diablo canyon npp risk-informed in-service inspection
DESCRIPTION
Purpose of In-service Inspection IAEA Workshop Purpose of In-service Inspection To identify conditions, such as flaw indications, that are precursors to leaks and rupture, which violate pressure boundary integrity principles. The lecturer can substitute this presentation by other example more appropriate to the country experience IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision MakingTRANSCRIPT
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
Diablo Canyon NPPDiablo Canyon NPPRisk-Informed In-service InspectionRisk-Informed In-service Inspection
Workshop InformationWorkshop InformationIAEA WorkshopIAEA Workshop City , Country
XX - XX Month, Year
LecturerLesson IV 3_11.3
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
2
Purpose of In-service InspectionPurpose of In-service Inspection
To identify conditions, such as flaw indications, that are To identify conditions, such as flaw indications, that are precursors to leaks and rupture, which violate pressure precursors to leaks and rupture, which violate pressure boundary integrity principles.boundary integrity principles.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
3
RI-ISI benefitsRI-ISI benefits
Enhance or maintained plant safety (CDF/LERF) Enhanced component reliability for high safety significance
components (HSSCs) Reduce nondestructive exams (NDE) Reduced man-rem exposure Other unquantifiable benefits
Reduced costs of engineering analysis (flaw evaluations, etc.) Reduced outage time Reduced chance of complicating plant operations
(scaffolding, leakage, etc.)
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
4
ASME Section XI Enhanced by Risk-ASME Section XI Enhanced by Risk-Informed ISIInformed ISI
Calculating pipe failure Calculating pipe failure prob. by considering prob. by considering design, experience and design, experience and operationsoperations
High design stress and High design stress and fatigue locations fatigue locations augmented by random augmented by random selectionselection
Failure ProbabilityFailure Probability
Exercising of PSA Exercising of PSA Model (CDF, LERF, Model (CDF, LERF, others)others)
Class 1, 2, and 3Class 1, 2, and 3ConsequenceConsequence
Risk-Informed ISIRisk-Informed ISIASME Section XI ASME Section XI ProcessProcess
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
5
Overall Risk-Informed ISI ProcessOverall Risk-Informed ISI Process
Scope and Segment Definition
ConsequenceEvaluation
Structural ElementFailure ProbabilityAssessment
ImplementProgram
Expert PanelCategorization
Element/NDESelection
Risk-Evaluation
Feedback
Loop
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
6
Segment DefinitionSegment Definition
Full Scope Definition All Class 1, 2, and 3 piping systems in ASME Section XI Piping fluid systems modeled in PSA Various balance of plant (non-nuclear code class) fluid systems
of importance Systems included under scope of Maintenance Rule determined
to be risk-significant Systems included in program are reviewed by expert panel for
concurrence
Partial Scope Definition Subset of piping classes such as ASME Class 1 piping only
(includes piping exempt from current requirements)
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
7
Segment DefinitionSegment Definition Segment defined based on:
Piping which have same consequence (loss of train A of RHR, loss of RWST, inside or outside containment consequences)
Where flow splits or joins (traditional PSA modeling points) Includes piping to a point in which a pipe failure could be
isolated (e.g., check valve, MOV, AOV, no credit for manual valves)
Pipe size changes Failure probability expected to be markedly different due to
material properties
Iterative process with Consequence Evaluation
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
8
Segment DefinitionSegment Definition
Subdivided system into piping segments
Assigned numerical identifier Based upon similar consequence Marked P&Ids & field isometrics
Determined failure modes effects analysis (FMEA)
Without operator action With operator action
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
9
Consequence EvaluationConsequence Evaluation
Both direct and indirect (spatial) effects are considered PSA is used to quantify impact
Consistent with EPRI PSA Applications Guide Calculations for CDF and LERF Conditional probability/frequency given piping failure
Considers multiple impacts Initiating event impact Single/multiple component/train/system impacts Combinations of impacts
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
10
Direct Effects EvaluationDirect Effects Evaluation
Failure effect based on disabling segment function leak PRA and system information used to determine if piping
failure causes:
An initiating event (e.g. LOCA, Reactor Trip) Loss of train or system Loss of multiple trains or systems Combination of the above
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
11
Overview Of Indirect Effects EvaluationOverview Of Indirect Effects Evaluation
