Date |
Description |
12/30/03 |
Response to RAI Concerning Generic Letter 96-06, "Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions." |
12/30/03 |
Resubmittal of Previously Submitted Documents |
12/23/03 |
NRC Integrated Inspection Report 50-346/03-22 |
12/19/03 |
Submittal of Revisions 7, 8, 9, and 10 of the Nuclear Operating Business Practice, Restart Readiness Review Extended Plant Outage (DBBP-VP-0002) |
12/18/03 |
Response to NRC Bulletin 2003-04: Rebaselining of Data in the Nuclear Materials Management and Safeguards System (NMMSS). |
12/18/03 |
Issuance of amendment - Motor Driven Feedwater Pump Flow Indication |
12/17/03 |
Core Operating Limits Report and Reload Report for Cycle 14 |
12/17/03 |
Withdrawal of 10CFR50, Appendix R, Subsection III.L.I, Exemption Regarding Time to Reach Cold Shotdown |
12/17/03 |
Response to Questions Regarding the 2002 Steam Generator Tube Inspections |
12/16/03 |
License Amendment Application to Revise Technical Specification 3/4.4.5, "Reactor Coolant System - Steam Generators," to Permit One-Time Extension of Steam Generator Tube Inservice Inspection Interval |
12/16/03 |
LER 03-014-00 Steam Feedwater Rupture Controls System Re-Energizes in a Blocked Condition |
12/15/03 |
NRC Press Release III-03-78:Davis-Besse Restart Meeting Postponed to Dec. 29, Meeting on NRC Inspection Findings Delayed Until Dec. 19 |
12/11/03 |
NRC Inspection Report 05000346-03-020 (DRS); 09/08/03 - 10/01/03; Davis Besse Nuclear Power Station; TI 2515/148, Verification of Compliance with Interim Compensatory Measures Order, Revision 2; Baseline Procedures 71130.02, 71130.03 and 71151. |
12/11/03 |
Request for additional information RE: 2002 Steam Generator Tube Service Inspection Results |
12/05/03 |
NRC Special Inspection - Reactor Coolant System Leak Test - Report No. 05000346/2003023 |
12/04/03 |
Davis Besse NRC Update - December 2003 Issue |
12/01/03 |
LER 03-013-00 Trip of Reactor Protection System During Plant Cooldown |
11/26/03 |
Withdrawal of License Amendment Request 01-0008 to Revise Technical Specification 3/4.3.1, "Reactor Protection System Instrumentation," to Delete Action and Enhance Specification Clarity |
11/26/03 |
Revised Response to NRC Generic Letter 98-04: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment |
11/26/03 |
LER 03-001-02 Potential of Air-Operated Valves to Functions During Design Basis Conditions |
11/24/03 |
LER 2003-012-00 Auxiliary Feedwater Pump Turbine Inoperable due to Degraded Steam Traps |
11/23/03 |
Integrated Report to Support Restart of the Davis-Besse Nuclear Power Station and Request for Restart Approval
- Integrated Report | Pages 1- 67 | Pages 68 - 134 |
- Appendix A, B and C
- Appendix D and E
|
11/20/03 |
Re-transmittal of Final Report on Examination of Reactor Vessel Head Degradation |
11/20/03 |
Request for Additional Information for License Amendment on Steam and Feedwater Rupture Control System Instrumentation |
11/20/03 |
Review of Generic Letter 96-06, "Assurance of Equipment Operability and Containment Integrity during Davis-Besse Accident Conditions |
11/19/03 |
Response to NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity." |
11/19/03 |
Davis Besse NRC Update - November 2003 Issue |
11/17/03 |
LER 03-011-00: Inoperability of Containment Spray Pump 1 Due to Solid State Trip Device Ground Fault False Trip |
11/14/03 |
LER 02-007-01, Davis-Besse Unit 1 Potential Leakage of Incore Monitoring Instrumentation Nozzles at Bottom of Reactor Vessel |
11/08/03 |
Disposition of Reactor Vessel Head Sample Piece "A2B" |
11/07/03 |
NRC Press Release III-03-067: NRC Davis-Besse Oversight Panel to Meet Nov. 12 in Oak Harbor, OH |
11/03/03 |
Requested for Additional Information Regarding the 2002 Steam Generator Tube Inspections (MB9541) |
10/30/03 |
NRC Integrated Inspection Report 05000346/2003018 |
