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Category:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 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 L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 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 L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 2023-08-07
[Table view] Category:Technical
MONTHYEARL-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 ML14134A5172014-05-30030 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 L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. ML13008A0612012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-By Checklists, Sheet 21 of 139 Through End L-15-328, Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 72012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 7 ML15299A1502012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 6 of 7 ML15299A1492012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 5 of 7 ML15299A1482012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 4 of 7 ML15299A1472012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 3 of 7 ML15299A1462012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 2 of 7 ML15299A1442012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 1 of 7 ML12209A2602012-07-26026 July 2012 Attachment 31, Fauske & Associates, Inc. Technical Bulletin No. 1295-1, BWR MSIV Leakage Assessment: NUREG-1465 Vs. MAAP 4.0.2 ML1017400422010-06-0404 June 2010 0800368.407, Rev. 0, Summary of Design and Analysis of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigati L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds ML1002501322010-01-11011 January 2010 0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B ML11301A2222008-12-0101 December 2008 Reference: Combined Heat and Power Effective Energy Solutions for a Sustainable Future ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 L-08-105, Reactor Head Inspection Report2008-04-11011 April 2008 Reactor Head Inspection Report L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse2008-01-27027 January 2008 Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse ML0726105652007-09-17017 September 2007 Confirmatory Order, 2007 Independent Assessment of Corrective Action Program (FENOC) ML0708602802007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity ML0708602762007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus ML0708602712007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3 ML0708602682007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues ML0708602612007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking ML0708602562007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 4. the Davis-Besse March 2002 Event ML0708602532007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background 2023-01-10
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Text
BWXT SERVICES, INC. 1 140-025-02-24 103 BWXT SERVICES, INC. 1140-025-02-24 103 Figure 5.3 (cont.): Piece A2A5 after sectioning, looking down on the front face of previous photo. The mounted surface on sample A2A5C is indicated. This area contained the thinnest measured cladding (0.202").
BWXT SERVICES, INC. 1140-025-02-24 104 Table 5.4: Sample identification listing for Piece A2A6.
Piece ID l Location Test Plan ] Met J SEM U
A2A6A1 RV head near 900 No plan -- --
I 2A6A2 Lower portion of Contains lower U l (see below) J-groove weld and clad from portion of axial 3 2 (see below) crack at -1 00 and2 3500l700 circ cracks (0°o45°)
A2A6B Upper portion of Contains upper U (see below) J-groove weld from 350-700 portion of axial 1 2
__ ______ ______ crack at_-1 0 _ __
U W
I -
V S U
U U
U U
U Figure 5.4: Piece A2A6 was first sectioned into Pieces A2A6A and A2A6B. Piece A2A6A was further sectioned into Pieces A2A6A1 and A2A6A2. Both cuts were U made on the same plane, parallel to the paper. The first cut line is partially visible; Piece A2A6B is the upper portion of the weld. The second cut line between Pieces A2A6A1 and A2A6A2 is obscured by Piece A2A6A.
U U
U z = = == _
BWXT SERVICES, INC. 1 140-025-02-24 105 BWXT SERVICES, INC. 1140-025-02-24 105 Table 5.5: Sample identification listing for Piece A2A6B.
E Piece ID Location Test Plan Met SEM A2A6B1 Upper portion of J-groove No plan -
weld at -350° Nopa___
A2A6B2 Upper portion of J-groove Lower surface weld axial crack at -100 mounted for _ 1_3 A2A6B3 Mid portion of J-groove weld Open crack axial crack at -100 SEM sample 1 A2A6B4 Upper portion of J-groove No plan =
-1 weld from 300-700 Figure 5.5: Piece A2A6B after sectioning. The bottom surface of mounted. The axial crack in A2A6B3 was opened up for SEM.
p BWXT SERVICES, INC. 1140-025-02-24 106 Table 5.6: Sample identification listing for Piece A2A6A2.
Piece ID Location Test Plan Met SEM p
A2A6A2A Lower portion of J-groove No plan --
weld and clad at -700 p
A2A6A2B Lower portion of J-groove Contains circ crack 1 weld and clad at -450 near 450 A2A6A2C Lower portion of J-groove Open circ crack --
weld and clad at -300 sample for SEM A2A6A2D Lower portion of J-groove Contains circ crack 1 1 weld and clad at -200 near 20° A2A6A2E Lower portion of J-groove crack and circ1 A2A6A2E lLweld and clad at -10g cracksan =
A2A6AF Lower portion of J-groove No plan --
weld and clad at -0 p
p p
Figure 5.6: Piece A2A6A2 after sectioning. Additional sections were made on A2A6A2B, -C, -D, and -E. Refer to the following four tables and figures.
