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Risk Informed InService InspectionResults of Studies on Nuclear Power Plants and Heavy Water Plants

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Title: Risk Informed InService InspectionResults of Studies on Nuclear Power Plants and Heavy Water Plants


1
Risk Informed In-Service Inspection-Results of
Studies on Nuclear Power Plants and Heavy Water
Plants
  • Santhosh
  • Reactor Safety Division, BARC
  • Mumbai, India.

2
Overview of Presentation
  • Introduction
  • RI-ISI Methodology
  • Case Study 1 Heavy Water Plants
  • Case Study 2 Indian PHWRs
  • Conclusions

3
Risk Analysis in PublicPolicy Decision
  • Most of the public policy decisions that are made
    involve the allocation of resources.
  • Available resources, whether natural or human,
    are finite. Therefore, resource allocation
    involves certain trade-offs.
  • The outcome of many ,if not most, public policy
    decisions is uncertain.

4
Risk Analysis in PublicPolicy Decision
  • The best way to deal with such uncertainties is
    the risk analysis.
  • Determining or estimating the probability of
    various outcomes gives a more complete picture
    than focusing only on the most likely (or the
    desired) outcome.
  • The cost of resources allocated can be compared
    to the benefits to inform decisions.

5
Risk Assessment in Industry
6
(No Transcript)
7
RI-ISI Methodology
8
RISK INFORMED IN-SERVICE INSPECTION
  • CONSEQUENCE
  • HEALTH
  • DAMAGE
  • TOXIC
  • ECONOMIC
  • LIKELIHOOD FREQUENCY
  • SERVICE DATA ANALYSIS
  • STRUCTURAL RELIABILITY ANALYSIS
  • REMAINING LIFE MODELS
  • EXPERT JUDGEMENT
  • RISK MATRIX
  • DEFINES THE INSPECTION CATEGORY,
  • METHOD, FREQUENCY AND SCOPE OF INSPECTION

LIKELIHOOD FREQUENCY
RISK
INSPECTION
9
Advantages of RI-ISI
  • Decision making based on the risk criteria and
    deterministic information
  • Better focus on allocating resources to high
    safety significant components.
  • In- Service Inspection based on failure modes of
    components and associated risk

10
Guides for RI-ISI
  • NUREG 1661- RI-ISI for Nuclear Power Plants by US
    Nuclear Regulatory Commission
  • API 581- Base Resource Document Mainly used by
    Chemical, Oil Petrochemical Industries
  • ASME RBI Guidelines Vol. 3- for Fossil Fuel
    Plants
  • EPRI- Risk Based Maintenance Guidelines
  • Risk based Inspection MAintenance Procedures
    (RIMAP) Workbook

11
Case Study 1RI-ISI of Heavy Water Plant
12
Scope and Objective
  • Apply RI-ISI for components connecting the
    CT1-HT1 towers, and compare with the existing ISI
    plan
  • To demonstrate the reduction in inspection
    achieved through adopting RI-ISI without
    compromising the plant safety
  • To ensure that the inspection will be focused on
    more safety significant components

13
Schematic Diagram of HWP
14
Steps Involved
  • Scope boundary of the study
  • Data collection on piping and equipment
  • Finding the inventory in each component (mass of
    H2S in liquid gas)
  • Evaluate the failure probability consequence
  • Establish the categories for failure probability,
    consequence risk
  • Conduct a risk impact analysis

15
Piping Failure Analysis Structural Reliability
  • Material properties for failure analysis
  • Possible damage mechanisms
  • Past inspection history for degradation rate
  • ASME B31G-Failure Pressure Model for estimating
    the remaining strength of a corroded pipeline
  • Limit state function is formulated for estimating
    the pipeline failure probability
  • COMREL tool for computing the failure probability

16
Equipment Failure Analysis Bayesian Updation
Technique
  • Plant specific failure incidences were collected
    for various equipment from SRUORs
  • Analyzed the failure incidences for identifying
    the exact failure mode
  • Updated the generic information with the plant
    specific data using Bayesian technique
  • Developed software for data base management and
    reliability analysis

