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MONTHYEARML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts Project stage: Other ML0702602122007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections Project stage: Other 2007-01-31
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Category:Graphics incl Charts and Tables
MONTHYEARL-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML20142A3972020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 32, Wind Rose Annual Average 10M ML20142A3982020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 31, Wind Riose Annual Average 75M ML20142A3992020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 30, Wind Rose Annual Average 100M ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15239B2122015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15238B8652015-09-0303 September 2015 FHRR MSFHI Tables 1 and 2 ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45)2013-07-23023 July 2013 Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45) ML12167A2622012-05-29029 May 2012 Enclosure - Davis-Besse 17RFO License Condition 2.C(7) SG Circumferential Crack Report ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1015201172010-05-28028 May 2010 Nozzle 4 - 52M Deposit Depth ML1005396232010-02-22022 February 2010 Lessons Learned Task Force Action Plan Regarding Stress Corrosion Cracking Dec 2009 (Final Update) ML0824902892008-10-0202 October 2008 ITSB Draft L, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824903002008-10-0202 October 2008 ITSB Draft R, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902952008-10-0202 October 2008 ITSB Draft M, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902752008-10-0202 October 2008 Draft a, Attachment to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902802008-10-0202 October 2008 ITSB Draft La, to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues L-08-094, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application2008-03-12012 March 2008 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application ML0727405102008-02-11011 February 2008 Lltf Action Plan Feb 2008 Update - Public ML0803700812008-02-0101 February 2008 Lltf Status of Recommendations February 2008 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0708602822007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix B, Crack Driving Force and Growth Rate Estimates ML0708602812007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix a, Finite Element Stress Analysis of Davis-Besse CRDM Nozzle 3 Penetration 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 ML0708602642007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 6. Boric Acid Wastage of Carbon Steel Components in Us PWR Plants 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 ML0708602532007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background ML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts ML0618002582006-06-27027 June 2006 Closure of Davis-Besse Operational Improvement Plan ML0611401302006-03-16016 March 2006 Ltr Fm J. Gutierrez, Morgan Lewis to S. Brock Requesting to Withhold Materials from Public Disclosure Which Was Submitted by FENOC - Affidavits of Terry Young and Warren Bilanin ML0525707982005-09-12012 September 2005 Documentation of Completed Post-Restart Process Plan for Transition of Davis-Besse from the IMC 0350 Oversight Process to the Reactor Oversight Program (ROP) ML0523801412005-08-31031 August 2005 Status of Davis-Besse Lessons Learned Task Force Recommendations - Last Update: August 31, 2005 ML0411301992004-04-21021 April 2004 Oversight Panel Final Restart Checklist Public Release Memo