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The Reactor Oversight The Reactor Oversight Process:Process:
Development and ResultsDevelopment and Results
Tom HoughtonTom Houghton
Nuclear Energy InstituteNuclear Energy Institute
September 20, 2005September 20, 2005
2
What is NEI?What is NEI? The Nuclear Energy Institute is the industry’s The Nuclear Energy Institute is the industry’s
policy organization, whose mission is to foster policy organization, whose mission is to foster the beneficial uses of nuclear technology in its the beneficial uses of nuclear technology in its myriad formsmyriad forms
NEI’s membership includes 250 corporate NEI’s membership includes 250 corporate members in 14 nationsmembers in 14 nations
NEI and its predecessor organizations have NEI and its predecessor organizations have served the nuclear industry since 1953served the nuclear industry since 1953
NEI’s key organizations areNEI’s key organizations are Governmental AffairsGovernmental Affairs CommunicationsCommunications Nuclear GenerationNuclear Generation
3
NEI 2006 Business PlanNEI 2006 Business PlanCORE ESSENTIAL
ACTIVITY
Enhancing the Business
Environment for Operating Plants
CORE ESSENTIAL ACTIVITY
Creating the Business
Environment for New Plants
Managing Used Nuclear
Fuel
Advancing a National
Energy Policy
Sustaining the Nuclear
Infrastructure
Branding, Building
Public Support
Enhancing The Regulatory Environment
Security
Emergency Planning
Materials
Risk-Informed Regulation
New Plant Regs.
NRC Effectiveness
New Plant Incentives
Price-Anderson Renewal
Appropriations for R&D, Nuclear Power 2010
Environmental Policy
Fuel Supply
Workforce
Manufacturing Base
Financial Community Outreach
Adequate Funding
Funding Reform
Licensing
EPA Standard
Nevada
Project Support
Advertising
Media Relations
State Govt., Labor Outreach
Environmental Programs
5 ESSENTIAL ACTIVITIES
4
In April 2000 NRC implemented the In April 2000 NRC implemented the new Reactor Oversight Processnew Reactor Oversight Process
The new process revised, and for the first time, The new process revised, and for the first time, integrated NRC’s inspection, assessment and integrated NRC’s inspection, assessment and enforcement programsenforcement programs
This presentation will describeThis presentation will describe Reasons for the changeReasons for the change Results to dateResults to date
5
Industry Performance improved Industry Performance improved dramatically in the 1980sdramatically in the 1980s
SafetySafety Production (capacity factor)Production (capacity factor) Cost ($/kw)Cost ($/kw)
6
US Capacity Factor 1981-2001
0.0%
10.0%
20.0%
30.0%
40.0%
50.0%
60.0%
70.0%
80.0%
90.0%
100.0%
1981 1986 1991 1996 2001
Top Quartile
Median
Bottom Quartile
Std Dev
U.S. Capacity Factor 1981-2001U.S. Capacity Factor 1981-2001
7
US Electricity Production Cost US Electricity Production Cost Estimates Estimates (1981-2000)(1981-2000)
(in constant 2000 cents/kWh)(in constant 2000 cents/kWh)
0
1
2
3
4
5
6
7
8
9
10
11
81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00
Nuclear1.76
Coal 1.79
Gas 5.69
Source: Pre 1995: UDI, Post 1995: RDI Modeled Production Cost
8
US Production Cost ($ per Installed KW -- Constant yr 2000 $)
0
50
100
150
200
250
1988 1990 1992 1994 1996 1998 2000
Bottom Quartile
Median
Top Quartile
Std Deviation
U.S. Production Costs 1988-2000U.S. Production Costs 1988-2000
9
Automatic Scrams Per Unit
012345678
1980 1985 1990 1995 2000
Scra
ms
per
year
Industry’s safety performance, as measured by Industry’s safety performance, as measured by NRC and WANO indicators, continued to improveNRC and WANO indicators, continued to improve