17
DAMAGE
  • Chemical
  • Quantity
  • State
  • Economic loss

18
Consequence Category Specified in API 581
19
Damage - Piping
20
Damage - Equipment
21
Health - Piping
22
Health - Equipment
23
Consequence Matrix
24
Consequence Category- Equipment
25
RISK MATRIX
26
Risk Category - Equipment
27
Risk Impact Analysis
CURRENT INSERVICE INSPECTION (ISI) PROGRAMME HAS
THREE INSPECTION CLASSES, VIZ. A, B C A
CARRYING H2S AND NON-ISOLATABLE B CARRYING H2S
AND ISOLATABLE C UTILITY FLUIDS Consequence is
considered in an implicit manner, but failure
potential are not considered
28
Risk Impact Analysis
29
Risk Impact Analysis-Results
30
Case Study 2RI-ISI of Nuclear Power Plants
31
Current PHWR ISI Programme
  • Currently In-Service Inspection is based on CAN
    standards - CAN/CSA-N 785.4-94
  • Inspection categories are defined as a function
    of fatigue usage factor, stress ratio and size of
    failure (RE)
  • Fatigue usage factor is determined as per the
    rules given in ASME Boiler and Pressure Vessel
    Code

32
INSPECTION CATEGORY FOR MEDIUM FAILURE SIZE
INSPECTION CATEGORY FOR LARGE FAILURE SIZE
Scope, frequency methods of inspection in
categories A, B, C1 C2 are decided by expert
group formed by utility
33
RI-ISI for NPPs International Scenario
34
Importance Measure in RI-ISI
  • ASME-WOG SUGGESTED RRW RAW IN ISI PRIORITISION

35
ASME-WOG on Indian PHWR
  • Applied ASME-WOG ranking scheme on process and
    safety systems of Kaiga Generating Station using
    KGS PSA results
  • RAW and RRW have been evaluated for initiating
    events considering the frequencies as 1/year and
    0/year respectively

36
SYSTEM PRIORITISATION - ASME/WOG
37
Application on Indian PHWRs
  • RI-ISI was applied on piping segments connecting
    the Primary Heat Transport System Shutdown
    Cooling System
  • Leak and rupture frequencies for piping segments
    were evaluated using Thomas model
  • Possible degradation mechanisms were considered

38
Application on Indian PHWRs
  • Consequence is quantified using Conditional Core
    Damage Probability
  • EPRI Risk matrix was applied for risk
    categorization
  • Risk impact analysis was carried out comparing
    with the current ISI programme

39
PHT of Indian PHWRs
40
Component Failure Frequency
  • STATISTICAL METHODS PAST EXPERIENCE
  • DEGRADATION MECHANSIMS
  • THOMAS MODEL WELDS, DIAMETER, LENGTH,THICKNESS,
    DESIGN, AGE, ETC
  • MECHANISTIC MODELS - BY UNDERTSANDING THE
    PREVALENT PHENOMENA IN THE COMPONENT

41
Classification of Degradation Mechanisms
42
Possible Degradation Mechanisms in Indian PHWRs
Atmospheric Corrosion
Boiler
Erosion Corrosion
SCC, CF
Turbine
Generator
Calandria
Condenser
SCC, Pitting, etc
Hydriding,
43
Risk Matrix
44
ISI CATEGORIES FOR COMPONENTS IN PHT
45
ISI CATEGORIES FOR COMPONENTS IN SDCS
46
Code for Inspection Methods
  • Visual examination 1
  • Dimensional examination 2
  • Surface examination 3A (LPT, MPT, ET)
  • Volumetric examination 3B (UT,RT,ET)
  • Integrative examination - 4

47
RESULTS
48
Suggested Inspection Method
49
Conclusions
  • RI-ISI was applied to HWPs and Indian PHWRs and
    demonstrated its advantages over the current ISI
    programme
  • Reduction in quantum of inspection which in turn
    improves the plant down time and cost
  • RI-ISI provides a basis of quantification for the
    inspection programme
  • RI-ISI focuses inspections on most significant
    areas, where
  • Degradation mechanisms are present
  • Consequence of potential failure are greater
  • Overall plant safety improvement is possible

50
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