ML021130021

EOC Meeting Slides - 04/18/02

ML021130021
Person / Time
Site:	LaSalle
Issue date:	04/18/2002
From:	NRC/RGN-III
To:
References
Download: ML021130021 (34)

Text

ANNUAL ASSESSMENT MEETING Nuclear Regulatory Commission

Agenda

! Introduction

! Review of Reactor Oversight Process

! Discussion of Plant Performance Results

! Licensee Response and Remarks

! NRC Closing Remarks

! Meeting with the Licensee adjourned

! NRC available to address questions from the public

Region III Organization Regional Specialists Director Division of Reactor Safety John (Jack) Grobe Resident Inspector George Wilson Senior Resident Inspector Eric Duncan Branch Chief Bruce Burgess Director Division of Reactor Projects Steven Reynolds Deputy Director Geoffrey E. Grant Regional Administrator Jim Dyer

Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/

index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm/adams.html Public Document Room 1-800-397-4209 (Toll Free)

NRC Activities

! Ensure nuclear plants are designed, constructed, and operated safely

! Issue licenses for the peaceful use of nuclear materials in the U.S.

! Ensure licensees use nuclear materials and operate plants safely, and are prepared to respond to emergencies

NRC Performance Goals

! Maintain safety and protect the environment

! Enhance public confidence

! Improve effectiveness, efficiency, and realism of processes and decision making

! Reduce unnecessary regulatory burden

NRC Oversight Activities

! Provides assurance plants are operating safely and in accordance with the regulations

! Risk informed process

! Objective indicators of performance

! Inspections focused on key safety areas

! Defines expected NRC and licensee actions

Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas

Strategic Performance Areas Safety Cornerstones

! Reactor Safety PInitiating Events PMitigating Systems PBarrier Integrity PEmergency Preparedness

! Radiation Safety POccupational Radiation Safety PPublic Radiation Safety

! Safeguards PPhysical protection

CROSS-CUTTING ISSUES

! PROBLEM IDENTIFICATION AND RESOLUTION

! HUMAN PERFORMANCE

! SAFETY CONSCIOUS WORK ENVIRONMENT

Baseline Inspections at all reactor sites to monitor plant safety performance in each of the Strategic Performance Areas Event Follow-up and Supplemental Inspections when required NRC Resident and Regional Inspectors Conduct Safety Inspections

Key Aspects of Baseline Inspection Program

! Conducted at all plants

! Objective evidence of safety in all cornerstones

! Emphasizes safety significant systems, components, activities, and events

! Monitors licensee effectiveness in finding and fixing safety issues

! Standardized inspection report format to describe significant findings and non-compliance

! Inspection reports are publicly accessible

Examples of Baseline Inspections

! Plant safety tours

! Plant control room tours

! Maintenance and alignment of equipment

! Operator response during simulated emergency conditions

! Plant security

! Controls for radiation releases

! Worker radiation protection

! Plant safety tours

! Plant control room tours

! Maintenance and alignment of equipment

! Operator response during simulated emergency conditions

! Plant security

! Controls for radiation releases

! Worker radiation protection

Examples of Baseline Inspections

! Equipment Alignment - ~ 70 hrs/yr

! Annual Fire Protection - ~ 35 hrs/yr

! Trienniel Fire Protection - ~200 hrs every 3 yrs

! Operator Response - ~ 125 hrs/yr

! Plant security - ~40 hours/yr

! Emergency preparedness - ~60 hrs/yr

! Rad release controls - ~100 hrs every 2 years

! Worker radiation protection - ~125 hrs/year

! Corrective action program - 10% every inspecton

! Corrective action program - ~200 hr every 2 yrs

Reactor Safety Emergency Preparedness Safeguards Radiation Safety Barrier Integrity Mitigating Systems Initiating Events Occupational Radiation Safety Public Radiation Safety Physical Protection Inspection Areas Inspection Procedures

