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| Issue date | Title | Topic | |
|---|---|---|---|
| ML022760305 | 30 September 2002 | Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Signature Page | |
| ML023040268 | 19 September 2002 | Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Power-Operated Valves |
| ML023180473 | 11 November 2002 | 10 CFR 50.59 Summary Report of Facility Changes, Tests & Experiments Covering Period 05/18/00 Through 05/18/02 | Safe Shutdown Boric Acid Ultimate heat sink Offsite Dose Calculation Manual Post Accident Monitoring Internal Flooding Temporary Modification Finite Element Analysis Condition Adverse to Quality Foreign Material Exclusion Frazil ice Control of Heavy Loads Flow Induced Vibration Power Uprate |
| ML023260058 | 18 November 2002 | Regulatory Commitment Change Summary Report (May 18, 2000 - May 18, 2002) | High Radiation Area Nondestructive Examination |
| ML030240394 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter, Table of Contents - Attachment B | Boric Acid Past operability Condition Adverse to Quality Operability Determination License Renewal Pressure Boundary Leakage Unidentified leakage Unidentified leak Power Uprate |
| ML030240408 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter, Enclosure 4, Table of Contents - Attachment 1 | Boric Acid Slow transfer Nondestructive Examination Condition Adverse to Quality |
| ML030240420 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter, Attachment 1, Page 158 - 364 | |
| ML030240424 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter, Attachment 1, Page 365 - 574 | |
| ML030240440 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter, Attachment 2 | Safe Shutdown Boric Acid Packing leak Ultimate heat sink Stroke time Past operability Temporary Modification VT-2 Condition Adverse to Quality Significance Determination Process Maintenance Rule Program Pressure Boundary Leakage Fire Protection Program |
| ML030240482 | 9 January 2003 | Firstenergy Nuclear Operating Co. (Fenoc)/ Evaluations Performed at Davis-Besse to Address USNRC Inspection Manual Chapter 0350, Item No. 1, Adequacy of Root Cause Determination/ Letter | |
| ML030280448 | 30 September 2002 | Reactor Vessel Head Degradation Lessons-Learned Task Force Report Executive Summary - Handout Provided at Public Meeting on November 20, 2002 | Boric Acid Generic Issues Program |
| ML030410381 | 30 January 2003 | Questions from the Public Meeting Between NRC and Firstenergy Nuclear Operating Co. Davis-Besse Safety Culture and Safety Concious Work Environment | |
| ML030800118 | 18 March 2003 | Semiannual Fitness-For-Duty Report, July - December 2002 | Fitness for Duty |
| ML030910624 | 31 July 2002 | Preliminary FENOC Submission Titled Responses to NRC Staff Comments and Questions on Davis-Besse Safety Significance Assessment (SIA-W-DB-O1Q301) Submitted April 8, 2002 | Finite Element Analysis |
| ML031010240 | 6 April 2003 | Transmittal of Revision 6 of Davis-Besse Return to Service Plan, Revision 5 of Davis-Besse Restart Action Plan, Revison 5 of Davis-Besse Program Compliance Plan, & Revison 3 of Nuclear Operating Business Practice, Restart Readiness Review E | Safe Shutdown Boric Acid Non-Destructive Examination Commercial Grade Dedication Coatings Temporary Modification Significance Determination Process Foreign Material Exclusion Maintenance Rule Program Through Wall Leak Fire Protection Program |
| ML031040150 | 13 July 2002 | Handwritten Comment on Preliminary FENOC Submission Titled Responses to NRC Staff Comments & Questions on Davis-Besse Safety Significance Assessment (SIA-W-DB-01Q-301) | Finite Element Analysis |
| ML031040196 | 18 April 2002 | Letter to Jim Dyer from Howard Bergendahl Re Confirmatory Action Letter Response - Root Cause Analysis Report with Handwritten Notes | Boric Acid Time of Discovery Packing leak Non-Destructive Examination Hydrostatic Coatings Nondestructive Examination VT-2 Finite Element Analysis Condition Adverse to Quality Fuel cladding Pressure Boundary Leakage Through-Wall Leak Through Wall Leak |
| ML031040235 | 31 August 2002 | ORNL/NRC/LTR-, Stochastic Failure Model for Davis-Besse Rvp Head. | Boric Acid Hydrostatic Pressure Boundary Leakage |
| ML031040251 | 30 September 2002 | ORNL/NRC/LTR-, Stochastic Failure Model for Davis-Besse Rvp Head. | Boric Acid Hydrostatic Pressure Boundary Leakage |
| ML031110097 | 8 April 2003 | Nuclear & Environmental Operations, Davis Besse Reactor Vessel Head Examination | |
