ML031770219

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Firstenergy Nuclear Power Company Public Meeting Presentation with NRC Davis-Besse Nuclear Power Station
ML031770219
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/03/2003
From:
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML031770219 (64)


Text

Davis-Besse Nuclear Power Station IMC 0350 Meeting 1

Davis-Besse ar Power Station June 3, 2003

Desired Outcome

  • Provide an Update on Plant Performance and Management

& Human Performance Progress Since the Last Meeting

  • Provide Information Concerning Decision on the High Pressure Injection Pump
  • Provide an Update on the Quality Oversight Perspective
  • Provide Status on Several Engineering Design Issues
  • Status our Overall Schedule and Performance Indicators Lew Myers FENOC Chief Operating Officer 2

Davis-Besse ar Power Station June 3, 2003

Meeting Agenda Pressure Test Results; Containment Closure...Mark Bezilla Management & Human Performance Plan Update....Lew Myers Electrical Distribution; SFAS Relays.....Jim Powers HPI Pump Modification; Corrective Action Program Performance.....Bob Schrauder Quality Assessment Activity..Steve Loehlein Remaining Issues Focus.....Mike Ross Schedule MilestonesMike Stevens Restart Action Performance...Clark Price 3

Davis-Besse ar Power Station June 3, 2003

and Containment Closure Mark Bezilla Vice President/Plant Manager 4

Davis-Besse ar Power Station June 3, 2003

and Containment Closure Desired Outcome

  • Provide an update on Containment Activities 5

Davis-Besse ar Power Station June 3, 2003

Reactor Coolant System Pressure Tests

  • Completed 50 psig Leak Test - May 6, 2003
  • Completed 250 psig Leak Test - May 25, 2003
  • Accomplishments:

- Determined that we could only heat up the Reactor Coolant System (RCS) due to decay heat, to <140 degrees

- Placed Makeup and Purification System in service

- Verified Pressurizer Heaters and spray functions

- Ran each Reactor Coolant Pump

- Gained confidence in the performance of the RCS and support systems 6

Davis-Besse ar Power Station June 3, 2003

Containment Closure

  • Containment Health Actions
  • Containment Work
  • Containment Closure
  • Containment Ownership Turnover from Containment Health to Operations 7

Davis-Besse ar Power Station June 3, 2003

Plan Update Lew Myers FENOC Chief Operating Officer 8

Davis-Besse ar Power Station June 3, 2003

Plan Update Desired Outcome

  • Demonstrate Strong Actions Taken to Date to Address Management and Human Performance
  • Demonstrate Plan for Site Alignment and Leadership Going Forward 9

Davis-Besse ar Power Station June 3, 2003

Plan Update Actions to Date

  • FENOC Corporate Organization Changes
  • Davis-Besse Management Changes
  • Independent Quality Assessment Organization
  • Established and Communicated Standards
  • Added/Enhanced Internal Oversight Groups

- Engineering Assessment Board

- Project Review Committee

- Corrective Action Review Board

- Management Review Board 10 Davis-Besse ar Power Station June 3, 2003

Plan Update Actions to Date (continued)

  • Added/Enhanced External Oversight Groups

- Restart Overview Panel, Company Nuclear Review Board

  • Improved Corrective Action Program and Oversight
  • Management Observation Program
  • All-hands Case Study Training
  • Leadership Team Training 11 Davis-Besse ar Power Station June 3, 2003

Plan Update Actions to Date (continued)

  • Employee Concerns Program Improvements
  • Increased Technical Rigor

- Calculation Program

- FENOC Problem Solving and Decision Making Nuclear Operating Procedure

- Operability Evaluations 12 Davis-Besse ar Power Station June 3, 2003

Plan Update Actions to Date (continued)

  • Initiated Several Employee Communication Mechanisms Cs, Town Hall & All-hands meetings
  • Section Specific Improvement Initiatives
  • Developed Performance Indicators for Monitoring Performance 13 Davis-Besse ar Power Station June 3, 2003

Plan Update FENOC Definition Safety Culture That assembly of characteristics and attitudes in organizations and individuals which establishes an overriding priority towards nuclear safety activities and that these issues receive the attention warranted by their significance.

14 Davis-Besse ar Power Station June 3, 2003

Plan Update FENOC Definition Safety Conscious Work Environment That part of a Safety Culture addressing employee willingness to raise issues and managements response to these issues.

