This page lists, in chronological order, general news and correspondence
on Reactor Vessel Head Degradation for 2004.
Date
|
Description
|
|
|
Davis-Besse Nuclear Power Station NRC Integrated
Inspection Report 05000346/2004015 |
| |
Submittal of Independent Assessment Report
of the Engineering Program Effectiveness at the Davis-Besse Nuclear
Power Station |
|
Davis-Besse NRC Update - December 2004
Issue |
| 11/29/04 |
Correction of Information Provided Regarding
Response to Generic Letter 95-07 |
|
NRC Triennial Fire Protection Baseline
Inspection Report |
|
Submittal of Independent Assessment Report
of Corrective Action Program Implementation for the Davis-Besse Nuclear
Power Station |
|
Davis Besse Inspection Report 2004-014 |
|
Correction of Performance Indicator Data
for the Davis-Besse Nuclear Power Station Alert |
|
|
Letter to Sandy Buchanan - Ohio Citizen
Action |
|
|
Announcement of Special Inspection: Follow-up
of Discrepant Alert and Notification System Performance Indicator |
|
NRC Special Inspection - Management and
Human Performance Corrective Action Effectiveness |
|
|
Submittal of Independent Assessment Report
of Operations Performance for the Davis-Besse Nuclear Power Station |
|
|
LER 04-002-00 for Davis-Besse Nuclear Power
Station, Unit No. 1 Regarding notification of an unplanned reactor
trip during reactor trip breaker testing. |
|
|
Davis Besse NRC Update - September 2004
Issue |
|
Integrated Inspection Report |
|
|
Transmittal of Preliminary Davis-Besse
ASP Analysis for Internal and Licensee Peer Review |
|
|
Request for Additional Information Regarding
Root Cause Analysis Report |
|
|
Revision to Commitments Related to Generic
Letter 2003-01, "Control Room Habitability" |
|
|
Davis-Besse Nuclear Power Station; NRC
evaluations of changes, experiments, or tests and permanent plant
modifications; Inspection Report 05000346/2004010(DRS) |
|
|
Davis-Besse Nuclear Power Station; Flood
Protection Measures, and Maintenance Effectiveness IR 05000346-04-008 |
|
|
Davis Besse NRC Update - July 2004 Issue |
|
|
Re-submittal of Corrective Action Program
Implementation Independence Assessment Plan for Davis-Besse Nuclear
Power Station |
|
|
Submittal of Engineering Program Effectiveness
Independent Assessment Plan for the Davis-Besse Nuclear Power Station |
|
|
Submittal of Independent Assessment Plan
for the Davis-Besse Nuclear Power Station Operations Performance,
Revision 1 |
|
|
Davis-Besse Nuclear Power Station; Routine
Integrated Inspection Report |
|
|
Davis-Besse Nuclear Plant; Initial License
Examination Report |
|
|
Davis-Besse Response to Request for Additional
Information Regarding Root Cause Analysis Report |
|
|
Davis Besse NRC Update - May 2004 Issue |
|
|
Davis-Besse Nuclear Power Station-Notice
of Violation NRC Special Inspection-Completeness and Accuracy of
Required Records and Submittals to the NRC-Report No.50-346/03-19(DRP) |
|
|
Davis-Besse Nuclear Power Station NRC Integrated
Inspection Report 05000346/2004006 |
|
|
Update on Structural Integrity Assessment
of Davis-Besse Reactor Pressure Vessel Head with Corrosion Wastage
Cavity |
|
|
NRC Special Inspection Report 50-346/04-04
Restart Readiness Assessment Team Follow-Up Inspection. |
|
|
NRC Integrated Special Inspection Report
05000346/2004002 |
|
|
Correction of Information Provided Regarding
Status of the Design Basis Validation Program. |
|
|
Correction to Response date for Request for additional information
regarding the Davis-Besse root cause analysis of the reactor pressure
vessel head degradation.
