ML030440168
| ML030440168 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/11/2003 |
| From: | Myers L FirstEnergy Corp, FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030440168 (45) | |
Text
Davis-Besse Nuclear Power Station IMC 0350 Meeting 1
Davis-Besse February 11, 2003 Nuclear Power Station
Opening Remarks Lew Myers Chief Operating Officer - FENOC 2
Davis-Besse February 11, 2003 Nuclear Power Station
Desired Outcomes
- Update Progress Made Toward Readiness
- Restart Readiness...Randy Fast
- Containment Integrated Leak Rate TestJim Powers
- System Health Assurance Building Blocks
- Safety Functional Validation ProjectBob Schrauder
- Management Reviews for Reload
- Restart Readiness and Safety Culture....Lew Myers
- Nuclear Quality Assessments...Steve Loehlein
- Schedule Update/Upcoming Activities
- Integrated Schedule Progress.....Mike Stevens 3
Davis-Besse February 11, 2003 Nuclear Power Station
Return to Service Plan Restart Overview Panel Reactor Head System Health Resolution Plan Assurance Plan Bob Schrauder Jim Powers Program Compliance Restart Test Plan Plan Restart Action Plan Randy Fast Jim Powers Lew Myers Management and Containment Health Human Performance Assurance Plan Excellence Plan Randy Fast Lew Myers 4
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness Randy Fast Plant Manager 5
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Fuel
- Inspections and corrective actions
- Re-manufactured assembly
- Fuel handling bridge modification/readiness
- Experienced team (Operations and Framatome)
- Training completed 6
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Reactor Coolant Pumps 7
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Upper portion of the Containment Emergency Sump 8
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Decay Heat Pit 9
Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Containment Air Coolers 10 Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Plenum for Containment Air Coolers (Inside) 11 Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Plant
- Containment Dome 12 Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness
- Process
- Readiness Reviews
- Management Oversight
- Refuel Director Roles &
Responsibility
- Observations 13 Davis-Besse February 11, 2003 Nuclear Power Station
Containment Integrated Leak Rate Test Jim Powers Director- Nuclear Engineering 14 Davis-Besse February 11, 2003 Nuclear Power Station
Containment Integrated Leak Rate Test
- Integrated Leak Rate Test (ILRT):
Containment is pressurized to test conditions that would occur in a design base accident.
- Leakage Test Required by ASME Code
- Test Performed per 10 CFR 50, Appendix J
- Test Performed in 1991 and 2000
- Local leak rate test of repair of containment
- Scheduled Completion: Early March, 2003
- Containment Pressure: > 38 psig
- Length of Test: ~ 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> 15 Davis-Besse February 11, 2003 Nuclear Power Station
System Health Assurance Bob Schrauder Director - Support Services 16 Davis-Besse February 11, 2003 Nuclear Power Station
Background
- System Health Assurance Plan
- Operational Readiness Reviews
- System Health Readiness Reviews
- Latent Issues Reviews
- Additional Reviews
- Self Assessments
- NRC Inspections
- Potential Issues Documented in Corrective Action Program 17 Davis-Besse February 11, 2003 Nuclear Power Station
Issue Resolution Issues Path A Path B Path C Topical Issue Corrective Action Safety Function Collective Significance Program Validation Project Review 18 Davis-Besse February 11, 2003 Nuclear Power Station
Safety Consequence Review
- Identify Potential Safety Issues
- Restart required Condition Reports
- Sources
- Latent Issues Reviews (LIR)
- Self Assessments
- NRC Safety-System Design and Performance Capability Inspection
- Categorization Based on Potential Impact on Plant Safety
- > 600 Condition Reports (CRs) reviewed
- 8% (51 CRs) with potential impact on plant design basis
- 51 CRs represent 28 individual issues
- Majority of Potential Issues Related to Calculations 19 Davis-Besse February 11, 2003 Nuclear Power Station
Safety Function Validation Project
- Purpose
- To provide assurance that safety functions that provide significant contributions to Core Damage Frequency (CDF) can be performed
- Assess extent of condition for calculation issues
- Evaluate Safety Functions Contributing > 1% of CDF
- Safety Functions are Provided by 15 Safety Systems
- 5 evaluated by Latent Issues Review
- 2 partially evaluated by Self-Assessment
- 8 additional systems added to review 20 Davis-Besse February 11, 2003 Nuclear Power Station
Safety Function Validation Project
- Review Methodology
- Defined safety functions and attributes to be validated
- Identified available calculations and testing that demonstrate system capability to perform function
- Reviewed calculations and testing to validate safety function/attribute
- For Functions/Attributes Not Fully Validated
- Performed technical evaluations
- Determined effect on system capability
- Supported Operability Determinations (if required)
- Non-Conformances Entered into Corrective Action Program 21 Davis-Besse February 11, 2003 Nuclear Power Station
Project Results
- Systems Fully Validated
- High Pressure Injection
- Safety Features Actuation System
- Systems Requiring Additional Analysis
- Low Pressure Injection System
- Emergency Core Cooling System-HVAC
- Steam Feed Rupture Control System
