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1. IAEA.PNRA.05.05 Stetkar & Associates 1 EVENT SEQUENCE ANALYSIS by
John W. Stetkar
Presented to
National Training Course on Probabilistic Safety Assessment
Islamabad, Pakistan
May 2 - 6, 2005
IAEA Project C7-PAK/9/028-001
2. IAEA.PNRA.05.05 Stetkar & Associates 2 LEVEL 1 PSA EVENT SEQUENCE INITIATING EVENT
PLANT THERMAL / HYDRAULIC RESPONSE
FUNCTIONAL SUCCESS CRITERIA
MITIGATING SYSTEMS
OPERATOR ACTIONS
INDUCED / CONSEQUENTIAL IMPACTS
CORE DAMAGE END STATES / LEVEL 2 PSA INTERFACE
3. IAEA.PNRA.05.05 Stetkar & Associates 3 SUCCESS CRITERIA
4. IAEA.PNRA.05.05 Stetkar & Associates 4 CRITICAL SAFETY FUNCTIONS CORE REACTIVITY CONTROL
REACTOR COOLANT SYSTEM BOUNDARY INTEGRITY / COOLANT INVENTORY CONTROL
CORE DECAY HEAT REMOVAL
CONTAINMENT INTEGRITY
5. IAEA.PNRA.05.05 Stetkar & Associates 5 WHAT IS "CORE DAMAGE"? IMPORTANT TO CLEARLY DEFINE CORE DAMAGE FOR LEVEL 1 PSA
THERMAL / HYDRAULIC SUCCESS CRITERIA
SCENARIO TIMING
INTERFACE WITH LEVEL 2 PSA MODELS
TYPICAL LEVEL 1 PSA CORE DAMAGE CRITERIA
SUSTAINED CORE UNCOVERY (e.g., COOLANT LEVEL BELOW CORE MID-PLANE)
PEAK CLADDING TEMPERATURE > 1200 °C
6. IAEA.PNRA.05.05 Stetkar & Associates 6 WHAT IS "CORE DAMAGE"? ADDITIONAL REFINEMENTS IN LEVEL 2 PSA
LOCALIZED CLADDING OXIDATION > 17% DURING OR AFTER QUENCHING
CLADDING REACTION WITH WATER OR STEAM > 1% OF TOTAL ZIRCALLOY INVENTORY
LOSS OF COOLABLE CORE GEOMETRY
ONSET OF CORE MATERIAL RELOCATION
7. IAEA.PNRA.05.05 Stetkar & Associates 7 WHAT IS "CORE DAMAGE"? DIFFICULT TO DEFINE FOR CHANNEL-TYPE REACTORS (CANDU, RBMK, AGR, MAGNOX, ETC.)
SINGLE CHANNEL
MULTIPLE CHANNELS
SINGLE QUADRANT
HALF OF CORE
ENTIRE CORE
DIFFICULT TO DEFINE FOR SOME PLANT OPERATING STATES IN SHUTDOWN PSAs
"PARTIAL CORE DAMAGE" MAY BE IMPORTANT FOR SOME OFFSITE RELEASE CATEGORIES
8. IAEA.PNRA.05.05 Stetkar & Associates 8 SUCCESS CRITERIA DESIGN / FSAR / LICENSING CRITERIA TYPICALLY VERY CONSERVATIVE NOT APPROPRIATE FOR REALISTIC PSA
BEST-ESTIMATE PLANT-SPECIFIC THERMAL / HYDRAULIC ANALYSES
USUALLY NOT NECESSARY TO RUN DETAILED CODES FOR ALL SUCCESS CRITERIA (e.g., RETRAN, MAAP, ETC.)