Purpose of Evaluation
• To review any issues in identifying potential indirect effects/consequences from piping failures
• Identify indirect effects that would differentiate piping segments from each other
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
12
Indirect EffectsIndirect Effects
Considerations
• Flooding, spraying, dripping – should be primarily addressed by the PSA internal flooding analyses for all plant areas
• Pipe Whip, jet impingement – concern is primarily for high-energy fluid system piping
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
13
Indirect Effects ProcessIndirect Effects Process
Prewalkdown• Review existing documents which examine the local effects of pipe
breaks for the systems in the risk-informed ISI program• Identify other systems/trains affected by a failure in each area• Identify plant areas for plant walkdown• Document evaluation• Develop walkdown sheets for key areas
Walkdown• Perform walkdown and document results, actions, issues
Post Walkdown• Evaluate results• Resolve actions
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
14
Failure Probability Assessment ProcessFailure Probability Assessment Process
Industry failure experience Identification of potential failure modes and causes Specific-plant information – layout, materials, operating
conditions and experience Use of tools or data to calculate failure probability Estimation of leak and break probabilities by engineering
team
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
15
Failure Probability Assessment ProcessFailure Probability Assessment Process
INDUSTRY EXPERIENCE
ENGINEERINGTEAM CALC. TOOL
PLANT INFORMATION(LAYOUT, MATERIALS,
OPERATING CONDITIONSPLANT OPERATING
EXPERIENCE)
IDENTIFICATION OFPOTENTIAL FAILUREMODES AND CAUSES
ESTIMATEDLEAK AND BREAK
PROBABILITIES
Engineering Team-ISI/NDE Engineering
-Materials Engineering
-Design Stress Engineering
(Engineering Mechanics)
-Plant System Engineer
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
16
RI-ISI Expert Panel ProcessRI-ISI Expert Panel Process
- IMPACT- RRW- RAW- INDIRECT EFFECTS
RISK EVALUATION
- MECHANISM- PROBABILITY- BASIS
PRESSURE BOUNDARYFAILURE PROBABILITY
-CONTAINMENT PERFORMANCE-EXTERNAL EVENTS-SHUTDOWN RISK-OTHER SCENARIOS-MAINTENANCE/OPERATION INSIGHTS-DESIGN BASIS/DEFENSE-IN-DEPTH-OTHER DETERMINISTIC INSIGHTS
OTHER CONSIDERATIONS
EXPERT PANEL
HIGH AND LOWSAFETY – SIGNIFICANT
PIPING SEGMENTS
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
17
Mapping of Surry Segments on Structural Mapping of Surry Segments on Structural Element Selection MatrixElement Selection Matrix
HIGH
FAILURE
IMPORTANCE
SEGMENT
LOW
FAILURE
IMPORTANCE
SEGMENT
OWNER
DEFINED
PROGRAM
3
(a) SUSCEPTIBLE
LOCATIONS (100%)
(b) INSPECTION
LOCATION
SELECTION PROCESS1
ONLY
SYSTEM PRESSURE
TEST & VISUAL
EXAMINATION
4
INSPECTION
LOCATION
SELECTION
PROCESS
2
LOW
SAFETY
SIGNIFICANT
SEGMENT
HIGH
SAFETY
SIGNIFICANT
SEGMENT
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
18
Presentation FormatPresentation Format
• Overview of RI-ISI approach• Detailed comparison
Scope and segment definition Consequence evaluation Failure probability assessment process Risk evaluation Selection of elements and NDE methods (expert
panel) Change in Risk calculations RI-ISI implementation (not addressed here)
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
19
EPRI-RI-ISI ProcessEPRI-RI-ISI Process
Determine Scope
Perform SegmentConsequence Analysis
Perform Segment DamageMechanism Analysis
Perform Service Review
Finalize Program
Perform Risk Impact Assessment
Select Elements for Inspection andElement Inspection Methods
Determine Segment Risk Category
AdjustElementSelection Performance
Monitoring
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
20
Segment DefinitionSegment Definition
Segment definition guidelines (similar in both methodologies)
Piping which have same consequences Where flow splits or joins Pipe size changes Change in piping material Isolation capability
EPRI uses the above plus same failure mechanism criterion
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
21
Consequence EvaluationConsequence Evaluation Deterministic evaluation of piping failure-induced impact
(both methodologies)
Direct impact (e.g. loss of a train) Indirect impact (e.g. damage caused by flooding, jet
impingement) Multiple impacts (e.g. initiating events + Accident
mitigation) Probabilistic evaluation
EPRI uses a bounding worst case evaluation (using matrix or calculation)
WOG uses surrogate(s) to quantify condition CDF (CDP) and LERF (LERP) for spectrum of failure modes (leak, disabling leak, double ended break) utilizing internal events PSA model
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
22
Structural Reliability AssessmentStructural Reliability Assessment Both methodologies evaluate potential for pipe failure EPRI qualitatively classifies potential for pipe rupture
as “High”, “Medium”, or “Low” based on degradation mechanisms, in-service data, expert knowledge (no code).
