Harris Nuclear Plant - NRC - Region II Presentation - September … · 2012-11-18 · Strategy –...
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Harris Nuclear Plant Nuclear Regulatory Commission - Region II Presentation September 23, 2003
Transcript of Harris Nuclear Plant - NRC - Region II Presentation - September … · 2012-11-18 · Strategy –...
Harris Nuclear PlantNuclear Regulatory
Commission - Region II Presentation
September 23, 2003
Introductory Comments
Jim Scarola
Agenda
Plant Overview – Bob DuncanReliability Improvement Initiative – John DillsEquipment Related Improvements – Garry MillerPerformance/People and Risk-Related Improvements – Ed WillsSelf Evaluation Program – Terry MortonLooking Ahead
Harris Organization
J. Scarola Vice President
Harris Plant
R.J. Duncan, IIDirector
Site Operations
J.W. GurganiousManager
Nuclear Assurance
T.C. MortonManager
Support Services
(Vacant)Manager
Engineering
E.A. McCartneyManagerTraining
B.C. WaldrepGeneral Manager
Harris Plant
G.D. MillerManager
Maintenance
D.G. SimmonsSuperintendent
Radiation Control
E.L. Wills, Jr.Manager
Operations
J.F. BriggsSuperintendentEnv & Chemical
T.J. NataleManager
Outage & Scheduling
Harris Plant Overview
Bob Duncan
1999 Improvement Program“Above the Rim”Aggressive Goals EstablishedFocus:
Human PerformanceEquipment ReliabilitySelf Evaluation
Harris
Harris Plant Self-Evaluation
Program Components:Self-AssessmentCorrective ActionOperating ExperienceBenchmarking
Integrated Via Corrective Action ProgramFoundation For Continuous ImprovementLed by Line Organizations
Commitments RealizedImprove Nuclear SafetyIndustrial SafetyHuman Performance Plant Material ConditionZTEF ProgramALARAChemistrySecuritySpent Fuel ShippingOutage Planning/Execution
Commitments Realized
Operational FocusOSI/PIEmployee DevelopmentOperator PipelineDiversity
Risk Reduction Programs
Secondary Chemistry ImprovementsZero Tolerance For Equipment FailureFire ProtectionALARAEmergency PlanningReactor Head Inspection Self Evaluation
Foreign Material DiscoveryPlant Security
Harris Plant Security
NRC “Interim Compensatory Measures Order” (February 25, 2002)Facility ModificationsPlant Equipment UpgradeProcess/Procedure ChangesSecurity Staffing & TrainingPlant Access ControlsCoordination & Liaison With Federal, State & Local AgenciesOctober 21-25, 2002, Tabletop Drills
Fire Protection
Safe Shutdown Analysis ReconstitutionPlant Modifications in DevelopmentHarris Team Communicating With Region II InspectorsIn Touch With Industry Actions for Associated Circuits
Harris Nuclear PlantPerformance Summary
2Q03Reactor Safety
Radiation Safety Safeguards
Initiating Events
Mitigating Systems
Barrier Integrity
Emergency Preparedness
Occupational Radiation Safety
Public Radiation Safety
Physical Protection
Performance Indicators
Occupational Exposure Control
Effectiveness
RETS/ODCM Radiological
Effluents
Protected Area Equipment
Personnel Screening Program
FFD / Personnel Reliability Program
Drill / Exercise Performance
ERO Drill Participation
Alert and Notification
System
Reactor Coolant System Specific
Activity
Emergency AC Power System Unavailability
UnplannedScrams
Reactor Coolant System Leakage
High Pressure Injection System
Unavailability
Emergency System
Unavailability
Residual Heat Removal System
Unavailability
Safety System Functional
Failure
Scrams With Loss of Normal Heat Removal
Unplanned Power
Changes
Significant Inspection Findings
Air Monitors Inst. Calibration
No Findings this Quarter
Strategic Performance Areas
Cornerstones
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
Fire Protection 9 URIs
4Q/2002
No Findings this Quarter
3Q/2002
No Findings this Quarter
FFD – Failure to withhold access
No Findings this Quarter
No Findings this Quarter
1Q/2003
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