|
|
|
Davis-Besse Nuclear Power Station - Inspection
Schedule Update |
|
|
NRC Press Release III-04-011: NRC Approves
Davis-Besse Restart |
|
|
Approval to Restart the Davis-Besse Nuclear
Power Station, Closure of Confirmatory Action Letter, and Issuance
of Confirmatory Order |
03/08/04
|
Davis-Besse Unit 1, Amendment, One-Time
Extension of Steam Generator Tube Inservice Inspection
|
|
|
Confirmatory Order Modifying License (Effective
Immediately) |
|
|
Inspection Report 50-346/04-05 - HPI Pump
Final significance Letter |
|
|
NRC Special Team Inspection Report 50-346/02-10,
Corrective Action Program Implementation and Notice of Violation |
|
|
Request for additional information regarding
root cause analysis submitted to the NRC concerning the reactor pressure
information. |
|
|
LER 04-001-00 for Davis-Besse, Unit 1 Regarding
Violation of Steam and Feedwater Rupture Control System Technical
Specification |
|
|
NRC Special Inspection Report 50-346/03-12
- Management and Human Performance Root Cause Assessment Phase 3 |
|
|
Meeting Slides from NRC Commission Briefing
on Status of Implementation of Davis-Besse Lessons Learned Task Force
Recommendations |
|
|
Recommendation for NRC to Approve Restart
of the Davis-Besse Nuclear Power Station and Recommendation to
Issue Confirmatory Order
|
|
|
Licensing Renewal Related Correspondence,
Updated Forecast for Submittal of License Amendment Applications
to Convert to the Improved Standard Technical Specifications and
Renew the Operating License |
02/23/04
|
Semiannual Report - Status of Implementation of Davis-Besse Lessons
Learned Task Force Report Recommendations
|
|
|
Revised Order EA-03-009 |
|
|
Disposition of Reactor Vessel Head Sample
Pieces "A2A7L," A2A7M," and A2A7N." |
|
|
Request to Amend the Existing Exemption
from 10 CFR 50.46 and 10 CFR 50, "Appendix K, for Boric Acid
Precipitation Control Methodology. |
|
|
Supplemental Information Regarding License
Amendment Application to Revise Technical Specification 3/4.4.5, "Reactor
Coolant System - Steam Generators (SG)," to Permit One-Time
Extension of SG Tube Inservice Inspection Interval. |
|
|
Davis Besse NRC Update - February 2004
Issue |
|
|
Tech Spec Change, Related Correspondence,
Correction of Information Provided in License Amendment Request No.
96-0008 |
|
|
Supplement to the Integrated Report to
Support Restart of the Davis-Besse Nuclear Power Station |
|
|
NRC Special Inspection - Restart Readiness
Assessment Team Inspection Report No. 05000346/2003011 (DRP) |
|
|
Supplemental Information Regarding License
Amendment Application to Revise TS 3/4.5, "Reactor Coolant System
- Steam Generators," to Permit One-Time Extension of Steam Generator
Tube Inservice Inspection Interval. |
|
|
NRC Special Inspection Report 50-346/03-19
- Completeness and Accuracy of Required Records and Submittals to
the NRC |
|
|
NRC Integrated Inspection Report 05000346/2003025 |
|
|
Davis Besse NRC Update - January 2004
Issue |
|
|
Request for Exemption From 10CFR50, Appendix
R, Section III.G.3 for Fire Area HH. |
|
|
Supplemental Information Regarding License
Amendment Applications to Modify Technical Specification 3/4.5.2,
Emergency Core Cooling Systems - ECCS Subsystems |
|
|
Response to Questions Regarding the 2002
Steam Generator Tube Inspections. |
|
|
LER 03-011-01. Davis-Besse Unit 1 Inoperability
of Containment Spray Pump 1 Due to Solid State Trip Device Ground
Fault False Trip |
|
|
NRC Special Inspection Report No. 05-346/03-24 |