15 Davis-Besse ar Power Station June 3, 2003

Plan Update Site Integration Plan: May-December 2003 eline Site Alignment and Leadership Development Interventions y - Response to Haber Report Development Plans for Directors 3-Day SMT Intervention One-on-One Coaching Starts with and Managers -- completed and (Haber Report Review) SMT Members and Managers Interviews with SMT members approved and Managers 3-Day Intervention w/Mgrs Facilitative Leadership Training?

Exelon Benchmark Transition / Restart Plan 360° Feedback (SMT and Mgrs) SCWE Training Management Observation Prog.

Work Management Safety-Focus Improvement Rollout Fill Open Supv. Positions Cross-functional 1 day all-site Process training day Focus on Safety as a Leadership Form Design Team for Cross-Team functional 1-day all-site trg ust - 1-2 Day Intervention with both Assessment Process for 1 - Day SMT Follow Up 2 - Day All Site Large Scale tember SMT and Managers internalizing capabilities to assess Intervention Meeting (Vision Map?)

supervisors All-Leadership Session - Supvs. 1 - Day Managers Follow Up Leadership Academy for SMT and Bi-monthly Form Cross-Functional Design Intervention Managers (Pilot?)

Team for 2-Day All-Site Large FENOC internal Safety Culture Scale Meeting Reinstate MRM, Business Plan, Long-term Safety Culture Tool -- format to use post restart Performance Indicators Improvement Plan ober - 1 - Day SMT Follow Up SCWE - 6 month follow-up survey All Leadership Session - Supvs. 1-Day All Site Large Scale ember Intervention Bi-monthly Meeting QA focused-assessment of safety 1-Day Managers Follow Up Culture Form Cross-Functional Design Intervention Team for 1-Day All-Site Large Scale Meeting 16 Davis-Besse ar Power Station June 3, 2003

Plan Update Upcoming Safety Culture Actions

  • Improve the Work Management Safety Oversight Process
  • Facilitated Site Alignment Activities

- Leadership development and coaching

- Department/section activities

- All-site meetings

  • Site Safety Conscious Work Environment Training

- Prior to Mode 2 - during all-site training day 17 Davis-Besse ar Power Station June 3, 2003

Plan Update Upcoming Safety Culture Actions (continued)

  • Focused Organizational Development Activities

- Engineering

- Maintenance

  • Continued Employee Communications

- Reinstate weekly managers meeting

- Initiate monthly department/section meetings

- Continue monthly site meetings

- Conduct weekly Senior Management Team strategy meetings 18 Davis-Besse ar Power Station June 3, 2003

Plan Update Safety Culture Monitoring

  • Safety Conscious Work Environment Surveys

- 3rd quarter 2003, then annually for 2 years

  • Internal Quality Assurance Assessments

- 4th quarter 2003, then annually for 2 years

  • FENOC Internal Safety Culture Assessment

- Prior to Mode 4 (Restart Readiness)

- Prior to Mode 2 (Restart Readiness)

- Prior to restart from subsequent outages

- FENOC going-forward process 19 Davis-Besse ar Power Station June 3, 2003

Plan Update Other Activities

  • Create a New Vision Map
  • Align Station Business Plan Activities/Incorporate into Monthly Review Meeting
  • Future State Stand-down 20 Davis-Besse ar Power Station June 3, 2003

and Safety Features Actuation System Relays Jim Powers Director - Engineering 21 Davis-Besse ar Power Station June 3, 2003

Electrical Distribution Emergency Diesel Generator (EDG) Issues/Resolution

  • Completed

- Operations accepted Operability Evaluation on May 15

- EDGs operable for all Modes

  • Plant Start-up

- Revise EDG Steady State Loading Calculation

- Revise EDG Transient Loading Calculation

- Prepare and issue USAR change; in draft

- Define acceptance criteria for EDG voltage and frequency response

  • Post-restart

- Evaluate actions to improve EDG voltage and frequency response during Safety Features Actuation System load sequencing 22 Davis-Besse ar Power Station June 3, 2003

Electrical Distribution AC System Issues/Resolution

  • First Mode 4

- Prepare Electrical Transient Analysis Program (ETAP) calculation

- Complete Evaluation Impacts of plant equipment

- Complete independent industry team review of ETAP analysis

- Evaluate conditions with unusual lineups to determine actions necessary going forward 23 Davis-Besse ar Power Station June 3, 2003