"FIRST PRINCIPLES" MASS AND ENERGY BALANCE
MORE IMPORTANT TO EXAMINE RANGE OF SCENARIO-SPECIFIC CONDITIONS THAN TO CALCULATE PRECISE ANSWER FOR ONLY ONE CONDITION
9. IAEA.PNRA.05.05 Stetkar & Associates 9 EVENT TREES DISPLAY SEQUENCE PROGRESSION
DISPLAY SEQUENCE END STATES
DISPLAY SEQUENCE-SPECIFIC DEPENDENCIES
FUNCTIONAL (SUCCESS CRITERIA)
PHYSICAL (SYSTEMS)
HUMAN
IMPROVED UNDERSTANDING OF MODELS
ANALYSTS / USERS
PLANT PERSONNEL
REVIEWERS
10. IAEA.PNRA.05.05 Stetkar & Associates 10 EVENT TREE STYLES "SMALL EVENT TREE / LARGE FAULT TREE" MODEL
SIMPLE EVENT TREE LOGIC
EVENT TREES FOCUS ON BASIC SAFETY FUNCTIONS
COMPLEX FAULT TREE LOGIC
SOPHISTICATED FAULT TREE MODELS REQUIRED TO ACCOUNT FOR SCENARIO-SPECIFIC DEPENDENCIES
"LARGE EVENT TREE / SMALL FAULT TREE" MODEL
MORE COMPLEX EVENT TREE LOGIC
EVENT TREE CONTAINS FUNCTIONS, SYSTEMS, OPERATOR ACTIONS
SIMPLER FAULT TREE LOGIC
EVENT TREE BRANCHING CONDITIONS ACCOUNT FOR SCENARIO-SPECIFIC DEPENDENCIES
11. IAEA.PNRA.05.05 Stetkar & Associates 11 TANSTAAFL"THERE AIN'T NO SUCH THING AS A FREE LUNCH" SAME BOOLEAN LOGIC AND COMPLEXITY REQUIRED FOR REALISTIC MODEL OF ALL POTENTIAL SCENARIOS
EVENT TREE / FAULT TREE LOGIC FUNCTIONALLY EQUIVALENT - COMPARATIVE STUDIES CONFIRM SAME RESULTS
LARGELY A MATTER OF STYLE AND ANALYST COMFORT
OFTEN EASIER TO VISUALIZE COMPLEX SCENARIO-SPECIFIC CONDITIONS IN EVENT TREE FORMAT
BEST APPROACH IS USUALLY "MEDIUM EVENT TREE / MEDIUM FAULT TREE" MODEL
12. IAEA.PNRA.05.05 Stetkar & Associates 12 EVENT TREE DEVELOPMENT EVALUATE ALL REQUIRED MITIGATION FUNCTIONS
SPECIALIZED EVENT TREE LOGIC FOR EACH INITIATING EVENT GROUP
TOP EVENTS USUALLY ARRANGED IN APPROXIMATE TIME SEQUENCE OF NORMAL EVENT PROGRESSION
EXAMPLE
REACTOR TRIP
TURBINE TRIP
STEAM RELIEF
FEEDWATER SUPPLY
REACTOR COOLANT INVENTORY CONTROL
LONG-TERM CORE DECAY HEAT REMOVAL COOLING
13. IAEA.PNRA.05.05 Stetkar & Associates 13 EVENT TREE DEVELOPMENT(continued) DEFINE OPERATOR ACTIONS DURING EVENT MODEL DEVELOPMENT NOT A SEPARATE PSA TASK
ACCOUNT FOR SCENARIO-SPECIFIC SUCCESS CRITERIA AND TIMING
ACCOUNT FOR INDUCED / CONSEQUENTIAL FAILURES
EXAMPLES
INSUFFICIENT STEAM RELIEF ? LOSS OF SECONDARY HEAT REMOVAL
STEAM RELIEF FAILS TO RECLOSE ? OVERCOOLING
INSUFFICIENT PRIMARY PRESSURE RELIEF ? REACTOR COOLANT PIPING OR VESSEL FAILURE
PRIMARY RELIEF FAILS TO RECLOSE ? LOCA
14. IAEA.PNRA.05.05 Stetkar & Associates 14 INDUCED / CONSEQUENTIAL IMPACTS
15. IAEA.PNRA.05.05 Stetkar & Associates 15 TRANSIENT-INDUCED IMPACTS LOCAs
PRIMARY OVERPRESSURE
STUCK-OPEN RELIEF / SAFETY VALVES