10
Significant Events: Industry Average Significant Events: Industry Average (1985-2000)(1985-2000)
2.37
1.61
0.81 0.86 0.8
0.440.27 0.29 0.25 0.2
0.12 0.09 0.07 0.04 0.03 0.030
0.5
1
1.5
2
2.5
85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 2000
Source: NUS
11
Safety System PerformanceSafety System Performance
70
8492 91 94 94 94 98 95 96 94
0
20
40
60
80
100
89 91 93 94 95 96 97 98 99 2000 2001
% o
f sy
stem
s ac
hie
vin
g 20
05 g
oals
Source: WANO 2001 Performance Indicators
12
Collective Radiation Exposure - BWRs
859988
846
475
403446
368 363
265
184
0
100
200
300
400
500
600
700
800
900
1000
Ma
n-R
em
pe
r U
nit
1980 1982 1984 1986 1988 1990 1992 1994 1996 1997
13
US Manufacturing IASR US Finance, Insurance, Real Estate IASR US Nuclear IASR*
Industrial Accident Safety Rate
3.954.004.204.204.30
4.704.70
1.10 0.900.620.80 0.80
0.60 0.70
0.260.77 0.64 0.46 0.45 0.29 0.340.00
1.00
2.00
3.00
4.00
5.00
1992 1994 1996 1997 1998 1999 2000
Indu
stri
al A
ccid
ent Sa
fety
Rat
e (IA
SR):
Acc
iden
ts# P
er 2
00,0
00 W
orke
r H
ours
#Number of accidents resulting in lost work, restricted work, or fatalities per 200,000 worker hours *Full- time, on- site employees
Sources: WANO and BLS
Despite objective evidence of improving safety, NRC Violations continued to
increase
Total Industry Violations
793 801
904 925
989
620
1,001
1,519
-
200
400
600
800
1,000
1,200
1,400
1,600
1990 1991 1992 1993 1994 1995 1996 1997
Increase was driven by a 100% jump in Level IV Violations (minor process and procedure
errors)
Industry Violations - Severity Level 4
710 715
795820
927
567
905
1427
0
200
400
600
800
1000
1200
1400
1990 1991 1992 1993 1994 1995 1996 1997
4
The consequences of the old approach were significant, both economically…
Civil Penalties
0
10
20
30
40
50
1990 1991 1992 1993 1994 1995 1996 1997
# of Violations
$0$1,000,000$2,000,000$3,000,000$4,000,000$5,000,000$6,000,000$7,000,000$8,000,000
Civil Penalty Amount
Number Civil Penalty Amount $
…AND in diverting NRC and industry resources from focusing on more risk significant areas
17
NRC agreed a new approach was appropriate
NRC’s internal reviews found the previous NRC’s internal reviews found the previous approach inefficient, untimely, very subjective approach inefficient, untimely, very subjective and inscrutable to licensees and the publicand inscrutable to licensees and the public
Advances in risk assessment provided Advances in risk assessment provided confidence that risk-informed performance confidence that risk-informed performance indicators and simplified risk analyses could indicators and simplified risk analyses could be used as effective assessment toolsbe used as effective assessment tools
18
RADIATIONSAFETY
PUBLIC HEALTH AND SAFETY ASA RESULT OF CIVILIAN NUCLEAR
REACTOR OPERATION
REACTOR SAFETY
SAFEGUARDS
INITIATINGEVENTS
MITIGATING SYSTEMS
BARRIERINTEGRITY
EMERGENCYPREPAREDNESS
PUBLIC OCCUPATIONALPHYSICAL
PROTECTION
Cornerstones
HUMANPERFORMANCE
SAFETY CONSCIOUS WORK ENVIRONMENT
PROBLEMIDENTIFICATION
ANDRESOLUTION
Cross-Cutting Areas
NRCs OverallSafety Mission
Strategic Performance
Areas
Cornerstone Chart
19
DevelopInspection
Plan
AssessResults
DetermineRegulatory
Action
ConductInspections
Regulatory Oversight ModelLicensee ProvidesSelf Assessments& Audit Results*
Licensee ProvidesSafety PerformanceIndicators
Licensee Assesses& CorrectsDeficiencies
Licensee ProvidesSelf Assessment &Audit Plans*
Regulatory Oversight ProcessRisk-Informed, Performance-Based Assessment,
Inspection and Enforcement
* Future
20
What are appropriate roles for Licensees and Regulators?