Safety Features Actuation System Relays

  • Originally Characterized as an Obsolescence Issue

- Supplier stopped manufacturing replacements

  • Reviews Found the Predominant Reason for Replacement was Coil Related

- Replacements were random with respect to age

  • Testing of Installed Relays has been Conducted

- Outliers were removed and will be replaced

- Relay population will gain improved reliability

  • Action Plan has been approved

- Obtain replacement relays from another utility 24 Davis-Besse ar Power Station June 3, 2003

Safety Features Actuation System Relays

  • Technical Evaluation (TE) is in Progress

- Industry experts are reviewing maintenance history

  • Average replacement rate has been at relatively the same level of 2% per year for about the last 20 years

- Temperature related aging does not appear to be an issue; further tests are under way to confirm

- Relay material condition is being assessed to further confirm suitability to function for another fuel cycle

- Independent review of TE will be conducted

  • Conclusion

- Operability evaluation will contain technical evaluation and confirm operability

  • Confirm that relays are acceptable for operation through the next operating cycle 25 Davis-Besse ar Power Station June 3, 2003

and Corrective Action Program Performance Bob Schrauder Director -Support Services 26 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification

  • Background

- Identified an issue that fine debris could impact the existing internal pump clearances

  • Selected Approach

- Modify the existing pump to add internal strainer to prevent debris from entering hydrostatic bearing

- This will allow the pumps to perform all design functions without replacement

  • Project Milestones

- Strainer design and testing

- Pump performance validation

- Field implementation 27 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification

  • Strainer Design and Testing

- Strainer allows water to pass through and supply the hydrostatic bearing and seal

  • flushes strainer surface

- Relocate ports that supply water to the hydrostatic bearing

  • supported by testing performed by pump manufacturer, Pump Guinard of France
  • reduce debris concentration at strainer

- MPR Associates performing design work

  • mock-up testing at Wyle Labs to verify performance 28 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification 29 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification

  • Pump Performance Validation

- Rotordynamics analysis performed to predict satisfactory pump operation

  • includes worn condition after debris service

- In-plant testing is being performed to validate rotordynamics model

- Post-modification testing will be performed prior to returning the pumps to service 30 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification

  • Field Implementation

- Both pumps must be removed; each weighs 6,000 pounds

- Removal of HPI pump 2 requires detailed planning due to its location in the Emergency Core Cooling Pump Room

- A team involving six different craft disciplines will be used to remove the pumps and interference

- Design and Plant Engineering are key groups involved with the removal plans 31 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification A full scale pump mock-up was used to determine rigging needs and pathway 32 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification Rigging needs determined through the use of a full scale HPI pump mock-up 33 Davis-Besse ar Power Station June 3, 2003

High Pressure Injection Pump Modification Summary

  • Implementation of this Modification will Resolve the Debris Issue
  • Current Schedule shows completion supports Pressure Test in mid-to-late July 34 Davis-Besse ar Power Station June 3, 2003

Corrective Action Program Corrective Action Program Review Items

  • Corrective Action Categorization
  • Corrective Action Quality
  • Corrective Action Timeliness
  • Rollover Process 35 Davis-Besse ar Power Station June 3, 2003

Corrective Action Program Categorization

  • New Process Effective March 1, 2003

- Issued revision to NOP-LP-2001, Condition Report Process

- New Condition Reports issued since ~ 2,500

  • Restart Goal is to Maintain a 12-Week Rolling Average Level of 90% or Better
  • Management Review Board Upgrades

- Category changed to a higher level ~5%

36 Davis-Besse ar Power Station June 3, 2003

Corrective Action Program Categorization CONDITION REPORT CATEGORY ACCURACY Goal > 90 % Good 100%

Category Recommendations Not Escalated 90%

80%

70%

60%

50%

1/ 5 1/ 1 2 1/ 1 9 1 / 26 2/ 2 2/ 9 2/ 1 6 2/ 23 3/ 2 3/ 9 3/ 16 3/ 23 3/ 3 0 4/ 6 4 / 13 4/ 20 4/ 2 7 5/ 4 5/ 1 1 5 / 18 5/ 25 6/ 1 6/ 8 6/ 15 6 / 22 6/ 29 12 Week Avg 37 Davis-Besse ar Power Station June 3, 2003

Corrective Action Review Board 100% 25 Restart Goal = positive trend Good Long -term Goal 90%