REACTOR COOLANT PUMP SEAL FAILURE
MAKEUP / LETDOWN
OVERCOOLING
SECONDARY OVERPRESSURE
STUCK-OPEN RELIEF / SAFETY VALVES
ATWS
OPERATOR ACTIONS
16. IAEA.PNRA.05.05 Stetkar & Associates 16 TRANSIENT-INDUCED LOCAs ADD TO LOCA INITIATING EVENT FREQUENCY
LOSE ACTUAL INITIATING EVENT INFORMATION
LOSE DEPENDENCIES
SIMPLIFIED EVENT TREES
SIMPLIFIED SYSTEM MODELS
ADD SEPARATE EVENT TREE TOP EVENT
RETAIN DEPENDENCIES
EVENT TREES MORE COMPLEX
INTERFACE WITH SYSTEMS MORE COMPLEX
BETTER UNDERSTANDING OF MODELS / RESULTS
17. IAEA.PNRA.05.05 Stetkar & Associates 17 OVERCOOLING SCENARIOS PRESSURIZED THERMAL SHOCK (PTS)
MAY BE SIGNIFICANT PLANT-SPECIFIC PROBLEM
TYPICALLY MORE IMPORTANT FOR OLDER PLANTS
VESSEL WELD MATERIAL
DOCUMENTATION AND INSPECTIONS
AUTOMATIC SIGNALS
SECONDARY ISOLATION (STEAM AND/OR FEED)
SAFEGUARDS ACTUATION
AFFECT SEQUENCE PROGRESSION
AFFECT AVAILABLE SYSTEMS
18. IAEA.PNRA.05.05 Stetkar & Associates 18 ATWS SCENARIOS REACTOR SHUTDOWN SUCCESS CRITERIA
SIGNAL FAILURES (REACTOR PROTECTION SYSTEM)
MECHANICAL FAILURES (CONTROL RODS)
ALTERNATE SHUTDOWN OPTIONS
TIME WINDOW
SUCCESS CRITERIA
AVAILABLE SYSTEMS
OPERATOR ACTIONS
19. IAEA.PNRA.05.05 Stetkar & Associates 19 ATWS MODELS CORE NUCLEAR POWER
PRIMARY / SECONDARY ENERGY BALANCE
FEEDWATER SUCCESS CRITERIA
PRIMARY PRESSURE RESPONSE
ENERGY RELEASE INTO CONTAINMENT
20. IAEA.PNRA.05.05 Stetkar & Associates 20 OPERATOR ACTIONS
21. IAEA.PNRA.05.05 Stetkar & Associates 21 OPERATOR ACTIONSAFTER INITIATING EVENT ACTIONS REQUIRED BY EMERGENCY OPERATING PROCEDURES
USE OF ALTERNATE EQUIPMENT
REALIGNMENT OF SYSTEMS
MANUAL BACKUP TO AUTOMATIC SIGNALS
REPAIR / RECOVERY OF FAILED EQUIPMENT
NO FUNDAMENTAL DIFFERENCE BETWEEN "PROCEDURE-DIRECTED" ACTIONS AND "RECOVERY" ACTIONS
22. IAEA.PNRA.05.05 Stetkar & Associates 22 ELEMENTS OF A HUMAN ACTION IDENTIFICATION
DIAGNOSIS COGNITIVE
DECISION
RESPONSE IMPLEMENTATION
23. IAEA.PNRA.05.05 Stetkar & Associates 23 HUMAN BEINGS ARE NOT HARDWARE HUMAN RELIABILITY CANNOT BE EVALUATED OUT OF CONTEXT
HUMAN PERFORMANCE DEPENDS ON THE ENTIRE HISTORY OF ACCUMULATED KNOWLEDGE, EXPERIENCE, TRAINING, GUIDANCE, AND INFORMATION UNTIL THE TIME OF RESPONSE
HUMANS INTERPRET THE INFORMATION THAT THEY RECEIVE, EVALUATE ITS RELEVANCE AND MEANING, FORM A CONCLUSION, AND RESPOND
INFORMATION, INTERPRETATION, AND DECISION DEPEND ON THE SCENARIO CONTEXT
24. IAEA.PNRA.05.05 Stetkar & Associates 24 SCENARIO-BASED PERSPECTIVE PSA MODELS CONTAIN VERY LARGE NUMBERS OF INDIVIDUAL SCENARIOS ("SEQUENCES", "CUTSETS", ETC.)