- Electrical Distribution Systems 22 Davis-Besse February 11, 2003 Nuclear Power Station
Issue Resolution Issues Path B Path C Path A Topical Issue Corrective Action Safety Function Collective Significance Program Validation Project Review 23 Davis-Besse February 11, 2003 Nuclear Power Station
Collective Significance Reviews
- System Health Assurance Plan Reviews Identified Potential Cross Cutting Issues
- Collective Significance Review Identified Five Programmatic Areas Warranting Evaluation
- Seismic Qualification
- High Energy Line Break (HELB)
- Environmental Qualification (EQ)
- Appendix R Safe Shutdown Analysis
- Station Flooding 24 Davis-Besse February 11, 2003 Nuclear Power Station
Review Process
- Nuclear Operating Business Procedure-LP-2006, Collective Significance Review Used
- Consistent process
- Consistent format
- Evaluation Process
- Condition Report database provides population of issues to evaluate
- Bin condition reports into common issue areas
- Evaluate each issue area to determine programmatic impact
- Conduct extent-of-condition evaluation where warranted
- Determine and schedule corrective actions
- Engineering Assessment Board to Review Results 25 Davis-Besse February 11, 2003 Nuclear Power Station
Summary
- Good Correlation with System Health Readiness Reviews
- More Analytical Work Necessary
- No Major Modifications Identified
- Some Rigor in Calculations Lacking 26 Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness and Safety Culture Assessment Lew Myers Chief Operating Officer - FENOC 27 Davis-Besse February 11, 2003 Nuclear Power Station
Background
- Root Cause Report on Reactor Pressure Vessel Head Degradation Found:
- Production focus, established by management, combined with taking minimum actions to meet regulatory requirements, resulted in acceptance of degraded conditions
- Davis-Besse was operated as a stand alone plant
- Conditions were identified at relative low threshold, but not properly classified or evaluated by management
- Quality Assurance finding were mixed quality
- Operations not active in role of improvements in plant conditions 28 Davis-Besse February 11, 2003 Nuclear Power Station
Definitions
- Safety Culture: That assembly of characteristics and attitudes in organizations and individuals which establishes an overriding priority towards nuclear safety activities and ensures that issues receive the attention warranted by their significance.
- Safety Conscious Work Environment: That part of a Safety Culture addressing employee willingness to raise issues and managements response to these issues.
29 Davis-Besse February 11, 2003 Nuclear Power Station
Safety Culture - - FENOC Model Drive for Safety Culture Excellence Questioning Attitudes Rigorous Work Control and Prudent Approach Emphasis on Individuals Open Communications Safety Commitment Nuclear Clear Professionalism Responsibilities and Cohesiveness Acceptance of Responsibility Managers Statement of Commitment Safety Policy Qualification and Training Management Value Structure High Organizational Commitment Policy Level Resources Commitment Oversight and Self Regulation 30 Davis-Besse February 11, 2003 Nuclear Power Station
Actions Taken
- Policy
- FirstEnergy Board of Directors passed and issued a resolution on Nuclear Safety
- FENOC Policy on Safety Culture and Safety Conscious Work Environment
- Strengthened Incentive Program to tie to safety
- Established Independent Executive - Level Quality Assurance, Executive VP Engineering and Chief Operating Officer
- Strengthened Employee Concerns Program
- Management
- Strong technically competent management team
- Strengthened Corrective Action Program/Corrective Action Review Board
- Improved leadership competencies
- Strengthened problem-solving and decision-making Nuclear Operating Procedure
- Engineering Assessment Board to monitor engineering products
- Individual
- Reactor Vessel Head group training
- Town Hall meetings
- 4Cs meetings with small groups with site Vice-President
- Operability training
- Requalified all Root Cause Evaluators 31 Davis-Besse February 11, 2003 Nuclear Power Station
Restart Readiness Review
- Purpose
- To determine why we should load fuel
- Group Review Readiness
- Assured Plant and Staff is Ready for fuel load
- Key Review Programs
- Corrective Action Program
- Management Observation Program
- Radiological Control Program
- Reactor Coolant System Leakage Program
- Employee Concerns Program
- System Engineering Reviewed Key Systems
- Safety Culture of Employees was Assessed 32 Davis-Besse February 11, 2003 Nuclear Power Station
Monitoring Safety Culture for Fuel Load
- Safety Culture Commitments Rating
- Individual group assessment
- Green: All major areas are acceptable with a few minor deviations
- White: All major areas are acceptable with a few indicators requiring management action
- Yellow: All major areas are acceptable with several indicators requiring management action
- Red: Several major commitment areas do not meet acceptable standards and require immediate management action 33 Davis-Besse February 11, 2003 Nuclear Power Station
Monitoring Safety Culture for Fuel Load
- Ratings Based on Convergent Assessment
- Performance Indicators (e.g., Risk Index, Backlogs)
- Management Observations
- Demonstrated Performance During Critical Plant Conditions (e.g.,
Fuel Load)
- Feedback from Independent Safety Culture Review and Nuclear Quality Assurance Assessments
- Performance, Safety and Health Associates
- Sonja B. Haber, Ph.D.