| ML031110492 | 30 April 2002 | Failure Criterion Development and Parametric Finite Element Analyses to Assess Margins for the Davis Besse RPV Head Corrosion | Boric Acid Finite Element Analysis |
| ML031210501 | 23 April 2003 | Submittal of Report Titled, Safety Culture Evaluation of Davis Besse Nuclear Power Station, Dated April 14, 2003 | Foreign Material Exclusion |
| ML031530169 | 29 May 2003 | Engineering Change Package - Reference Documents Table of Content - ECR No. 02-0805-00, Rev. 01 | |
| ML031530174 | 29 May 2003 | Engineering Change Screen | |
| ML031530180 | 5 August 2002 | Restart Test Plan | |
| ML031530183 | 28 November 2002 | Engineering Change Request ECR NO-02-805-00 | |
| ML031530185 | 28 November 2002 | Installation and Test Requirements | |
| ML031530186 | 28 November 2002 | Regulatory Applicability Determination No. 02-02026, Rev 0 | |
| ML031530402 | 5 May 2002 | NRC Assessment of Margin Available at Davis Besse | |
| ML031560654 | 30 April 2002 | Failure Criterion Development and Parametric Finite Element Analyses to Assess Margins for the Davis-Besse RPV Head Corrosion with Handwritten Notes | Finite Element Analysis |
| ML032310045 | 13 August 2003 | Transmittal of Final Report on Examination of the Reactor Vessel Head Degradation, and Safety Significance Assessment Update | Nondestructive Examination Finite Element Analysis |
| ML032310058 | 30 June 2003 | Final Report: Examination of the Reactor Vessel (Rv) Head Degradation at Davis-Besse. Table of Contents and Pages 1 - 98 | Boric Acid Nondestructive Examination |
| ML032310060 | 30 June 2003 | Final Report: Examination of the Reactor Vessel (Rv) Head Degradation at Davis-Besse. Pages 99 - 226 | Boric Acid |
| ML032510339 | 17 September 2003 | Incore Monitoring Nozzle Inspections | Boric Acid Pressure Boundary Leakage |
| ML032600982 | 15 July 2002 | Stochastic Failure Model for the Davis Besse RPV Head | |
| ML032600983 | 14 August 2002 | Stochastic Failure Model for Davis Besse RPV Head | Boric Acid Hydrostatic Pressure Boundary Leakage |
| ML033140402 | 20 November 2003 | Letter, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions | Coast down |
| ML033350327 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Cover Page Through Figure 2.7.9 | Boric Acid Nondestructive Examination |
| ML033350335 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 3.1.1 - 3.2.3 | |
| ML033350340 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 3.3.1 - 3.5.5 | |
| ML033350343 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 3.5.6 - 5.3 | |
| ML033350349 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 5.3 - 6.1.1.1 | |
| ML033350353 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 6.1.1.2 - 7.2.4.1 | Boric Acid |
| ML033350358 | 30 November 2003 | Framatome Anp, Inc. Document 31-5029337-02, Examination of Reactor Vessel (Rv) Head Degradation at Davis Besse, Figures 7.2.4.2 - 8.3.3.5 | Boric Acid |
| ML033360251 | 23 November 2003 | Integrated Report to Support Restart of the Davis-Besse Nuclear Power Station and Request for Restart Approval | Safe Shutdown Boric Acid Packing leak Non-Destructive Examination Tornado Missile Coatings Temporary Modification Condition Adverse to Quality Tornado Missile Protection Foreign Material Exclusion Large early release frequency Code Reconciliation Exemption Request Pressure Boundary Leakage Through-Wall Leak Grace period |
| ML033650298 | 23 September 2002 | Confirmatory Action Letter Response - Revision 1 to Root Cause Analysis Report Regarding Reactor Pressure Vessel Head Degradation - Serial Number 1-1289 | |
| ML040020032 | 19 December 2003 | Submittal of Revisions 7, 8, 9, and 10 of the Nuclear Operating Business Practice, Restart Readiness Review Extended Plant Outage (DBBP-VP-0002) | Safe Shutdown Boric Acid Commercial Grade Dedication Temporary Modification Foreign Material Exclusion Maintenance Rule Program Fire Protection Program |
| ML040270181 | 11 February 2004 | Memo, Evaluation of Davis-Besse Modifications to the High Pressure Injection Pump and Associated Mock-Up Testing (TIA No. 2003-04, TAC No. MC0584) | Safe Shutdown Boric Acid Mission time Hydrostatic Coatings Finite Element Analysis |
| ML040270271 | 5 March 2002 | Holtec Highlights, HH17.05 | |
| ML040280597 | 27 January 2004 | Submittal of Revision 1 and Revision 2 of the Davis-Besse Nuclear Power Station Operational Improvement Plan Operating Cycle 14 | Grace period |