ML032730171

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NRC - Region II Presentation - September 23, 2003
ML032730171
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/23/2003
From: Scarola J
Progress Energy Co
To:
Office of Nuclear Reactor Regulation
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ML032730004 List:
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Download: ML032730171 (62)


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Harris Nuclear Plant Nuclear Regulatory Commission - Region II Presentation September 23, 2003

Introductory Comments Jim Scarola

Agenda O Plant Overview - Bob Duncan O Reliability Improvement Initiative - John Dills O Equipment Related Improvements - Garry Miller O Performance/People and Risk-Related Improvements - Ed Wills O Self Evaluation Program - Terry Morton O Looking Ahead

Harris Organization J. Scarola Vice President Harris Plant R.J. Duncan, II J.W. Gurganious T.C. Morton Director Manager Manager Site Operations Nuclear Assurance Support Services (Vacant) E.A. McCartney B.C. Waldrep Manager Manager General Manager Engineering Training Harris Plant G.D. Miller D.G. Simmons Manager Superintendent Maintenance Radiation Control E.L. Wills, Jr. J.F. Briggs Manager Superintendent Operations Env & Chemical T.J. Natale Manager Outage & Scheduling

Harris Plant Overview Bob Duncan

Harris O 1999 Improvement Program O Above the Rim O Aggressive Goals Established O Focus:

Z Human Performance Z Equipment Reliability Z Self Evaluation

Harris Plant Self-Evaluation O Program Components:

Z Self-Assessment Z Corrective Action Z Operating Experience Z Benchmarking O Integrated Via Corrective Action Program O Foundation For Continuous Improvement O Led by Line Organizations

Commitments Realized O Improve Nuclear Safety O Industrial Safety O Human Performance O Plant Material Condition O ZTEF Program O ALARA O Chemistry O Security O Spent Fuel Shipping O Outage Planning/Execution

Commitments Realized O Operational Focus O OSI/PI O Employee Development O Operator Pipeline O Diversity

Risk Reduction Programs O Secondary Chemistry Improvements O Zero Tolerance For Equipment Failure O Fire Protection O ALARA O Emergency Planning O Reactor Head Inspection O Self Evaluation Z Foreign Material Discovery O Plant Security

Harris Plant Security O NRC Interim Compensatory Measures Order (February 25, 2002)

O Facility Modifications O Plant Equipment Upgrade O Process/Procedure Changes O Security Staffing & Training O Plant Access Controls O Coordination & Liaison With Federal, State &

Local Agencies O October 21-25, 2002, Tabletop Drills

Fire Protection O Safe Shutdown Analysis Reconstitution O Plant Modifications in Development O Harris Team Communicating With Region II Inspectors O In Touch With Industry Actions for Associated Circuits

Harris Nuclear Plant Strategic Reactor Performance Summary Radiation Performance Safeguards Safety 2Q03 Safety Areas Initiating Mitigating Barrier Emergency Occupational Public Radiation Physical rstones Events Systems Integrity Preparedness Radiation Safety Safety Protection Performance Indicators Unplanned Emergency AC Reactor Coolant Drill / Exercise Occupational RETS/ODCM Protected Area Scrams Power System System Specific Performance Exposure Control Radiological Equipment Unavailability Activity Effectiveness Effluents Personnel Scrams With High Pressure Reactor Coolant ERO Drill Screening Loss of Normal Injection System System Participation Program Heat Removal Unavailability Leakage Alert and FFD / Personnel Unplanned Emergency Notification Reliability Power System System Program Changes Unavailability Residual Heat Removal System Unavailability Safety System Functional Failure Significant Inspection Findings LTA Procedure Loss of CCW No Findings this No Findings this No Findings this No Findings this FFD - Failure to 2003 AFW Actuation Quarter Quarter Quarter Quarter withhold access LTA 50.59 2003 No Findings this No Findings this No Findings this No Findings this No Findings this No Findings this No Findings this Quarter Quarter Quarter Quarter Quarter Quarter Quarter 2002 No Findings this Fire Protection No Findings this No Findings this No Findings this No Findings this No Findings this Quarter 9 URIs Quarter Quarter Quarter Quarter Quarter 2002 No Findings this RWST L/T No Findings this No Findings this No Findings this Air Monitors No Findings this Quarter Flooding Quarter Quarter Quarter Inst. Calibration Quarter

HNP NRC Commitments Inspections With No Findings 2002: 2003:

O SSDI O PI&R O EP O Heat Sink O Modifications/50.59 O Security - ICM O Maintenance Rule Implementation O Outage - RP O Operator Training O Outage - ISI O Outage - Vessel Head / Boric Acid Control O Simulator

Key Performance Indicators INPO Index Top Quartile Threshold 100 99.0 99.0

.0 99 90 Index 80 .6 .7

.3 .1 96 93 89 89

.5 70 .3 78 82 60 1997 1998 1999 2000 2001 2002 2003 YTD

Key Performance Indicators Radiation Exposure (Person-Rem) 300 250 Top Quarter HNP Annualized Person-Rem Threshold Exposure 200 (Fuel Cycle) Per Fuel Cycle 150 252 100 149 133 67.4 67.4 50 16 10 62 1 7 .4 0

1997 1998 1999 2000 2001 2002 2003 Aug YTD 18 Month Actual is Currently 46.1 Rem

Key Performance Indicators Chemistry Index (Fuel Cycle) 1.6 Chemistry Index

1. 1.

1.4 34 36 1.27 Top Quartile 1.24 Threshold 1.2 1.15 1.08 1.04 1.00 1.00 1.0 1997 1998 1999 2000 2001 2002 2003 YTD 2003 YTD Actual is Currently 1.00

Key Performance Indicators Capability Factor (Fuel Cycle - 18 Mo. Avg.)

Top Quartile Threshold 100 92.3 93.3 93.7 89.2 93.3 93.3 90 92.6 83.3 81.5 80.6

% 80 70 60 1997 1998 1999 2000 2001 2002 2003 Aug YTD

Key Performance Indicators Refueling Duration (Days) 103.4 100 80.5 80 77.0 73.3 67.5 65 60 54.5 Days 40.9 40 36.0 27.4 22.6 20 0

O1 O2 O3 O4 O5 O6 O7 O8 O9 O1 O1 RF RF RF RF RF RF RF RF RF 0 1 RF RF

Key Performance Indicators Forced Outage Hours (Full & Partial) 600 Top Quartile Threshold 545 3 Year Average Equivalent Hours 500 486 468 HNP 3 Year Average 367 398 400 374 324 276 300 200 177 166 193 200 142 100 77 133 79 79 55 24 81 0

1995 1996 1997 1998 1999 2000 2001 2002 2003 Aug YTD Current HNP 3-Year Forced Loss Rate is 1.3%

HNP Improvement Plan Status Trip Reduction Initiative John Dills

HNP Improvement Plan Status Trip Reduction Initiative Strategy - The Three Rs O Reliability Z PMs Z Monitoring O Redundancy Z Eliminate Single-Point Vulnerability Z ECRs O Resiliency Z Survive Ability

Equipment Related Improvements Garry Miller

ZTEF Zero Tolerance for Equipment Failures O Culture of Intolerance for Unplanned Equipment Failures O Focused on Critical Components O 3-Phase Implementation Z Instill ZTEF Culture and Vision Z Identify Critical Components Z Develop Integrated Management Strategy

ZTEF Phase 3 Current Status O Pilot on 5 Systems Completed Z Maint and failure history Z OE, EPIX, EPRI Z PM Basis Documents O Lesson Learned to Remaining Systems O Phase 3 Complete by End of 2004

ZTEF Unplanned Action Statement Entries 140 120 100 80 Unplanned LCOs 60 40 20 0

2001 2002 2003 YTD as of 8/30/03

ZTEF On-Line Corrective Maintenance Backlog 250 200 150 On-Line Backlog 100 50 0

2001 2002 2003 Actual as of 8/30/03

R-11 Outage - 1A Bus Repairs O UAT feed to 1A Non-safety Bus O Bus Bar Insulation Deficiencies Identified during Planned Inspections O Repair Options Investigated O Permanent Repair Completed

R-11 Outage - 1A Bus Repairs RFO ECCS Vent Modification O SOER 97-01 O PM established for NDE O Routed CSIP Recirculation Flow to VCT top O Installed 14 additional vents in 9 locations

RFO ECCS Vent Modification RFO ESW Inspections O 2700 of Large Bore Piping Inspected and Cleaned Z No Significant findings O ~100 Small Bore Piping Replaced O Heat Exchangers in Good Overall Condition Z Fouling Significantly Less than RFO-10 Z Few Tubes Required Plugging

RFO Reactor Head Inspections O Spare Reactor Vessel Head Used for Mock-up Testing O Comprehensive Inspection Z Established Acceptance Criteria O No Evidence of Leakage O Video Record