BWXT SERVICES, INC. 1 140-025-02-24 107 BWXT SERVICES, INC. 1140-025-02-24 107 Table 5.7: Sample identification listing for Piece A2A6A2B.
l Piece ID Location Test Plan Met SEM A2A6A2B1 Lower portion of J-grooveNopa weld at 450 (includes bore) No plan _ ll A2A6A2B2 Lower portion of J-groove Contains circ crack 1 l_________ ] weld and clad at -45° near 45° A2A6A2B3 Clad at -45' No plan -
Figure 5.7: Piece A2A6A2B after sectioning (side view of Figure 5.6).
The top surface of A2A6A2B2 was mounted.
BWXT SERVICES, INC. 1140-025-02-24 108 BWXT SERVICES, INC. 1140-025-02-24 108 Table 5.8: Sample identification listing for Piece A2A6A2C.
Piece ID Location Test Plan Met ISEM l Lower portion of J-groove A2A6A2C1 weld and upper surface of No plan _
clad at -30 (includes bore)
A2A6A2C2 Lower portion of J-groove Circ crack near 300 1 weld and clad at 30° bent open for SEM A2A6A2C3 Lower portion of J-groove No plan _ =
weld (RCS side)
Figure 5.8: Piece A2A6A2C after sectioning (side view of Figure 5.6). The circumferential cracks were bent open for SEM.
BWXT SERVICES, INC. 1140-025-02-24 109 Table 5.9: Sample identification listing for Piece A2A6A2D.
l Piece ID IF Location I Test Plan I Met l SEM l A2A6A2D1 Lower portion of J-groove N ln-weld at -200 (includes bore) No plan A2A6A2D2 Lower portion of J-groove Contains circ crack 1 1 weld and clad at -200 at .2001 (Lower srface -
circ crack at .
Figure 5.9: Section photo for Piece A2A6A2D (side view of Figure 5.6). The mounted surface of Piece A2A6A2D2 for optical and SEM examination is the lower surface (not visible) in the photo.
BWXT SERVICES, INC. 1140-025-02-24 110 Table 5.10: Sample identification listing for Piece A2A6A2E.
p Piece ID ll Location I Test Plan Met SEM A2A6A2E1 Lower portion of Lower surface 1 J-groove weld at -100 mounted for met A2A6A2E2 Contains clad at -200 No plan --
I~~~~~~~~~~~~~~~~~~
A2A6A2E3 Contains clad at -0° No plan --
A2A6A2E4 A2A6A2 Lower portion of LwrprinoJ-groove e ci rcPContains cracksaxial at - and 100 -- -
weld (RCS side) I(PNL Sample)
Q p
Figure 5.10: Section photo for Piece A2A6A2E (side view of Figure 5.6).
The mounted surface of Piece A2A6A2E1 is indicated. Piece A2A6A2E4 is reserved for PNL.
BWXT SERVICES, INC. 1140-025-02-24 ill BWXT SERVICES, INC. 1140-025-02-24 111 Table 5.11: Sample identification listing for Piece A2A7.
Piece ID Location Test Plan Met J SEM A2A7A RV head and clad near 3500 No plan l _
A2A7B RV head and clad near 3400 No plan _ l A2A7C RV head near 3450 No plan -
A2A7D Undercut region near 3450 Met mount 1 A2A7E RV head and clad near nose No plan -
A2A7F Undercut region near nose Met mount 1 A2A7G RV head near nose No plan -
A2A7H Clad prior to nose No plan -
A2A71 RV head and clad near 50 ° No plan -
A2A7J RV head and clad near 400 No plan -
A2A7K Undercut region near 400 Met mount I A2A7L Center portion of clad cracks SEM open crack _
sample A2A7M Adjacent to center cracks Met mount (center 1 1 portion)
A2A7N Clad cracks toward 2700 Met mount (2700) 1 1 A2A70 Clad near 0" No plan -
A2A7P Center portion of clad cracks Reserved for PNL -
A2A7Q Clad near 40 No plan -
A2A7R Clad near 400 No plan -
A2A7S Clad cracks toward 900 Met mount 1 1 A2A7T Clad near 600 No plan --
A2A7U Clad near 100 No plan
BWXT SERVICES, INC. 1140-025-02-24 112 Figure 5.11: Section photo for Piece A2A7. The mounted surfaces
-M, -N, and -S samples are indicated by the white arrows. Further for the -D, -F, -K, sectioning of Piece A2A7L is shown in Figure 5.12.