10/29/03 |
Completion of NRC Order (EA-03-038) Requirements Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel for Davis-Besse, Unit 1. |
10/27/03 |
Supplemental Information for Technical Specification Change Regarding TS 3/4.7.1.7, "Motor Driven Feedwater Pump System" to Correct the Safety Grade Designation of the Motor Driven Feedwater Pump Flow Indication in Surveillance Requirement 4.7.1.e.2 (LAR 03-0001, TAC No. MB9017) |
10/27/03 |
LER 03-010-00, Davis-Besse Unit 1 Potential Inoperability of Decay Heat/Low Pressure Injection System Due to Loss of Valve Disc Pins |
10/21/03 |
NRC Special Inspection - System Health Assurance Followup - Report No. 0500346/2003003 (DRS) |
10/16/03 |
Davis-Besse Nuclear Power Station, Unit 1, Response to NRC Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors." (TAC No. MB9572) |
10/13/03 |
LER 2003-009, Loss of Offsite Power due to Degraded Regional Grid Voltage |
10/08/03 |
Preliminary Significance Determination for a Greater than Green Finding (NRC Inspection Report 50-346/2003-21) - Davis-Besse High Pressure Injection Pump Design Issue |
10/07/03 |
Final Significance Determination for a Yellow Finding (NRC Inspection Report 50-346/03-15) - Davis-Besse Potential Clogging of the Emergency Sump Following a Loss of Coolant Accident |
10/07/03 |
Davis Besse NRC Update - October 2003 Issue |
09/29/03 |
Issuance of Amendment - Safety Features Actuation System (SFAS) Instrumentation |
09/29/03 |
NRC Integrated Inspection Report 50-346/03-17 |
09/25/03 |
Issuance of Amendment Re: Startup Test Reports (TAC No. MB9478) |
09/19/03 |
Update of Confirmatory Action Letter 3-02-001D Status for Davis-Besse Nuclear Power Station |
09/12/03 |
LER 2003-003-01, Potential Inadequate HPI Pump Minimum Recirculation Flow Following SBLOCA |
09/11/03 |
EDO Letter - Semiannual Report - Status of Implementation of Davis-Besse Lessons Learned Task Force Report Recommendations
|
09/10/03 |
Davis Besse NRC Update - September 2003 Issue |
09/05/03 |
Issuance of Amendment No. 257 (MB8953) - One-Time Exception during Restart Test Plan |
08/29/03 |
Semiannual Report - Status of Implementation of Davis-Besse Lessons Learned Task Force Report Recommendations
|
08/20/03 |
Supplemental Information Regarding License Amendment Application to Revise Technical Specification (TS) 3/4.5.2, Emergency Core Cooling Systems - ECCS Subsystems - Tavg > 280F (License Amendment Request No. 03-0008; TAC No. MB8953) |
08/18/03 |
LER 03-001-01 From Davis-Besse Unit 1 Regarding Potential Inability of Air-Operated Valves to Function During Design Basis Conditions |
08/14/03 |
Davis Besse NRC Update - August 2003 Issue |
08/13/03 |
Transmittal of Final Report on Examination of the Reactor Vessel Head Degradation, and Safety Significance |
08/12/03 |
Issuance of Amendment - Pressurizer - High Level Limit |
08/12/03 |
Issuance of Amendment (TAC No. MB9016) |
08/11/03 |
License Amendment Application to Modify Technical Specification 3/4.5.2, Emergency Core Cooling Systems - ECCS Subsystems - Tavg > 280F (License Amendment Request No. 03-0004) |
08/11/03 |
10 CFR 50.55a Request RV-3 Regarding American Society of Mechanical Engineers Code for Operation and Maintenance (OM) of Nuclear Power Plants Inservice Testing Requirement at the Davis-Besse Nuclear Power Station, Unit 1 |
08/11/03 |
60 Day Response to Generic Letter 2003-01:"Control Room Habitability" |
08/08/03 |
60-Day Response to NRC Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors" |
08/07/03 |
Signature Validation for August 2, 2003 Regulatory Correspondence, Serial Number 2980 |
08/07/03 |
Request for Additional Information (MB8395) |
08/05/03 |
LER 03-007-00 - Davis-Besse Unit 1, "AC System Analysis Shows Potential Loss of Offsite Power Following Design Basis Accident" |
08/05/03 |
