Ri.15 2RV-01-Q30 RPV Safe End-ta-Pipe Hot leg, loop 0 2RV-01 89.11 R1.20 2RV-01-023 RPV Nozzle-to-Safe End Cold leg, loop 0 2RV-01 85.10 R1.15 2RV-Oi-031 RPV Safe End-to-Elbow Cold leg, loop 0 2RV-01 89.11 R1.20 2RV-01-024 RPV Nozzle-to-Safe End Cold leg, loop C 2RV-01 85.10 R1.15 2RV-01-032 RPV Safe End-to-Elbow Cold leg, loop C 2RV-01 89.11 R1.20 2RV-01-025 RPV Nozzle-to-Safe End Hot leg, loop C 2RV-01 85.10 R1.15 2RV-01-033 RPV Safe End-to-Pipe Hot leg, loop C 2RV-01 89.11 R1.20 2RV-01-026 RPV Nozzle-to-Safe End Hot leg, loop 8 2RV-01 85.10 R1.i5 2RV-01-034 RPV Safe End-to-Pipe Hot leg, loop 8 2RV-01 89.11 R1.20 2RV-01-027 RPV Nozzle-to-Safe End Cold leg, loop 8 2RV-01 85.10 Ri.i5 2RV-01-035 RPV Safe End-to-Elbow Cold leg, loop 8 2RV-01 89.11 R1.20 2RV-01-028 RPV Nozzle-to-Safe End Cold leg, loop A 2RV-01 85.10 Ri.15 2RV-01-036 RPV Safe End-to-Elbow Cold leg, loop A 2RV-01 89.11 R1.20 2RV-01-029 RPV Nozzle-to-Safe End Hot leg, loop A 2RV-01 85.10 R1.15 2RV-01-037 RPV Safe End-to-Pipe Hot leg, loop A 2RV-01 89.11 R1.20 Note 1: Category and Item Numbers may change based on NRC approved alternatives or future NRC regulation(s).