This page lists, in chronological order, general news and correspondence
on Reactor Vessel Head Degradation for 2003.
| 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
|
| 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 |