Performance Model for Successful Plant Operations
Inputs Management Actions Outputs
People
Plant
Processes
Procedures
Safety Performance
Cost Effective
Production
Human Performance
Self Assessment
Corrective Action
21
Reactor Oversight Process
Enforcement
Public Meetings
•Press Releases•NRC WebSite•PDR/ADAMS
Assessment ReportsInspection Plans
Inspection FindingsPerformance Indicators
Communications
Assessment Process
(Action Matrix)
Agency Response
Management ConferenceMonitor Licensee Actions
NRC InspectionsAdditional Regulatory Actions
Event Response(SI/AIT/IIT)
Performance IndicatorsRisk Informed
Baseline InspectionsGeneric Safety
InspectionsSupplemental
Inspections
Significance Determination Process Performance Indicator Thresholds
Performance IndicatorsInspections
Significance Evaluations Significance Evaluations
Cornerstones of Safety
22
Performance BandsSAMPLE INDICATOR
Licensee Response
Increased Regulator Response
Required Regulator Response
Unacceptable Performance
23
ACTION MATRIXR
ES
ULT
S
INCREASING SAFETY SIGNIFICANCE
All AssessmentInputs (PIs andInspection Areas)Green; Cornerstone objectives fully met
One or Two inputs White (in different cornerstones) in a Strategic Performance Area; Cornerstone objectives fully met
One DegradedCornerstone (2 W or 1 Y input) or any 3 W inputs in strategic performance area; Cornerstones met-minimal reduction in safety margin
Repetitive/multipledegraded cornerstones, Multiple Y or 1R input; Cornerstone met-longstanding issues or signif safety margin reduction
Overall Unacceptable Performance; Operation not permitted. Unacceptable safety margin.
RE
SP
ON
SE
Routine ResidentInspector Interaction
SRI/BC Meet with Licensee
DD/RA Meet withLicensee Management
EDO (or Commission) Meet with SeniorLicense Management
Management Meeting
Commission Meeting with Senior LicenseeManagement
Licensee Action
Licensee Corrective Action Licensee Corrective Action with NRCOversight
Licensee SelfAssessment with NRCOversight
Licensee Performance Improvement Plan withNRC Oversight
NRCInspection
Risk-Informed BaselineInspection Program
Inspection Followup Baseline and Inspection Focused on Cause of Degradation
Baseline and Team Insp. Focused on Cause of Overall Degradation
RegulatoryActions
None -Document Response to Degrading Area in Inspection Report
Docket Response toDegrading Condition
-10 CFR 2.204 DFI-10 CFR 50.54(f) Letter-CAL/Order
Order to Modify, Suspend or RevokeLicensed Activities
AssessmentReport
DD review/signAssessment Report(w/ inspection plan)
DD review/signAssessment Report(w/ inspection plan)
RA review/signAssessment Report(w/ inspection plan)
RA review/signAssessment Report(w/ inspection plan)
CO
MM
UN
ICA
TIO
N
PublicAssessment Meeting
SRI or Branch ChiefMeet with Licensee
SRI or Branch ChiefMeet with Licensee
RA Discuss Performancewith Licensee
EDO (or Commission) Discuss Performance with Senior Licensee Management
Commission Meetingwith Senior LicenseeManagement
Regional Review Only Headquarters Review
0%
10%
20%
30%
40%
50%
1Q
99
2Q
99
3Q
99
4Q
99
1Q
00
2Q
00
3Q
00
4Q
00
1Q
01
2Q
01
3Q
01
4Q
01
1Q
02
2Q
02
3Q
02
Unplanned Power Changes per 7000 Critical Hours
Pe
rce
nt
of
Gre
en
-Wh
ite
Th
res
ho
ld
Unit Average
0%
10%
20%
30%
40%
50%
1Q99 2Q99 3Q99 4Q99 1Q00 2Q00 3Q00 4Q00 1Q01 2Q01 3Q01 4Q01 1Q02 2Q02 3Q02
Safety System Functional FailuresP
erc
en
t o
f G
ree
n-W
hit
e T
hre
sh
old
PWR Average BWR Average
