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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] |
Text
/ *./*'f__ /'. (7 70
- CCPOF=0.01 60 CCPOF=O.01 IL 50 0
S 40
.,*30 30 ~-, ...
20 10 0 I I I III! I I!1 I I i1 II II !
150 0 50 100 Crack Half Angle I I I, 1 , ,1I , , , , , , f, , il 1'11 '1'11 lol l 0.7 0.6 a 0.5 0- 0.4 "6 0.3
.0
- 1. 0.2 0.1 0.
0 10 20 30 40 50 60.
Time to Failure (months)
Long term results for integrated model. Linear region extends from about 25-50 months.
Integrated model:
Calculation is for some fixed period of operation (say 20 EFPY at 600TF)
- 1. Determine number of nozzles that have cracked by randomly selecting a value of the Weibull parameter from a lognormal distribution with log mean 5.35 and 0.65 of 1.5.
[determined by fitting to available inspection results] and assuming a Weibull slope The fraction of cracked nozzles is given by IfIOrnIMýJU1 i rl-cCd was deleted i tnin in accordance with the Freedom of Information Act, exemptions.. 5
,:OIA--?**z.2.?*
I %Q