34 Davis-Besse February 11, 2003 Nuclear Power Station
Fuel Load Safety Culture Assessment Safety Culture Drive for Excellence Questioning Attitudes Rigorous Work Control and Prudent Approach Individuals Open Communications Emphasis on Safety Commitment Nuclear Clear Professionalism Responsibilities and Cohesiveness Acceptance of Responsibility Managers Statement of Commitment Safety Policy Qualification and Training Management Value Structure High Organizational Commitment Policy Level Resources Commitment Oversight and Self Regulation 35 Davis-Besse February 11, 2003 Nuclear Power Station
Summary
- Safety Culture Model is Unique and State of the Art
- Safety Culture Assessment is Innovative
- Under refinement
- Provides fair assessment of status
- Contains areas that are qualitative and quantitative
- Useful tool for management focus
- Assessment is a Fair Representation of Our Readiness for Fuel Load 36 Davis-Besse February 11, 2003 Nuclear Power Station
Nuclear Quality Assessments Steve Loehlein Manager - Quality Assessments 37 Davis-Besse February 11, 2003 Nuclear Power Station
Nuclear Quality Assessments
- Past/Recent Observations and Assessments
- Safety Function Validation Project
- Fuel Spacer Grid Damage and Associated Stop Work
- Restart Readiness Meetings
- Restart Station Review Board Decision-Making
- Operations Readiness for Mode Ascension
- Integrated Safety Features Actuation System Test Preparation and Completion
- Reactor Coolant Pump and Vessel Head Heavy Lifts 38 Davis-Besse February 11, 2003 Nuclear Power Station
Nuclear Quality Assessments
- Current/Ongoing Activities
- System Health Readiness Reviews
- Program Reviews
- Radiation Protection Phase II Program Review
- Safety Culture and Safety Conscious Work Environment Independent Survey
- Corrective Action Program Implementation Plan
- Implementation of Corrective Actions
- Safety Function Validation Project 39 Davis-Besse February 11, 2003 Nuclear Power Station
Nuclear Quality Assessments
- Upcoming Observations and Assessments
- Restart Test Plan and Associated Procedures
- Fuel Movement Activities
- Radiation Protection Activities
- Evaluation and Integration of Results from Safety Function Validation Project
- Effectiveness of Actions Taken in Corrective Action Program 40 Davis-Besse February 11, 2003 Nuclear Power Station
Integrated Schedule Progress Mike Stevens Director- Work Management 41 Davis-Besse February 11, 2003 Nuclear Power Station
Integrated Schedule Progress
- Critical Path Milestones for Containment Testing
- Install and Bolt the Reactor Head
- Complete Lower Portion of Emergency Sump Strainer
- Perform Integrated Safety Features Actuation System Test/Train #2
- Complete Decay Heat Valve Tank
- Fill and Vent the Reactor Coolant System
- Perform Integrated Leak Rate Test on Containment Vessel 42 Davis-Besse February 11, 2003 Nuclear Power Station
Integrated Schedule Progress
- Critical Path Milestones for Reactor Coolant System Testing
- Readiness Review for Reactor Coolant System Pressure Test
- Reactor Coolant System Inspection
- Non-Nuclear Heat-up
- Operate 7 days at Normal Operating Pressure and Normal Operating Temperature
- Reactor Coolant System Inspection
- Under Vessel Nozzle Inspection 43 Davis-Besse February 11, 2003 Nuclear Power Station
Performance Measures Clark Price Owner - Restart Action Plan 44 Davis-Besse February 11, 2003 Nuclear Power Station
Closing Remarks Lew Myers Chief Operating Officer - FENOC 45 Davis-Besse February 11, 2003 Nuclear Power Station