ML0414503382004-02-13013 February 2004 Oversight Panel Open Action Item List ML0414503372004-02-13013 February 2004 IMC 0350 Panel Process Plan ML0414503262004-02-13013 February 2004 Restart Action Matrix - Open Items Only ML0308000432003-01-0101 January 2003 Firstenergy Nuclear Operating Company, NRC Allegations and Employee Concerns Program Contact Trends, January 2002 - January 2003 ML0224601492002-08-29029 August 2002 Undated Data Chart, CDF, LERF, Rem ML0224601482002-08-29029 August 2002 Heat 69 Crack Growth - Bounding Weibull with 1.5 Shape Facto with Handwritten Notes ML0224601422002-08-29029 August 2002 Chart, Long-Term Results for Integrated Model with Handwritten Notes ML0224003452002-08-27027 August 2002 Failure Frequency Curve for Davis-Besse Conditions ML0224003402002-08-27027 August 2002 Draft Graphs for Flaw Curves and Stress Intensity Factors ML0530703682002-03-13013 March 2002 Timeline of Key Events Related to Reactor Vessel Head Boric Acid Wastage Rev.3, 3-13-02 ML0530704022001-04-20020 April 2001 Normal Sump Pump Samples 2024-06-19
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24248A2112024-09-0303 September 2024 2023 Davis-Besse End-of-Cycle Meeting Presentation ML22222A1102022-07-21021 July 2022 KM Session Final ML22178A1952022-06-27027 June 2022 2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation ML22028A3922022-02-0101 February 2022 Licensee Regulatory Conference Presentation ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML21176A1992021-06-25025 June 2021 Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry ML20210M0712020-07-27027 July 2020 Combined End-of-Cycle 2019 Public Meeting Slide Presentation ML19249D0212019-09-0606 September 2019 End-of-Cycle Summary Handout (2018) ML18310A3802018-11-0808 November 2018 Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request ML18180A1962018-06-29029 June 2018 Slides for Davis Besse 2017 EOC Open House ML17229B3382017-08-17017 August 2017 Presentation for 2016 Davis-Besse EOC Open House ML16174A3152016-06-21021 June 2016 Annual Assessment Meeting Open House June 21, 2016 ML15156A6962015-06-11011 June 2015 Annual Assessment Meeting Open House Handout ML14224A1112014-08-25025 August 2014 Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014 ML14218A0542014-08-0707 August 2014 Handout Davis-Besse EOC Mtg ML14050A4002014-02-20020 February 2014 NRC Presentation for Davis-Besse Steam Generator Replacement Webinar ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13157A0642013-06-0606 June 2013 June 11, 2013 NRC Presentation ML13159A0092013-06-0404 June 2013 Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12227A4172012-08-15015 August 2012 NRC End-Of-Cycle Assessment 2011 Meeting Presentation ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1206901712012-02-29029 February 2012 Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective ML12200A2402012-02-23023 February 2012 Presentation Slides on Davis-Besse Shield Building Crack ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting L-02-002, G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse2010-04-15015 April 2010 G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse ML0920202972009-07-15015 July 2009 NRC Slides from EOC Meeting ML0920202872009-07-15015 July 2009 Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station ML0725600562007-09-12012 September 2007 9/12/2007 Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) 9/12/2007 NRC Meeting Slides ML0725600462007-09-11011 September 2007 9/11/2007-Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) - 9/11/2007 NRC Meeting Slides ML0722201892007-08-0808 August 2007 NRC EOC Public Meeting