RFO Reactor Head Inspections RFO Bottom Vessel Inspection O Proactive Response To STP Finding Z 2 Weeks After STP Z 100% Bare Metal Visual Exam (VT-2)

Z Video Record O Used Same Acceptance Criteria As Developed For RPV Head Exam

RFO Bottom Vessel Inspection O No Evidence Of Leakage From Bottom Mounted Instrumentation (BMI) Nozzles O Some Streaking From Removable Cavity Seal Ring Leaks (Replaced In 1994):

Z Thin, Transparent Film; No Masking Z Met Acceptance Criteria Z Local Cleaning Performed To Aid In Evaluation

RFO Bottom Vessel Inspection RFO CETNA Modification O RFO-10 Experience O CETNA Design - Old versus New Z Why Modify O Advantages of New CETNA Design

RFO CETNA Modification Control Rod Drives Thermocouple Nozzles Insulation Vessel Head

Operations Ed Wills

Operations Performance O RFO-11 O Trips Post-RFO-11 O Forced Downpowers

Risk Improvements O Raised 1CC-294 Setpoint O DEH Changes Z Firmware Z Procedure Changes O Surge Protection A Condensate Pump Motor O Minimize ESW Operation (GL 89-13)

O Procedure Changes to Support AFW Outage

Operator Career Path O Operations Pipeline Z Ten NLO New Hires Z Eleven Operators Currently in Class Z Next License Class O Overtime Challenge O Moving to Other Organizations Z Engineering Z Nuclear Assessment Z Training

Self Evaluation Terry Morton

Overview O Self Evaluation Z Continuous Improvement Z Examples of Results X CAP X Self Assessment X Operating Experience X Benchmarking

Continuous Improvement CAP Results O Condensate Pump Root Cause Investigation Z 1999 Failure Z August 17, 2003 Failure Z August 27, 2003 Failure Z 96 Possible Failure Modes Analyzed

CAP Results O Actions Z Refurbishment & Testing Z Modification to Prevent Surge Damage on A Bus

Surge Suppression and Lightning Arrestor Surge Suppression and Lightning Arrestor CAP Results O Component Cooling Water Event Root Cause Z 18 Failure Modes Analyzed Z Relief Valve Set Point too Close to System Transient Pressure Z Reseat Error Caused by Incorrect Settings

Counting notches Relief Valve Secured for Testing

CAP Results O Actions Z Revised Set Point Z Revised Maintenance Procedure - In Shop Settings Z Implemented Concurrent Verification of Settings Z Retrain Technicians Z Shared OE with the Industry

Operating Experience Results O Reactor Vessel Head Inspections Z South Texas Project Bottom Mounted Instrument Leaks Z Action Prior to SEN 238 Z Proactive 100% Bare Metal Inspection Z Baseline for Future Inspections Z No Evidence of Leakage

Operating Experience Results O Davis-Besse Event Z Major contributor to this event was a shift in the focus at all levels of the organization from implementing high standards to justifying minimum standards.

Z Senior Management Involvement Z Conducted an Independent Fleet Evaluation

Self Assessment Results O Davis-Besse Self Assessment Z Focused Assessment to Determine Degree of Respect for Nuclear Safety Z Emphasis on Leadership Z Five Key Attributes

Self Assessment Results O HNP has Healthy Respect for Nuclear Safety O All Five Attributes Satisfactorily Met O Actions Z Improve Lower Threshold Problem Reporting Z Enhance Approval and Funding Process for Equipment Repairs

Self Assessment Results O Electrical Safety Z Fleet Round Robin Self Assessment Z Strengths X Zero Energy Checks Prior to Work Start X Pre-job Briefs with Non-Station Personnel Z Actions X Improve Use of pre-job Inspection Checklist X Acquire Additional Insulated Tools for Operations X Improved Verification During Electrical Tag Outs

Benchmarking Results O Rigging Program Z Benchmarked Program to Industry Standards Z Program In Compliance with Regulations Z Focus Included X Inspections and Records X Safety Record X Training and Qualification X Program Ownership Z Actions X Develop Fleet Procedure

Benchmarking Results O Service Water Program Z Industry Contact Through EPRI Meeting Z Successes and Opportunities Discussed with a Focus on Piping Issues Z Actions Z Implement Improved Motor Oil Cooler Cleaning Techniques Z Use of MIC Indices

Continuous Improvement