IDENTIFY IMPORTANT DIFFERENCES THAT AFFECT HUMAN RESPONSE
GROUP SCENARIOS AND DEFINE PSA ACTIONS BASED ON SUCCESS CRITERIA AND BOUNDARY CONDITIONS FOR HUMAN PERFORMANCE
MANUAL START OF STANDBY EQUIPMENT IS A SCENARIO-BASED COGNITIVE ACTION
25. IAEA.PNRA.05.05 Stetkar & Associates 25 SCENARIO-BASED CONSIDERATIONS INITIATING EVENT
AVAILABLE TIME WINDOW
AVAILABLE EQUIPMENT
CUES, INDICATIONS, AND ALARMS
PROCEDURES, TRAINING, AND EXPERIENCE
COMPETING PRIORITIES
PREVIOUS OPERATOR ACTIONS (SUCCESSES AND FAILURES)
26. IAEA.PNRA.05.05 Stetkar & Associates 26 IDENTIFY / DISPLAY HUMAN DEPENDENCIES PSA MODELS SHOULD:
DISPLAY OPERATOR ACTIONS IN SCENARIO CONTEXT
IDENTIFY ALL CONDITIONS WHERE OPERATOR ACTIONS ARE COMBINED THROUGH "AND" LOGIC
DIFFICULT TO IDENTIFY SCENARIO CONTEXT AND COMBINED ACTIONS IN FAULT TREE FORMAT
USUALLY REQUIRES MODEL SOLUTION
NUMERICAL VALUES MAY SUPPRESS CUTSETS
"SCREENING VALUES" MAY BE OPTIMISTIC
EVENT TREE FORMAT GENERALLY BETTER
DEFINES SCENARIO CONTEXT
IDENTIFIES COMBINED ACTIONS
27. IAEA.PNRA.05.05 Stetkar & Associates 27 OPERATOR ACTIONS IN FAULT TREES ADVANTAGES
SIMPLER EVENT TREES
DISADVANTAGES
MORE COMPLEX FAULT TREES
MORE DIFFICULT FOR ANALYSTS TO IDENTIFY SCENARIO-SPECIFIC DEPENDENCIES
HOUSE EVENTS OR SPECIAL LOGIC TO DEFINE CONDITIONS FOR CORRECT ACTIONS
GENERAL EXPERIENCE FROM REVIEWS
POOR TREATMENT OF OPERATOR ACTIONS
OPTIMISTIC QUANTIFICATION OF COMBINED ERRORS
28. IAEA.PNRA.05.05 Stetkar & Associates 28 OPERATOR ACTIONS IN EVENT TREES ADVANTAGES
SIMPLER FAULT TREES
EASIER FOR ANALYSTS TO IDENTIFY SCENARIO-SPECIFIC DEPENDENCIES
DISADVANTAGES
MORE COMPLEX EVENT TREES
BRANCH POINT CONDITIONS TO DEFINE CORRECT ACTIONS
GENERAL EXPERIENCE FROM REVIEWS
IMPROVED TREATMENT OF OPERATOR ACTIONS
REALISTIC QUANTIFICATION OF COMBINED ERRORS
29. IAEA.PNRA.05.05 Stetkar & Associates 29 PLANT DAMAGE STATES
30. IAEA.PNRA.05.05 Stetkar & Associates 30 PLANT DAMAGE STATES (PDS) DEFINE INTERFACE BETWEEN PLANT ANALYSIS (LEVEL 1 PSA) AND CONTAINMENT ANALYSIS (LEVEL 2 PSA)
PLANT DAMAGE STATES ARE "INITIATING EVENTS" FOR LEVEL 2 PSA
COLLECT LEVEL 1 EVENT SEQUENCES WITH SIMILAR CONTAINMENT RESPONSE
"LEVEL 1+" PSA EXTENDS MODELS TO INCLUDE CORE DAMAGE SEQUENCES AND CORRESPONDING PLANT DAMAGE STATES (INTERNATIONAL PSA TERMINOLOGY)
31. IAEA.PNRA.05.05 Stetkar & Associates 31 PLANT DAMAGE STATE PARAMETERS REACTOR COOLANT SYSTEM PRESSURE
STEAM GENERATOR HEAT REMOVAL
WATER INJECTION
CORE DEBRIS COOLING / CONTAINMENT HEAT REMOVAL
FISSION PRODUCT REMOVAL
CONTAINMENT ISOLATION
32. IAEA.PNRA.05.05 Stetkar & Associates 32 TIMING CONSIDERATIONS SOME PSAs DISTINGUISH BETWEEN CONDITIONS AT TIME OF CORE DAMAGE AND AT TIME OF VESSEL FAILURE
SOME PSAs DISTINGUISH BETWEEN "EARLY" AND "LATE" CORE DAMAGE SCENARIOS
"EARLY" OFTEN ASSOCIATED WITH LOSS OF SECONDARY COOLING OR LOCAs WITH INJECTION FAILURE
"LATE" OFTEN ASSOCIATED WITH LOSS OF RHR COOLING OR RECIRCULATION FAILURE
"LARGE EARLY RELEASE FREQUENCY" (LERF) IMPORTANT FOR SOME RISK-INFORMED APPLICATIONS
MANY PSAs DO NOT INCLUDE TIME AS A PLANT DAMAGE STATE PARAMETER