C~~~~~~~~~~~~~~~
-,-I
-- ~~~~~
BWXT SERVICES, INC. 1140-025-02-24 113 Table 5.12: Sample identification listing for Piece A2A7L.
Piece ID ll Location ] Test Plan j Met SEM p
A2A7L1A Center portion of clad cracks SEM open crack sample -
1l A2A7L1 B Adjacent to center cracks No plan --
p A2A7L2A Center portion of clad cracks SEM open crack sample -- 1 p A2A71-21B IAdjacent to center cracks No plan -- --
p p
p p
p p
p Figure 5.12: Section photo for Piece A2A7L. The main crack located near p the center of A2A7L was opened in the laboratory, resulting in Pieces A2A7L1 and A2A7L2.
Additional sections, which created the -A and -B pieces, were made to facilitate the SEM examinations. The surfaces examined by SEM are indicated.
p C 4~
BWXT SERVICES, INC. 1140-025-02-24 114 BWXT SERVICES, INC. 1140-025-02-24 114 Table 5.13: Sample identifications for Piece Al.
Piece ID Location Test Plan Met SEM AlA Contains cavity nose No plan -
Contains cavity side wall Met and SEeEDS toward 90° A1Bl 5.14)
AlC Contains nozzle #3 bore and No plan --
__________ small portion of cavity Noplan_
Contains cavity side wall Met and SEM/EDS AID C ontains 2700sieal samples (see Tables 21 toward 27005.15 and_5.16) _
Figure 0.13: ectioning Or riece A1 into our pieces. Pieces A1 s and A1 were further sectioned for metallography and SEM. Refer to Figure 5.14 through Figure 5.16.
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BWXT SERVICES, INC. 1140-025-02-24 115 Table 5.14: Sample identifications for Piece A B.
Piece ID Location Test Plan Met SEM Al Bi Upper portion of cavity' side No plan --
wall near 900 Al B2 Upper portion of cavity side Transverse met l wall near 900 mount Al 83 Middle portion of cavity side SEM/EDS sample -
wall near 900 Al B4 Lower portion of cavity side Transverse met l wall near 900 mount Al B5 RV head behind cavity side No plan wall AlB6 Lower portion of cavity side No plan wall near 900 Al B7 Cavity side wall No plan
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'I Bi'
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- i Figure 5.14: Section photo for Piece AlB, looking at the cavity side wall. The mounted surfaces of Piece Al B2 and Piece Al B4 is indicated.
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BWXT SERVICES, INC. 1 140-025-02-24 116 BWXT SERVICES, INC. 1140-025-02-24 116 Table 5.15: Sample identifications for Piece Al D.
Piece D Location Test Plan Met SEM Al Dl Cavity side wall near 2700 No plan Al D2A Upper portion of cavity side No plan --
wall near 2700 AID2B Upper portion of cavity side Transverse met wall near 270° mount location AlD2C Middle portion of cavity near SEM/EDS 1 l 2700 Al D2D Lower portion of cavity side Transverse met l wall near 2700 mount location Al D2E RV head behind cavity side Macroetch sample wall Al D2F Lower portion of cavity near No plan 2700 N Figure 5.15: Section photo for Piece AID, looking at the cavity side wall. Refer to Figure 5.16 for the mounted surface locations.
BWXT SERVICES, INC. 1140-025-02-24 117 Table 5.16: Sample identifications for Piece Al D2B and Piece Al D2D.
Piece ID Location Test Plan [Met SEM Al D2B1 Upper portion of cavity side Transverse met l wall near 2700 mount location 1 l Al D2132 Upper portion of cavity side No plan --
wall near 2700 AID2DI Lower portion of cavity side Transverse met wall near 2700 mount location AlD2B1J A1 D2D2 Lower wall portion of cavity side No plan lD 13 near 2700
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AlDD `A1D2D2.,
Figure 5.16: Section photo for Pieces AID2B and AID2D, looking at the cavity side wall. The mounted faces for Piece Al D2B1 and Piece Al D2D1 are indicated.
p BWXT SERVICES, INC. 1140-025-02-24 118 Sample A2A7M Knoop Microhardness 350.0 u 300.0 250.0-c 200.0 a 150.0 o 100.0-i 50.0-0.0-0.000 0.050 0.100 0.150 0.200 0.250 0.300 Distance from Upper Clad Surface, inches Figure 6.1.1.1: 4X macro photograph of metallurgical mount A2A7M. Refer to Figure 5.11 for the sample orientation. Cladding thickness ranged from 0.227" to 0.277" (5.77 to 7.04 mm). Knoop microhardness values exhibited a hardness elevation near the exposed cladding surface.
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