80% Restart Goal = positive trend 20 Long-term Goal 90%

CARB Accepted 60% 15 40% 10 20% 5 0% 1/ 5 1/ 12 1/ 19 1/ 26 2/ 2 2/ 9 2/ 16 2/ 23 3/ 2 3/ 9 3/ 16 3/ 23 3/ 30 4/ 6 4/ 13 4/ 20 4/ 27 5/ 4 5/ 11 5/ 18 5/ 25 6/ 1 6/ 8 6/ 15 6/ 22 6/ 29 0

Reject 0 0 0 5 1 0 0 0 0 6 3 1 Accept 0 0 0 0 4 0 0 2 0 14 5 1 12 Week Avg 62%

Goal 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90% 90%

Accept Reject Goal 12 Week Avg

  • Apparent Cause - CARB Acceptable Rate ~ 62%

38 Davis-Besse ar Power Station June 3, 2003

Corrective Action Review Board 100% 10 Good 80% 8 CARB Approval Restart Goal = improving trend 60% Long -term Goal 90% 6 40% 4 20% 2 0% 1/ 5 1/ 12 1/ 19 1/ 26 2/ 2 2/ 9 2/ 1 6 2/ 23 3/ 2 3/ 9 3/ 16 3/ 23 3/ 30 4/ 6 4/ 13 4/ 20 4/ 27 5/ 4 5/ 1 1 5/ 1 8 5/ 25 6/ 1 6/ 8 6/ 15 6/ 22 6/ 29 0

Reject 0 0 0 0 0 1 1 2 0 0 0 0 0 1 1 0 0 0 0 0 0 Appr o ve d wi t h c omme nt s 0 0 0 1 1 1 0 2 1 0 1 1 3 2 3 2 1 0 1 0 0 Appr o ve d 0 0 0 0 0 0 0 0 0 1 0 0 2 0 1 0 0 0 0 0 0 12 -We e k % Apvd Avg 57% 5 7% 4 0% 33% 17% 13% 13% 8% 8% 15% 8% 8% 17 % 14% 1 5% 15 % 15% 16% 16% 19% 20%

12 -We e k % Apvd &Apv d w/ c omme nt s 100% 100% 100% 100% 1 00% 88% 75% 67% 67% 69% 67% 6 9% 78 % 76% 7 7% 78 % 78% 80% 84% 90% 90%

Approve d Approve d wit h c omme nt s Re je c t 12-We e k % Apvd & Apvd w/ c omme nt s 12-We e k %Apvd Avg

  • Root Causes - CARB Acceptable Rate ~ 90%

39 Davis-Besse ar Power Station June 3, 2003

Timeliness 80%

Goal < 5% Good Overdue Open Corrective Actions Overdue 60%

40%

20%

0%

Overdue % Goal

  • Goal: < 5% overdue corrective actions 40 Davis-Besse ar Power Station June 3, 2003

Investigation Timeliness 80%

Goal < 5%

Good Overdue Open Investigations Overdue 60%

40%

20%

0%

Overdue % Goal

  • Goal: < 5% overdue corrective action investigation 41 Davis-Besse ar Power Station June 3, 2003

Supervisor Review Timeliness CONDITION REPORT SUPERVISORY REVIEW Goal > 90% Good 10 0 %

Supervisory Reviews Completed Within 1 Day 80%

60%

40%

20%

12 Week Avg

  • Goal: 90 % or more supervisor reviews completed one day or less

- 89% completed within one day or less 42 Davis-Besse ar Power Station June 3, 2003

SRO Review Timeliness CONDITION REPORT SRO REVIEW Goal > 95% Good 100%

SRO Reviews Completed Within 1 Day 80%

60%

40%

20%

12 Week Avg

  • Restart goal: > 95% of the SRO reviews to be completed within one day

- 86% of SRO completed within one day 43 Davis-Besse ar Power Station June 3, 2003

Rollover Process

  • Rollover Definition

- The method of transferring the evaluation (complete or partial) of issues(s) addressed in one Condition Report (CR) to another, more encompassing CR

  • Difficulties Identified

- Paper trail is hard to follow at times

- Exacerbated by the large number being processed

- Generally concentrated in specific areas

- Few isolated cases actually have not been effectively resolved

  • Recommended Improvements

- Perform independent assessment

- Recently revised NOP-LP-2001, Condition Report Process, has rollover criteria

- Strengthened rollover criteria in future Nuclear Operating Procedure revision based on lessons-learned 44 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Steve Loehlein Manager - Quality Assessment 45 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Independent Review of Condition Reports