LTA 50.59
No Findings this Quarter
RWST L/T Flooding
No Findings this Quarter
No Findings this Quarter
No Findings this Quarter
2Q/2003Loss of CCWLTA Procedure
AFW Actuation
No Findings this Quarter
HNP NRC CommitmentsInspections With No Findings2002:
SSDIEPModifications/50.59Maintenance RuleOperator Training
2003:PI&RHeat SinkSecurity – ICM ImplementationOutage – RPOutage - ISIOutage – Vessel Head / Boric Acid ControlSimulator
Key Performance IndicatorsINPO Index
60
70
80
90
100
1997 1998 1999 2000 2001 2002 2003YTD
Inde
xIn
dex
99.099.0Top Quartile Threshold
82.5
93.7
89.3
78.3
89.1 96
.6
99.0
Key Performance IndicatorsRadiation Exposure (Person-Rem)
300
1997 1998 1999 2000 2001 2002 2003Aug YTD
133
16 101 77
149
0
50
100
150
200
250HNP Annualized HNP Annualized
ExposureExposurePer Fuel CyclePer Fuel Cycle
Top Quarter Threshold
(Fuel Cycle)
67.467.4Pers
onPe
rson
-- RemRem
252
18 Month Actual is Currently 46.1 Rem 18 Month Actual is Currently 46.1 Rem
62.4
Key Performance IndicatorsChemistry Index (Fuel Cycle)
Che
mis
try
Inde
xC
hem
istr
y In
dex
1.001.00
1.04
1.0
1.2
1.4
1.6
1997 1998 1999 2000 2001 2002 2003YTD
Top QuartileThreshold1.2
7 1.34
1.36
1.24
1.15
1.08
2003 YTD Actual is Currently 1.00 2003 YTD Actual is Currently 1.00
Key Performance Indicators Capability Factor (Fuel Cycle - 18 Mo. Avg.)
Top Quartile Threshold
83.3
92.3 93.3
81.5 80.6
93.789.2
60
70
80
90
100
1997 1998 1999 2000 2001 2002 2003Aug YTD
%%
93.393.392.6
Key Performance Indicators Refueling Duration (Days)
77.0 73.367.5
80.5
54.5
40.9
65
36.027.4
103.4
22.6
0
20
40
60
80
100
RFO1
RFO2
RFO3
RFO4
RFO5
RFO6
RFO7
RFO8
RFO9
RFO1
0RF
O11
Day
s
Key Performance Indicators Forced Outage Hours (Full & Partial)
Equi
vale
nt H
ours
Equi
vale
nt H
ours
Current HNP 3-Year Forced Loss Rate is 1.3%
486545
374398
7724
142193
200
367
468
324276
177 166
0
100
200
300
400
500
600
1995 1996 1997 1998 1999 2000 2001 2002
HNP HNP 3 Year Average3 Year Average
Top Quartile Threshold 3 Year Average
7979
2003Aug YTD
55133
81
HNP Improvement Plan Status
Trip Reduction Initiative
John Dills
Strategy – The Three “R’s” Reliability
PMsMonitoring
RedundancyEliminate Single-Point VulnerabilityECRs
ResiliencySurvive Ability
HNP Improvement Plan StatusTrip Reduction Initiative
Equipment Related Improvements
Garry Miller
ZTEF Zero Tolerance for Equipment FailuresCulture of Intolerance for Unplanned Equipment FailuresFocused on Critical Components3-Phase Implementation
Instill ZTEF Culture and VisionIdentify Critical ComponentsDevelop Integrated Management Strategy
ZTEF Phase 3 Current Status
Pilot on 5 Systems CompletedMaint and failure historyOE, EPIX, EPRI PM Basis Documents
Lesson Learned to Remaining SystemsPhase 3 Complete by End of 2004
0
20
40
60
80
100
120
140
2001 2002 2003
Unplanned LCOs
ZTEF Unplanned Action Statement Entries
YTD as of 8/30/03
0
50
100
150
200
250
2001 2002 2003
On-Line Backlog
ZTEFOn-Line Corrective Maintenance Backlog
Actual as of 8/30/03
R-11 Outage - 1A Bus Repairs
UAT feed to 1A Non-safety BusBus Bar Insulation Deficiencies Identified during Planned InspectionsRepair Options InvestigatedPermanent Repair Completed
R-11 Outage - 1A Bus Repairs
RFO-11 - ECCS Vent Modification
SOER 97-01PM established for NDERouted CSIP Recirculation Flow to VCT topInstalled 14 additional vents in 9 locations
RFO-11 - ECCS Vent Modification
RFO-11 – ESW Inspections
2700’ of Large Bore Piping Inspected and Cleaned
No Significant findings~100’ Small Bore Piping ReplacedHeat Exchangers in Good Overall Condition
Fouling Significantly Less than RFO-10Few Tubes Required Plugging
RFO-11 – Reactor Head InspectionsSpare Reactor Vessel Head Used for Mock-up TestingComprehensive Inspection
Established Acceptance CriteriaNo Evidence of LeakageVideo Record