! Adverse Weather

! Evaluation of Changes

! Equipment Alignment

! Fire Protection

! Flood Protection

! Heat Sink

! In Service Inspection

! Operator Requalification

! Maintenance Rule Imp

! Maintenance Risk Assessment

! Non-Routine Events

! Excercise Evaluation

! Alert and Notice

! ERO Augment

! EAL

! EP Preparation

! Drill Evaluation

! RAD Access

! ALARA Plan

! RAD monitoring

! RAD Effluents

! RAD Transport

! RAD Environmental

! Operability Evaluation

! Operator Workarounds

! Permanent Mods-Online

! Permanent Mods

! Post Maintenance Test

! Refueling Outage

! SSDI

! Surveillance Testing

! Temporary Modifications

! PI&R

! Event Follow-up

! PI Verification

! Sec Authorization Access

! Sec Search

! Sec Response

! Sec Plan change

Event Follow-up and Supplemental Inspections

! Review events for significance

! Follow-up significant inspection findings

! Determine causes of performance declines

! Provides for graduated response

Performance Indicators

! 18 Performance Indicators

! Covers all cornerstones

! Licensee submits data to NRC quarterly

! Baseline Inspection program verifies accuracy

! Available on Reactor Oversight Program Web site

Unplanned Power Change Reactor Safety Emergency Preparedness Safeguards Radiation Safety Barrier Integrity Mitigating Systems Initiating Events Occupational Radiation Safety Public Radiation Safety Physical Protection Performance Indicators Safety System Functional Failure Residual Heat Removal System Unavailability Heat Removal System Unavailability High Pressure Injection System Unavailability Emergency AC Power System Unavailability Unplanned Scrams RETS/ODCM Radiological Effluents Occupational Exposure Control Effectiveness Reactor Coolant System Specific Activity Reactor Coolant System Leakage Protected Area Equipment FFD/Personnel Reliability Program Personnel Screening Program Alert and Notification System ERO Drill Participation Scrams with Loss of Normal Heat Removal Drill/Exercise Performance Relationship of Strategic Performance Areas, Safety Cornerstones and Performance Indicators

Inspection Findings Green:

Very Low safety issue White:

Low to moderate safety issue Yellow: Substantial safety issue Red:

High safety issue Significance Threshold Performance Indicators Green:

Only baseline Inspection White:

May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight

Performance Indicator

Key Aspects of Assessment Program

! Objective assessment of performance

! Action Matrix to determine agency response to performance P Inspection level increases P Management involvement increases P Regulatory action increases

! Plant specific assessment letters

! Information on NRC public web site

Lic en s e e R e s p o ns e R e gu la tory R e s po n s e D e gra d ed C o rne rs ton e M u lt iple/ R ep e titive U na c c e p tab le C olu m n C o lu m n C o lum n D e gra d ed C o rn ers ton e P e rfo rm an c e C o lum n C olu m n R

E S

U L

T S

A ll A s s ess m en t Inp uts (P e rf o rm an c e In dic at o rs (P Is ) a n d Ins p ec tio n F ind in gs )

G reen ; C o rn ers ton e O b jec t iv e s F ully M et O ne or T w o W hite In p uts (in d iff eren t c orne rs tone s ) in a S tra teg ic P e rfo rm an c e A rea ; C orn ers to n e O bjec t iv es F ully M et O ne D e grad ed C o rne rs ton e (2 W hite Inp uts o r 1 Y e llow Inp ut) or a n y 3 W hit e Inp uts in a S tra t e gic P erfo rm a nc e A re a; C o rne rs ton e O bjec t iv e s M e t w it h M in im al R e duc t io n in S af ety M a rg in R epe tit iv e D e g ra d ed C orn e rs to ne, M u ltip le D egra de d C orn e rs to nes, M u ltip le Y ellow Inp u ts, o r 1 R ed Inp u t; C orne rs tone O b jec tives M e t w ith L o ngs ta nding Is s ues o r S ig nif ic a nt R e du c t io n in S afe ty M a rg in O ve ra ll Un a c c epta ble P e rfo rm an c e ; P la n ts No t P e rm itted to O perat e W ith in t his B a nd, U na c c ep tab le M a rg in to S a fe ty R

E S

P O

N S

E R e g ulato ry P e rform a nc e M ee tin g N on e B ranc h C hief (B C ) o r D iv is io n D irec t or (D D )

M e et w ith Lic e ns ee D D o r R e g io na l A dm in is tra to r (R A )

M e et w ith L ic en s e e R A (o r E D O ) M ee t w ith S en io r Lic e ns e e M a n a ge m e n t C om m is s ion m ee t ing w ith S e nior L ic ens e e M a na g em en t L ic e ns ee A c tio n L ic e ns ee C o rre c tive A c tio n Lic e n s e e roo t c au s e ev a lu a tio n a nd c orrec tive ac tio n w ith N R C O ve rs ig h t Lic e ns ee S e lf As s es s m ent w ith N R C O vers ig ht L ic e n s ee P erfo rm a nc e Im pro v e m e n t P lan w ith N R C O v ers igh t N R C In s p ec t ion R is k-In fo rm ed B as e lin e Ins p ec tio n P ro g ram B a s elin e a n d s up p lem e nta l ins p e c tio n p ro c e d ure 95 00 1 B as e lin e an d s u pp le m e n ta l ins p ec tio n p roc edu re 95 0 02 B as eline an d s upp lem en tal in s p e c tio n p ro c ed u re 9 5 003 R e g ulato ry A c tio ns N on e S u p plem en t al ins p e c tio n o nly S up ple m e nta l ins p ec tio n o n ly