NRC Special Inspection - Containment Integrated Leak Rate Test - Report No. 50-346/03-05 (DRS) |
08/02/03 |
Supplemental Information Regarding License Amendment Application to Review Technical Specification (TS) 3/4.5.2, Emergency Core Cooling Systems - ECCS Subsystems - Tavg > 280F (License Amendment Request No. 03-0008; TAC No. MB8953) |
07/31/03 |
Request for Additional Information - Davis-Besse Nuclear Power Station (TAC No. MB8953) |
07/30/03 |
Davis-Besse Nuclear Power Station Incore Monitoring Instrumentation Nozzle Inspections |
07/30/03 |
NRC Integrated Inspection Report 50-346/2003-015 Preliminary Yellow Finding |
07/23/03 |
Reactor Vessel Closure Head Welding Data Sheets |
07/21/03 |
LER 03-006 Davis-Besse Unit 1 - Potential Errors in Analysis of Block Walls Regarding HELB Differential Pressure & Seismic Events |
07/17/03 |
Update of Confirmatory Action Letter 3-02-001C Status for Davis-Besse Nuclear Power Station |
07/17/03 |
Davis Besse NRC Update - July 2003 Issue |
07/11/03 |
NRC Inspection Report 50-346/03-19 - EP Exercise/Inspection |
07/07/03 |
NRC Special Inspections - Adequacy of Safety Significant Programs - Reports No. 50-346/02-11 and 50-346/03-09 |
07/02/03 |
Davis-Besse Oversight Panel Restart Checklist, Revision 3 |
07/01/03 |
NRC Press Release III-03-046: NRC Oversight Panel to Meeting with Davis-Besse Officials July 9 |
06/30/03 |
LER 03-005 - Containment Gas Analyzer Heat Exchanger Valves Found Closed Rendering the Containment Gas Analyzer Inoperable |
06/30/03 |
Davis-Besse Nuclear Power Station - Inspection Schedule Update |
06/17/03 |
NRC Special Inspection - Emergency Core Cooling System and Containment Spray System Sump Inspection Report No. 50-346/03-06(DRS) |
06/16/03 |
NRC Integrated Inspection Report 50-346/03-13 |
06/16/03 |
License Amendment Application to Modify Technical Specification 3/4.5.2, Emergency Core Cooling Systems - ECCS Subsystems - Tavg > 280F (License Amendment Request No. 03-0008) |
06/15/03 |
LER-2003-004 Inadequate Calibration of Reactor Coolant System Temperature Instrumentation |
06/10/02 |
LER-2003-003 Potential Inadequate HPI Pump Minimum Recirculation Flow Following SBLOCA |
06/03/03 |
Davis Besse NRC Update - June 2003 Issue |
05/30/03 |
NRC Supplemental Inspection and Radiation Protection Program Effectiveness Review Report No. 50-346/03-08(DRS) |
05/29/03 |
Final Significance Determination for a Red Finding (NRC Inspection Report 50-346/2003-16-Davis-Besse Control Rod Drive Mechanism Penetration Cracking and Reactor Pressure Vessel Head Degradation |
05/21/03 |
License Amendment Application to Revise Technical Specification (TS) 3/4.5.2, "ECCS Subsystems - Tavg ≥ 280F," to Relocate the Requirements of Technical Specification Surveillance Requirement 4.5.2.h (License Amendment Request No. 03-0002) |
05/19/03 |
License Amendment Application to Revise Technical Specification 3/4.7.1.7, "Motor Driven Feedwater Pump System" to Correct the Safety-Grade Designation of the Motor Driven Feedwater Pump Flow Indication in Surveillance Requirement 4.7.1.7.e.2 (License Amendment Request No. 03-0001) |
05/09/03 |
NRC Integrated Inspection Report 50-346/03-04 |
05/05/03 |
LER 2003-002 Potential Degradation of High Pressure Injection Pums Due to Debris in Emergency Sump Fluid Post Accident |
05/05/03 |
Davis Besse NRC Update - May 2003 Issue |
04/24/03 |
Response to the Nuclear Regulatory Commission (NRC) Preliminary Significance Assessment for the Control Rod Drive Mechanism Cracking and Reactor Pressure Vessel Degradation Identified for the Davis-Besse Nuclear Power Station |
04/23/03 |
Submittal of the Report Titled "Safety Culture Evaluation of the Davis-Besse Nuclear Power Station", dated April 14, 2003 |
04/23/03 |
Westinghouse Letter - Request for Review and Approval of WCAP, "Ambient Temper Bead Repair of Head Adapter Penetrations in PWR Reactor Vessel Upper Heads" |