  • Led by Nuclear Quality Assessment
  • Team Members from other Departments and other FENOC Sites
  • Scope Includes all 0350 Restart Condition Reports/Corrective Actions 46 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Objectives

  • Confirm that Initially Identified Condition has been Evaluated
  • Track/Confirm that Issues Rolled to Another Condition Report were not lost
  • Document any Resulting Concerns in the Corrective Action Process for Resolution 47 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Status of Review (as of May 27)

  • 1783 - 0350 Restart Condition Reports (CRs)
  • 7700 Associated Corrective Actions (CAs )
  • 510 Associated Rollovers 48 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Reviews Completed to date (as of May 27)

  • 5057 CAs reviewed (includes Rollover CAs)

- 4379 CAs found to be acceptable (87% of those reviewed)

- 678 CAs continue in review (13% of those reviewed)

  • 510 Rollover CAs (100%)

- 415 Rollover CAs found to be acceptable (81%)

- 95 Rollover CAs continue in review (19%)

49 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Identified Concerns

  • Weaknesses in Documenting Resolution of the Identified Concern
  • Evaluations that do not address Full Scope of Identified Issue
  • Two Isolated Examples of incorrect Actions
  • Concerns have been Identified with the involved Department and reported on Condition Reports 50 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Recent Key Activities

  • Observations of Technical Issues Resolution
  • Quality Control Oversight of Vendor Activities 51 Davis-Besse ar Power Station June 3, 2003

Quality Assessment Update Current Activities

  • Focused Assessment of Corrective Action Program

- Training drills, controller briefs, actual exercises

  • Management Decision-Making, Safety Culture, Radiation Protection, and Regulation Driven Changes to the Security Program 52 Davis-Besse ar Power Station June 3, 2003

Remaining Issues/Focus Mike Ross Restart Director 53 Davis-Besse ar Power Station June 3, 2003

Remaining Issues/Focus Plant Support Center

  • In Full Operation
  • Issue List Developed
  • Action Item Database
  • Issues Needing Decision brought to Senior Management Team in Timely Fashion
  • Developed Issue Resolutions with Fragnet Transferred to Outage Control
  • Director, Nuclear Supply Chain on Site and Part of Plant Support Center Meeting to expedite Supply Requests
  • Listing of Modifications 54 Davis-Besse ar Power Station June 3, 2003

Remaining Issues/Focus Focus

  • Early Identification of Emergent Issues
  • Review of Plant Issues to ensure Proper Prioritization and Resolution
  • Issue Receiving Extra Focus

- HPI Modification

- Electrical Transient Analysis Program (ETAP)

- Safety Features Actuation System Relays

- Air-Operated Valve Program

- Plant Block Walls Seismic & Tornado Loading

- Thermal Overload Bypass of Safety Related Motors

  • Recent additions to Modification List

- Containment Spray Cyclone Separator

- Boron Precipitation Modification 55 Davis-Besse ar Power Station June 3, 2003

Schedule Milestones Mike Stevens Director - Maintenance 56 Davis-Besse ar Power Station June 3, 2003

Upcoming Activities Schedule Milestones

  • Complete Electrical Transient Analysis Program for Mode 4
  • Perform Testing on HPI 1 & 2
  • Refill Circulating Water and draw Condenser Vacuum
  • Conduct Mode 4 Restart Readiness Review
  • Enter Mode 4/Mode 3
  • Complete Train 2 work, followed by Train 1 work
  • Conduct Startup Readiness Review Meeting
  • Startup 57 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance Clark Price Owner - Restart Action Plan 58 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance Item 0350 Checklist Item Description Discovery Implementation No.

1 Adequacy of Root Cause a Penetration cracking and Reactor Pressure Technical Root Cause 02-0891 Vessel corrosion b Organizational, Programmatic and Human 100 Performance Issues Adequacy of Safety Significant Structures, 2

Systems and Components a Reactor Pressure Vessel Head Replacement 97 Containment Vessel Restoration following b 99 RPV Head Replacement Structures, Systems and Components Inside c 100 94 Containment c.1 Containment Emergency Sump 100 100 EOC of Boric Acid in Systems Outside of d 100 97 Containment Field Complete In Progress Hold - Plant Conditions N/A - Not Applicable 59 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance Item 0350 Checklist Item Description Discovery Implementation No.