-10 C F R 2.2 0 4 D F I

-10 C F R 5 0.5 4 (f) Le tte r

- C A L /O rde r O rd e r to M od ify,

S u s p en d, o r R e v ok e Lic e ns e d A c tivitie s C

O M

M U

N I

C A

T I

O N

A s s e ss m ent L e tte rs B C or D D re view /s ig n a s s e s sm en t rep o rt (w /

in s p ec tio n p la n)

D D re v ie w /s ign as s es sm en t rep ort (w / in s p ec tion pla n )

R A rev iew /s ig n as s ess m e nt re p ort (w / ins p ec tio n p la n)

R A re v ie w /s ign a s s e ss m ent rep o rt (w / in s p e c tio n p la n)

C om m iss io n In fo rm ed A n nua l P u blic M ee tin g S R I o r B C M e et w ith L ic e ns ee B C o r D D M ee t w it h Lic e n s e e R A (or d es ig n ee )

D is c uss P erf orm anc e w ith Lic e ns e e E D O (o r C o m m iss io n )

D is c u ss P e rf o rm an c e w ith S en io r L ic e ns e e M a n a ge m e n t C om m is s ion M ee t ing w ith S e nior L ic ens e e M a na g em en t IN C REASING SAFETY SIGN IFICA NC E ---------->

An Action Matrix is used to assess overall plant safety performance and specify thresholds for NRC Enforcement Actions

Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Degraded Cornerstone Unacceptable Performance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Action Matrix Concept

National Summary of Plant Performance -103 Plants End of Calendar Year 2001 Licensee Response 74 Regulatory Response 24 Degraded Cornerstone 4

Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0

Fourth Quarter Calendar Year 2001 Performance Indicator Results Green:

1834 White:

8 Yellow:

0 Red:

0 Total Inspection Findings (April 2001 - December 2001)

Green:

660 White:

23 Yellow:

2 Red:

0 National Summary

LASALLE 1 4th Qtr 2001 - Performance Summary

LASALLE 1 4th Qtr 2001 - Performance Summary

LASALLE 2 4th Qtr 2001 - Performance Summary

LASALLE 2 4th Qtr 2001 - Performance Summary

LASALLE INSPECTION RESULTS

! EIGHT GREEN FINDINGS:

2 INITIATING EVENTS CORNERSTONE

3 MITIGATING SYSTEMS CORNERSTONE

2 BARRIER INTEGRITY CORNERSTONE

1 SAFEGUARDS CORNERSTONE

! PERFORMANCE INDICATORS:

UNIT 1 - ALL GREEN

UNIT 2-WHITE PI - UNPLANNED SCRAMS/7000 HOURS

! INSPECTION HOURS: 3812

LASALLE INSPECTION RESULTS (CONTINUED)

! CROSS-CUTTING ISSUE

! ADVERSE TREND IN HUMAN PERFORMANCE:

3 REACTOR SCRAMS

MATERIAL IN SUPRESSION POOL

ISOLATION OF MONITOR

RHR SYSTEM INOPERABILITY

LASALLE INSPECTION RESULTS (CONTINUED)

MAJOR INSPECTION ACTIVITIES:

TWO SPECIAL INSPECTIONS

ONE SUPPLEMENTAL INSPECTION

TRIENNIAL FIRE PROTECTION PERFORMANCE INDICATORS:

SAFETY SYSTEM UNAVAILABILITY -RHR

LaSalle Annual Assessment (April 1 -Dec 31, 2001)

! Operated safely

! Met all cornerstone objectives - Unit 1

! Licensee Response Band of Action Matrix-Unit 1 P All inspection findings were of very low safety significance (Green)

P All Performance Indicators requiring no additional NRC oversight (Green)

! Regulatory Response Band of Action Matrix-Unit 2 P White Performance Indicator (Scrams)

P Supplemental inspection completed 8/01

! NRC plans to conduct baseline inspections

NRC Response To 9/11

! Activated NRC Response Centers

! Closely Coordinated Response With:

-- Our Licensees

-- FBI

-- Military, State, & Local Authorities

-- Law Enforcement

-- Intelligence Communities

! Issued Security Advisories

-- Increased Patrols

-- Augmented Security Capabilities

-- Added Barriers and Posts

-- More Limited Access

-- Enhanced Security Awareness

! Issued Order on Security

! NRC Monitored Enhanced Security