04/22/03 |
Letter from Brian W. Sheron, NRC to Alex Marion, NEI, regarding Pressurized Water Reactor (PWR) Materials Reliability Project Interim Alloy 600 Safety Assessment for U.S. PWR Plants (MRP-44), Part: Alloy 82/182 Pipe Butt Welds |
04/14/03 |
Davis Besse NRC Update - April 2003 Issue |
04/11/03 |
Letter from R. Barrett, NRC, Office of Nuclear Reactor Regulation (NRR), Division of Engineering to Alex Marion, Nuclear Energy Institute, regarding Flaw Evaluation Guidelines
|
03/31/03 |
LER 2003-001 Potential Inability of Air-Operated Valves to Function During Design Basis Conditions |
03/14/03 |
Issuance of Errata to Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
03/11/03 |
Davis Besse NRC Update - March 2003 Issue |
03/10/03 |
William Travers Letter to Commission - Plans for Implementing the Davis-Besse Lessons Learned Task Force Recommendations |
03/07/03 |
Samuel Collins and Ashok Thadani Letter - Actions Resulting from the Davis-Besse Lessons Learned Task Force Report Recommendations - Correction
|
03/07/03 |
NRC Integrated Inspection Report No. 50-346/03-02 |
02/27/03 |
Licensee Response to 10 CFR 2.206 Petition Filed by Congressman Kucinich |
02/26/03 |
NRC Special Inspection-System Health Assurance-Reports No. 50-346/02-13(DRS) and 50-346/02-14(DRS) |
02/25/03 |
Davis-Besse Control Rod Drive Mechanism Penetration Cracking and Reactor Pressure Vessel Head Degradation Preliminary Significance Assessment (Report No. 50-346/2002-08(DRS)) |
02/20/03 |
Letter from Steven M. Long, Senior Reliability and Risk Analyst - Clarification of the Extent of My Dissent with the Agency's Decision Not to Order the Davis-Besse Plant to Shut Down for Inspection by December 31, 2001 and Explanation of the Basis for My Disagreement |
02/19/03 |
Letter from Alexander Marion, NEI, to Brian Sheron, NRC, on Questions Concerning NRC Order EA-03-009
|
02/19/03 |
Final Significance Determination for Two White Findings and Notice of Violation, NRC Inspection Report No. 50-346/02-16(DRS) |
02/11/03 |
Letter from Samuel J. Collins, Director, Office of Nuclear Reactor Regulation - Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
|
02/10/03 |
Davis Besse NRC Update - February 2003 Issue |
02/06/03 |
NRC Special Inspection-Management and Human Performance Root Cause Assessment-Report No. 50-346/02-15(DRP) |
01/31/03 |
Davis-Besse Nuclear Power Station NRC Integrated Inspection Report 50-346/02-19 |
01/21/03 |
Update of Confirmatory Action Letter 3-02-01B Status for Davis-Besse Nuclear Power Station |
01/14/03 |
Comments in Defense of the Risk-Informed Decision Making Process and on the OIG Event Inquiry, "NRC's Regulation of Davis Besse Regarding Damage to the Reactor Vessel Head" |
01/14/03 |
Davis Besse NRC Update - January 2003 Issue |
01/09/03 |
Submittal of Evaluations Performed at Davis-Besse to Address U. S. NRC Inspection Manual Chapter (IMC) 0350, Item Number 1, Adequacy of Root Cause Determination:
|
01/08/03 |
Overview of Research Related to Degradation of Control Rod Drive Mechanisms
|
01/08/03 |
Memorandum from Chairman Richard A. Meserve to Hubert T. Bell, Inspector General, regarding Report on NRC's Regulation of Davis-Besse Regarding Damage to the Reactor Vessel Head (Case No. 02-03S). |
01/07/03 |
Letter from Chairman Richard A. Meserve to the Editor of the New York Times Regarding Davis-Besse Nuclear Power Plant |
01/07/03 |
NRC Special Inspections - Substantial Potential for an Overexposure of Occupational Workers (Report No. 50-346/02-16(DRS)) and Uncontrolled Release of Radioactive Material to the Environment (Report No. 50-346/02-06(DRS)) Two Preliminary White Findings |
01/03/03 |
Memorandum from William D. Travers, Executive Director for Operations to The Commissioners - Senior Management's Review of the Davis-Besse Lessons Learned Task Force Report |