WOG uses SRRA code (stays with the user) to quantify leak/rupture frequency/probability based on in-service data, potential failure mechanisms, and plant specific information (e.g. layout, materials, operating and conditions, etc.)
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
23
Risk EvaluationRisk Evaluation EPRI uses risk matrix to separately categorize piping
segments in the high, medium, or low classifications using prescriptive criteria for the consequence and rupture potential elements (risk is not calculated). It uses plant staff to review the results and concur with the risk ranking results
WOG methodology uses standard approaches for CDF/LERF calculation (ie. Frequency * CCDP) and risk ranking process (RAW and RRW). Additionally, expert panel discussions are held to review PSA results and include other potential risk contributors (e.g. shutdown risk, external events, etc.) WOG methodology allows credit for aumented
programs
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
24
Element SelectionElement Selection
Both methodologies inspect for cause EPRI methodology uses prescriptive rules (fixed
percentages) to determine the population of elements to be inspected
WOG methodology uses a combination of prescriptive and statistical rules to determine the population of elements to be inspected.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
25
WOG MatrixWOG Matrix
HIGH
FAILURE
IMPORTANCE
SEGMENT
LOW
FAILURE
IMPORTANCE
SEGMENT
OWNER
DEFINED
PROGRAM
3
(a) SUSCEPTIBLE
LOCATIONS (100%)
(b) INSPECTION
LOCATION
SELECTION PROCESS1
ONLY
SYSTEM PRESSURE
TEST & VISUAL
EXAMINATION
4
INSPECTION
LOCATION
SELECTION
PROCESS
2
LOW
SAFETY
SIGNIFICANT
SEGMENT
HIGH
SAFETY
SIGNIFICANT
SEGMENT
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
26
EPRI Risk MatrixEPRI Risk Matrix
MEDIUMMEDIUM(Cat. 4)(Cat. 4)LOWLOW
(Cat. 6)(Cat. 6)LOWLOW(Cat. 7) (Cat. 7)
LOWLOW(Cat. 7)(Cat. 7)LOWLOW
HIGHHIGH(Cat. 2)(Cat. 2)
MEDIUMMEDIUM(Cat. 5)(Cat. 5)
LOWLOW(Cat. 6)(Cat. 6)
LOWLOW(Cat. 7) (Cat. 7) MEDIUMMEDIUM
HIGHHIGH(Cat. 1)(Cat. 1)
HIGHHIGH(Cat. 3)(Cat. 3)
MEDIUMMEDIUM(Cat. 5)(Cat. 5)
LOWLOW(Cat. 7)(Cat. 7)HIGHHIGH
HIGHHIGHMEDIUMMEDIUMLOWLOWNONENONE
CONSEQUENCE CATEGORY CONSEQUENCE CATEGORY CCDP and CLERP PotentialCCDP and CLERP Potential
DE
GR
AD
AT
ION
CA
TE
GO
RY
Pipe
Rup
ture
Pot
entia
l
Failure Potential
Assessment
Consequence Assessment
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making
27
Change in Risk CalculationsChange in Risk Calculations EPRI methodology uses a progressively more
quantitative evaluation to assess the changes in Risk Qualitative Bounding Simplified Complex
WOG methodology calculates the change in Risk based on the change in pipe failure frequency (probability) due to the proposed change in the Inspection program. The calculations are consistent with those performed to calculate the Risk.