Slides ML0717905962007-06-27027 June 2007 Slides from Public Meeting Between NRC and FENOC Regarding Response to May 14, 2007, Demand for Information ML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts ML0706502022007-01-23023 January 2007 Slides to Summary of Pre-Application Meeting with FENOC Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML0632003672006-12-11011 December 2006 Slides, Improved Technical Specification Conversion from Category 1 Pre-submittal Meeting with Fenco to Discuss Davis-Besse's' Proposed Conversion to Improved Technical Specifications ML0612404142006-05-0202 May 2006 NRC Annual Assessment Meeting ML0601801602006-01-18018 January 2006 Industry Safety Culture Presentation for January 18, 2006 Public Meeting ML0603002272006-01-10010 January 2006 Multi-Regional NRC Public Meeting Licensee (FENOC) Slide Presentation ML0802205572005-09-12012 September 2005 NRC Commissioners Briefing by Firstenergy Nuclear Operating Co ML0525604472005-08-17017 August 2005 B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program 2024-09-03
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Davis-Besse 14RFO Eddy Current Exam Scope S/G 2-A S/G 1-B Total nspection of all new re-rolls 100 50 150 Periphery Gap Analysis
- Tech Spec Requirement 379 406 785 Full length bobbin examination of all in-service non-sleeved tubes. Sleeved tubes were inspected from LTE to bottom of 14888, 15220 30108 Full length bobbin examination of 33% sleeves 66 70 136 Plus Point exam of the expanded sleeve regions (both upper and lower rolls) and parent tube pressure boundary portion just below the lowest sleeve roll, extending approximately 6 inches past the sleeve of 33% of the sleeves 66 70 136 Plus Point exam of the expanded sleeve regions and parent tube pressure boundary portion just below the lowest sleeve roll, extending approximately 6 inches past the sleeve of 67% of the 133 142 275 Plus Point and Pancake inspection of non-sleeved in-service stress relieved upper tube roll expansions (79%) and Plus point and pancake coil examination of all of.the non-stress-relieved tube upper roll expansions and tube ends -factory re-rolls (5 tubes) and repair rolls (114 tubes) 11604 11856 23460 Plus point and pancake coil examination of 21% of the non-sleeved in-service tubes in the upper tube sheet region from tube end including tube end and upper roll expansions to Upper tube 3085 3152 6237 Plus Point and Pancake inspection of in-service stress relieved lower tube roll expansions in S/G A 33%. 4913 N/A 4913 Plus Point and Pancake inspection of in-service stress relieved lower tube roll expansions in S/G 1 -B1 00%. N/A 15220 15220 Plus point and pancake coil examination of the tubes bordering the sleeve region (165 sleeves) 91 81 172 Plus point and pancake coil examination of all of the flaw-like indications reported from bobbin 600 400 1000 Plus point and pancake coil examination of all dent indications (100% sample of all previously reported and new dents using a 2.5 volt bobbin threshold) 253 205 458 Plus point and pancake coil examination of all dent indications greater than 0.5 volts between 15S and UTS in the periphery 16 8 24 Plus point and pancake coil sample inspection of lower tubesheet sludge pile region tubes 986 1120 2106 Sleeve Bobbin .inspection of all previously identified gross mean distortions (42 tubes) 0 42 42 Plus Point and pancake coil inspection of 33% of the sleeve gross mean distortions and 100% of the non-sleeve gross mean 0 16 16 Plus Point inspection of 33% of the Hot Leg rolled Plugs 183 76 259 Visual Welded Plug Exam (VT-1) (0 during 14 Mid-Cycle) 33 19 52 Visual Plug exams of all Plugs in Upper and Lower 1138 474 1612 38534 48627 87161 03/21,'2006 11:38 FAX 419 249 2478 DB PROCURNIENT