3 Adequacy of Safety Significant Programs a Corrective Action Program 100 100 b Operating Experience Program 100 100 c.1 Quality Audits 100 100 c.2 Self-Assessments of Programs 100 d Boric Acid Corrosion Management Program 100 100 Reactor Coolant System Unidentified Leakage e 100 Monitoring Program f In-Service Inspection Program 100 100 g Modification Program 100 100 h Radiation Protection Program 100 97 Completeness & Accuracy of Required Records i 60

& Submittals to NRC Field Complete In Progress Hold - Plant Conditions N/A - Not Applicable 60 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance Item 0350 Checklist Item Description Discovery Implementation No.

Adequacy of Organizational Effectiveness 4 a-b 90

& Human Performance 5 Readiness for Restart a Review of Licensee's Restart Action Plan b Systems Readiness for Restart 100 91 b.1 Design Calculation Resolution 100 Included with 5 b c Operations Readiness for Restart Restart Readiness Reviews d Test Program Development and Implementation 72 6 a-f Licensing Issue Resolution 100 7 a Confirmatory Action Letter Resolution CAL Resolution & Restart Report Field Complete In Progress Hold - Plant Conditions N/A - Not Applicable 61 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance T OT AL REST ART CONDIT ION REPORT EVALUAT IONS A dd Close 7000 6000 Number of Restart CRs 5000 4000 Closed 3000 2000 1000 Open 0

1/ 5 1/ 12 1/ 19 1/ 2 6 2/ 2 2/ 9 2 / 16 2 / 2 3 3/ 2 3/ 9 3 / 16 3 / 2 3 3 / 3 0 4/ 6 4 / 13 4 / 2 0 4 / 2 7 5/ 4 5 / 11 5 / 18 5 / 2 5 6/ 1 6/ 8 6 / 15 6 / 2 2 6 / 2 9 To t a l Clo se d 3 10 3 3 2 0 4 3 4 0 6 3 5 5 8 3 6 8 1 3 8 3 3 3 9 8 9 4 17 3 4 4 5 2 4 6 9 2 4 8 3 0 4 9 9 8 5 117 5 2 3 4 5 3 13 5 3 7 7 5 4 6 0 5 5 4 2 5 6 0 8 5 6 7 3 5 7 3 3 5 7 8 8 To t a l Op e n 18 3 2 17 7 2 16 6 8 16 10 15 7 4 14 7 5 13 6 8 12 19 973 786 689 597 5 16 457 427 400 350 325 349 3 13 322 294 Clo se 82 10 1 202 15 2 12 3 15 2 15 6 18 4 279 240 13 8 16 8 119 117 79 64 83 82 66 65 60 55 Ad d 8 41 98 94 87 53 49 35 33 53 41 76 38 58 49 37 33 57 90 29 69 27 62 Davis-Besse ar Power Station June 3, 2003

Restart Action Performance TOTAL RESTART CORRECTIVE ACTIONS A dd Close 8000 7000 6000 Number of Restart CAs 5000 Closed 4000 3000 2000 1000 Open 0 1/ 5 1/ 12 1/ 19 1/ 26 2/ 2 2/ 9 2/ 16 2/ 23 3/ 2 3/ 9 3/ 16 3/ 23 3/ 30 4/ 6 4/ 13 4/ 20 4/ 27 5/ 4 5/ 11 5/ 18 5/ 25 6/ 1 6/ 8 6/ 15 6/ 22 6/ 29 Total Clos ed 1313 1457 1619 1817 2009 2262 2448 2701 3082 3401 3751 4097 4272 4497 4771 4879 5088 5394 5575 5677 5840 5957 Total Open 3049 3216 3384 3431 3389 3268 3191 3081 2823 2636 2381 2159 2051 1886 1675 1610 1442 1196 1075 1024 924 809 Clos e 97 144 162 198 192 253 186 253 381 319 350 346 175 225 274 108 209 306 181 102 163 117 Add 79 311 330 245 150 132 109 143 123 132 95 124 67 60 63 43 41 60 60 51 63 2 63 Davis-Besse ar Power Station June 3, 2003

Closing Comments Lew Myers Chief Operating Officer - FENOC 64 Davis-Besse ar Power Station June 3, 2003