0%
20%
40%
60%
80%
100%
1Q99 2Q99 3Q99 4Q99 1Q00 2Q00 3Q00 4Q00 1Q01 2Q01 3Q01 4Q01 1Q02 2Q02 3Q02
ERO Drill Participation
Pe
rce
nt
of
Gre
en
-Wh
ite
Th
res
ho
ld
Average ERO Drill Participation
0%
10%
20%
30%
40%
50%
1Q99 2Q99 3Q99 4Q99 1Q00 2Q00 3Q00 4Q00 1Q01 2Q01 3Q01 4Q01 1Q02 2Q02 3Q02
Occupational Exposure Control Effectiveness
Pe
rce
nt
of
Gre
en
-Wh
ite
Th
res
ho
ld
Site Average Occupational Exposure Control Effectiveness
0%
20%
40%
60%
1Q99 2Q99 3Q99 4Q99 1Q00 2Q00 3Q00 4Q00 1Q01 2Q01 3Q01 4Q01 1Q02 2Q02 3Q02
Protected Area Security Equipment Performance Index
Pe
rce
nt
of
Gre
en
-Wh
ite
Th
res
ho
ld
Site Average
29
Performance Indicator TrendPerformance Indicator Trend
New PIs > Green by Quarter
0
5
10
15
20
25
1Q002Q
003Q
004Q
001Q
012Q
013Q
014Q
011Q
022Q
023Q
024Q
021Q
032Q
033Q
034Q
031Q
042Q
043Q
044Q
041Q
05
SEC
PRAD
ORAD
EP
BA
MS
IE
30
Greater than GreenPerformance Indicators
Greater than Green PIsTotal = 91 (ROP Inception through 1Q05)
0
5
10
15
20
25
IE1 IE2 IE3 MS1 MS2 MS3 MS4 MS5 BA1 BA2 EP1 EP2 EP3 OR1 PR1 PP1 PP2 PP3
Yellow
White
31
Inspection Finding Trend
New Findings > Green by Quarter
0
5
10
15
20
Find
ings
SEC
PRAD
ORAD
EP
BAR
MS
IE
32
Greater than GreenGreater than GreenInspection FindingsInspection Findings
Greater than Green Findings by CornerstoneTotal = 133 (ROP inception through 1Q05)
0
1020
3040
50
6070
80
IE MS BAR EP ORAD PRAD SEC
Red
Yellow
White
33
Inspection FindingsInspection FindingsFY 2002 - 2004FY 2002 - 2004
20022002 20032003 20042004
GreenGreen 696696 716716 881881
White White 2626 1414 1212
YellowYellow 22 22 00
RedRed 33 11 00
TOTALTOTAL 727727 733733 893893
34
““Greater than Green” TrendGreater than Green” Trend
New FINs and PIs > Green
010203040506070
2000 2001 2002 2003 2004
New PI > G New FIN > G
35
Crosscutting IssuesCrosscutting Issues
Number of Crosscutting Issues
50 59 67
177
392
050
100150200250300350400450
2000 2001 2002 2003 2004
36
Industry ActionsIndustry Actions
Developing crosscutting criteriaDeveloping crosscutting criteria Performance indicatorsPerformance indicators
MSPIMSPI Replacement for Scrams w/ loss of normal heat Replacement for Scrams w/ loss of normal heat
removal PIremoval PI Alternate RCS leakage PIAlternate RCS leakage PI
Significance Determination Process (SDP) Significance Determination Process (SDP) improvementsimprovements
37
ROP continues to evolve Availability of data has enhanced public confidenceAvailability of data has enhanced public confidence Continue to modify performance indicators and Continue to modify performance indicators and
significance determination process for inspectionssignificance determination process for inspections Focuses industry ®ulator on risk significant issuesFocuses industry ®ulator on risk significant issues Degrading performance can be identified before Degrading performance can be identified before
serious increase in risk to publicserious increase in risk to public Has resulted in performance improvements by Has resulted in performance improvements by
focusing on problem areas focusing on problem areas Has demonstrated need to reassess deterministic Has demonstrated need to reassess deterministic
regulationsregulations HOWEVER, ROP is not a substitute for vigilance, HOWEVER, ROP is not a substitute for vigilance,
and a willingness to aggressively pursue off normal and a willingness to aggressively pursue off normal conditionsconditions