[aoo1j Davis-Besse 14 RFO March 2006 Axial Indications Ax SG Count Row Tube Ind Volts TSP Inchi Probe Depth Length Deg. Mode 2-A 1 151 13 SAI 0.49 15S 2.78 520PP 40 1.30 Groove IGA 2-A 2 150 21 SAI 0.39 15s -5.2 520PP 34 1.48 Groove IGA 2-A 3 87 122 SAI 0.34 UTE -1.68 520PP 86 0.26 Roll Trans PWSCC 2-A 4 58 1 SAI 0.23 15S -2.93 520PP 53 0.48 Groove IGA 2-A 5 `S0 17 SAI 0.18 15S -3.74 520PP 0 0.88 Groove IGA 2-A 6 151 12 SAI 0.18 15S 2.24 520PP 0 0.46 Groove IGA 2-A 7 151 15 SAI 0.16 15S 2.64 520PP 14 0.37 Groove IGA 2-A B 151 15 SAI 0.09 ISS 3.69 520PP 32 0.22 Groove IGA 2-A 9 151 15 SAI 0.06 158 4.7 520PP 28 .0.15 Groove IGA 1-1 10 56 104 SAI 2.25 UTE -1.48 520PP 97 0.26 Roll Trans PWSCC 1-S 11 79 57 SAI 0.50 UTE -1.13 S20PP 70 0.13 Rofl Trans PWSCC 1-8 12 109 74 SAI 0.35 UTE -1.39 520PP 68 0.16 Roll Trans PWSCC 1-8 13 141 65 MAI 0.26 15S -0.83 520PP 41 5.15 Groove IGA 1-B 14 143 62 SAI 0.20 15S -4.88 520PP 25 0.85 Groove IGA 1-B 15 64 1 SAI 0.18 15S -1.03 520PP 33 0.70 Groove IGA 1-B 16 25 97 MAI.- 0.14 15S -1.25 520PP 84 0.50 Groove IGA 1-8 17 83 1 SAI 0.12 ISS -1.81 520PP 31 0.13 Groove IGA 1-B 18 64 1 SAI 0.12 155 -3.19 520PP 25 0.42 Groove IGA 1-8 19 63 1 SAI 0.08 155 -2.12 520PP 18 0.13 Groove IGA Results as Of 8:58 AM, 3/21/2006 03o"21/2008 11:38 FAX 419 249 2478 DB PROCURMENT i o002 Davis-Besse 14 RFO March 2006 Circumferential Indications (Not in Prev Rerolled Tubes)SG Count[ Row I Tube Ind , Volts TSP Inchl I Probe I Depth ICircExti Deg. Mode 2-A 11f 35 1 1 SCIf 1.64 1 UTE -0.23 1520PP 7I 0.19 Tube End PWSCC 2-A .1 38 5 SCI 0.50 UTE -0.32 ,52oPPI 41 0.16 Tube End PWSCC 1-B 1 81 74 SCI 0.67 LTE 1.57 520PP 72 0.17 PWSCC In Heel SRR 1-B 1 84 82 SCI 1.09 UTE -0.16 520PP 93 0.28 Tube End PWSCC-J-Results as of 8:57 AM, 3/21/2006 03,21/2008 11:39 FAX 419 249 2478 DB PROCUMENT 0003 Davis-Besse 14 RFO March 2006 Volumetric Indications (Not in Previously Rerolled Tubes)SG Row Tube Ind Voit TSP inchlI Probe Depth Ax Len Circ Len Deg. Mode 1-B 105 119 SVI 0.23 UTS 8.25 520PP 38 0.13 0.10 OD IGAin UpperTS~f1_~.LJ iIII _I__Results as ot 8:58 AM, 03104/02 03/21/2008 11:39 FAX 419 249 2478 DB PROCURKENT o004 Davis-Besse 14 RFO March 2006 New Tube End Indications (Not in Previously Rerolled Tubes)S CountI Row I Tube Ind I Volts I TSP I Inchl I Probe 1-B 1 29 66 MAA 2.05 UTE -0.34 520PP 1-B 2 30 14 SAA 1.59 UTE -0.29 520PP I-B 3 35 88 SAA 1.39 UTE -0.28 520PP 1-1 4 36 91 SAA 1.10, UTE -0.29 520PP 1-B 5 40 104 SAA 2.08 UTE -0.34 520PP 1-B 6 43 92 SAA 2.33 UTE -0.27 520PP 1-B 7 43 108 SAA 1.09 UTE -0.29 520PP 1-B 8 89 126 SAA 1.91 UTE -0.31 520PP 2-A 9 21 49 SAA 0.77 UTE -0.23 520PP 2-A 10 24 51 SAA 0.54 UTE -0.30 520PP 2-A 11 26 80 SAA 1.31 UTE -0.27 520PP 2-A 12 32 83 SAA 2.02 UTE -0.39 520PP 2-A 13 59 1 SAA 1.41 UTE -0.28 520PP 2-A 14 80 12 SAA 1.43 UTE -0.28 520PP 2-A 15 85 31 SAA 1.21 UTE -0.26 520PP 2-A 18 92 3 SAA 0.61 UTE -0.26 520PP 2-A 17 112 87 SAA 1.63 UTE -0.42 520PP 2-A 18 116 111 MAA 0.86 u.TE -0.32 520PP 2-A 19 125 14 SAA 1.02 UTE -0.22 520PP---------------------
-Page 1 of I Results as of 8:58 AM, 3/21/2006 03/21/2006 11:39 FAX 419 249 2478 DB PROCURDIENT io0O5 Davis-Besse 14 RFO January 2006 Top 10 Wear Calls By Bobbin Depth SG Row Tube Depth Volts TSP Inch1 Prev Depth 2-A 16 2 24 1.05 13S -0.71 23 2-A 147 36 22 1.12 lOS 0.70 27 1-B 67 1 21 1.08 12S -0.02 17 2-A 146 34 19 0.88 105 0.61 16 2-A 150 27 18 0.95 10S -0.79 16 2-A 146 33 17 0.87 10S 0.64 18 1-B 14 74 18 0.62 12S -0.21 14 2-A 13 1 15 0.68 13S -0.75 -9 2-A 151 15 15 0.67 13S -0.78 11 2-A 12 1 14 0,66 13S -0.70 19 Results as ot 8:58 AM, 3/21/2006