RFO-11 – Reactor Head Inspections
RFO-11 – Bottom Vessel InspectionProactive Response To STP Finding
2 Weeks After STP100% Bare Metal Visual Exam (VT-2)Video Record
Used Same Acceptance Criteria As Developed For RPV Head Exam
RFO-11 – Bottom Vessel InspectionNo Evidence Of Leakage From Bottom Mounted Instrumentation (BMI) NozzlesSome Streaking From Removable Cavity Seal Ring Leaks (Replaced In 1994):
Thin, Transparent Film; No MaskingMet Acceptance CriteriaLocal Cleaning Performed To Aid In Evaluation
RFO-11 – Bottom Vessel Inspection
RFO-11 – CETNA Modification
RFO-10 Experience CETNA Design – Old versus New
Why Modify…Advantages of New CETNA Design
RFO-11 – CETNA Modification
Control Rod Drives
Vessel Head
Insulation Thermocouple Nozzles
Operations
Ed Wills
Operations Performance
RFO-11Trips Post-RFO-11Forced Downpowers
Risk Improvements
Raised 1CC-294 SetpointDEH Changes
FirmwareProcedure Changes
Surge Protection A Condensate Pump MotorMinimize ESW Operation (GL 89-13)Procedure Changes to Support AFW Outage
Operator Career Path
Operations PipelineTen NLO New HiresEleven Operators Currently in ClassNext License Class
Overtime ChallengeMoving to Other Organizations
EngineeringNuclear AssessmentTraining
Self Evaluation
Terry Morton
Overview
Self Evaluation Continuous ImprovementExamples of Results
CAPSelf AssessmentOperating ExperienceBenchmarking
Continuous Improvement
Condensate Pump Root Cause Investigation
1999 FailureAugust 17, 2003 FailureAugust 27, 2003 Failure96 Possible Failure Modes Analyzed
CAP Results
CAP Results
ActionsRefurbishment & TestingModification to Prevent Surge Damage on “A” Bus
Surge Suppression and Lightning Arrestor
Surge Suppression and Lightning Arrestor
CAP Results
Component Cooling Water Event Root Cause
18 Failure Modes AnalyzedRelief Valve Set Point too Close to System Transient PressureReseat Error Caused by Incorrect Settings
Counting notches
Relief Valve Secured for
Testing
CAP Results
ActionsRevised Set Point Revised Maintenance Procedure – In Shop SettingsImplemented Concurrent Verification of SettingsRetrain TechniciansShared OE with the Industry
Operating Experience Results
Reactor Vessel Head InspectionsSouth Texas Project Bottom Mounted Instrument LeaksAction Prior to SEN 238Proactive 100% Bare Metal InspectionBaseline for Future InspectionsNo Evidence of Leakage
Operating Experience Results
Davis-Besse EventMajor contributor to this event was a shift in the focus at all levels of the organization from implementing high standards to justifying minimum standards. Senior Management InvolvementConducted an Independent Fleet Evaluation
Self Assessment ResultsDavis-Besse Self Assessment
Focused Assessment to Determine Degree of Respect for Nuclear Safety Emphasis on LeadershipFive Key Attributes
Self Assessment Results
HNP has Healthy Respect for Nuclear SafetyAll Five Attributes Satisfactorily MetActions
Improve Lower Threshold Problem ReportingEnhance Approval and Funding Process for Equipment Repairs
Self Assessment ResultsElectrical Safety
Fleet Round Robin Self AssessmentStrengths
Zero Energy Checks Prior to Work StartPre-job Briefs with Non-Station Personnel
ActionsImprove Use of pre-job Inspection ChecklistAcquire Additional Insulated Tools for OperationsImproved Verification During Electrical Tag Outs
Benchmarking Results
Rigging ProgramBenchmarked Program to Industry StandardsProgram In Compliance with RegulationsFocus Included
Inspections and RecordsSafety RecordTraining and QualificationProgram Ownership
ActionsDevelop Fleet Procedure
Benchmarking Results
Service Water ProgramIndustry Contact Through EPRI MeetingSuccesses and Opportunities Discussed with a Focus on Piping IssuesActionsImplement Improved Motor Oil Cooler Cleaning TechniquesUse of MIC Indices
Continuous Improvement
