ML20116F275
| ML20116F275 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1996 |
| From: | Richard Anderson, Steven Arndt, Bell T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | |
| References | |
| FACA, NUREG-BR-0228, NUREG-BR-228, NUDOCS 9608060300 | |
| Download: ML20116F275 (35) | |
Text
.-
4 NUREG/BR-0228 4
i
't f
United States
/
l Nuclear Regulatory Commission g,
(
l Development of XRC Staffin Guidance for Professional l Regulatory Risk Analysis l
i j
l l
l Office for Analysis and Evaluation of Operational Data i
S. A. Arndt, R. L Anderson, T. L Bell i
July 1996 0\\j 1
- k i
l
- en" 28Re8
- 7 2
]
BR-0228 R PDR
.__._.m._.m 1
7 t
l j
AVAILABILITY NOTICE 1
i Availability of Reference Materials Cited in NRC Publications i
Most documents cited in NRC publications will be available from one of the following sources.
1.
The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.
The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082, j
Washington, DC 20402-9328 3.
The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-j tions, it is not intended to be exhaustive.
i l
Referenced documents available for inspection and copying for a fee from the NRC Public l
Document Room include NRC correspondence and internal NRC memoranda: NRC bulletins,
{
circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.
The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, grantee reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission issuances.
I Documents available from the National Technical Information Service include NUREG-series i
reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nucl ear Regulatory Commission.
Documents available from public and special technical libraries include all open literature items, buch as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries, j
Documents such as ineses, dissertations, foreign reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear i
Regulatory Commission, Washington DC 20555-0001.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted
]
and may be purchased from the originating organization or, if they are American National j
Standards, from the American National Standards Institute,1430 Broadway, New York, NY 10018-3308.
J
J i
p+** "*%
United States 5
i Nuclear Regulatory Commission
,,,,,/
i Guidance for Professional Development of NRC Staffin Regulatory Risk Analysis l
S. A. Arndt, R. L Anderson, T. L Bell Technical Training Division Office for Analysis and Evaluation of Operational Data July 1996 1
ABSTRACT This document provides a summary of suggested training programs recommended for Nuclear Regulatory Commission personnel who either perform or use the results of probabilistic risk assessments (PRAs) in their day-to-day work activities. Tasks range from using PRA results to working with PRA models. This document is designed to allow the formulation of training programs based on job requirements, educational background, and PRA experience.
i l
i l
1 iii
Table of Contents Introduction.................
I General Guidance.................
2 Education 3
Technical Training 3
Experience 4
Appendix A Listing of PRA Courses.
6 Appendix B Recommended Course Sequences 7
Appendix C Course Descriptions 15 Figures Figure 1
- Necessary Components To Achieve PRA Knowledge, Skills, and Abilities Levels..
5 Figure 2
- Recommended Course Sequence for Inspectors and Program Managers..
8 Figure 3
- Recommended Course Sequence for Technical Managers.....
9 Figure 4
- Recommended Course Sequence for Senior Reactor Analysts and Events Assessment Personnel 12 Figure 5
- Recommended Course Sequence for Severe Accident Personnel....... 13 Figure 6
- Recommended Course Sequence for NMSS Perfomiance Assessment and Hydrology Personnel........................
14 i
I V
j
I.
Introduction The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements of its licensing and regulatory processes. In October 1991, the NRC's Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff's uses of PRA. After determining staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development.
For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group completed its assigned tasks in 1993, and a summary report, NUREG-1489, "A Review of NRC Uses of Probabilistic Risk Assessment," was published in March 1994.
In addition to the PRA Working Group, two other high-level groups were established to address the concern over the NRC staff's use of PRA. The Regulatory Review Group reviewed NRC processes, programs, and practices with a focus on seeking replacement of prescriptive requirements and guidance with requirements based on performance and the use of risk insights.
The Regulatory Analysis Steering Group was tasked with the oversight of guidance for proposed regulatory actions.
In a November 2,1993, memorandum to the Executive Director for Operations, the Office of Nuclear Reactor Regulation (NRR), Office of Nuclear Material Safety and Safeguards (NMSS),
Office for the Analysis and Evaluation of Operational Data (AEOD), and the Office of Nuclear Regulatory Research (RES) collectively focused on the findings and recommendations made by the above three NRC study groups regarding the status of PRA use and its role in the regulatory process. In the memorandum, the offices concurred in the need to systematize and expand the use of PRA within the agency.
The Commission issued a policy statement (SECY-94-218) to declare the agency's commitment to increase the use of PRA methods and insights in its regulatory activities. This policy statement aniculated the Commission's position on the role of PRA in various regulatory programs and communicated that position to the staff, the public, licensees, and applicants for licenses.
The staff then proposed to formulate a comprehensive plan (PRA Implementation Plan, SECY 219) for application of PRA technology and insights throughout the agency. The Commission then endorsed the PRA Implementation Plan to as a means of achieving the concepts in the PRA policy statement. The goal of the PRA Implementation Plan is to improve the way the NRC regulates by increasing the use of PRA in regulatory matters to the extent practical given the state-of-the-art in PRA methods and data available. This plan, which is updated quarterly, provides the framework for continued current and future applications of PRA at the NRC.
To suppor't the goal of improved regulatory activities through increased use of PRA technology, the plan includes an extensive training program. As the agency shifts to greater use of and reliance on PRA methods and risk-informed regulation, all technical staff members, including inspectors, will need to develop an understanding of the strengths and limitations of PRA methods and their use. Training of the staff will be a critical pan of the change in the regulatory culture of the agency.
The PRA Working Group's report, referred to above, recommended the development of a complete Probabilistic Risk Assessment (PRA) curriculum and identified three levels of agency 1
1
i l
PRA users. The first broad category of PRA user is the Basic User. This category consists of staff who use PRA results and require some basic information on how PRAs are performed and the results are obtained. The second category is called the Advanced User and consists of staff who work with PRA models or manage contractor efforts with PRA models. The Advanced User will require more extensive training. The final category is the Expert Practitioner. This group consists of staff who perform quality assurance and expert advisory functions as well as develop new PRA models.
II. General Guidance The PRA training program is designed to assist staff members to develop new knowledge, skills, and abilities (KSAs) in PRA methods and statistics. These KS As are considered to fall into the three broad categories of Basic User KSAs, Advanced User KSAs, and Expert Practitioner KSAs.
As illustrated in Figure 1, some formal education, training, and experience is needed to obtain the KSAs for each of the PRA levels. As the level of KSAs move from Basic User to Advanced User to Expert Practitiener, less information can be gained in short training courses, and greater emphasis must be placed on formal education and experience. The PRA training curriculum will serve as the baseline from which to continue staff development in this area.
In addition to classroom instruction in training courses, college courses, on-the-job training, and industrial experience will be needed in order to acquire some of the required knowledge and expenence.
Placement of all NRC technical staff positions into one of the three KSA categories is the responsibility of NRC line management. This guideline provides recommendations for this placement. Some of the job functions have been reviewed and are included as examples. Thesejob functions are:
Basic User Resident Inspectors Regional Inspectors Licensing Project Managers Operator Licensing Examiners NRR and NMSS Technical Reviewers TfD Instructors Headquaners and Regional Duty Officers Reactor Safety Team Personnel Agency Technical Managers AEOD Reactor Analysis Branch Personnel Advanced User NRR PSA Branch Personnel AEOD Reliability and Risk Assessment Branch Personnel RES PRA Branch Personnel NMSS Performance Assessment and Hydrology Personnel Event Assessment Personnel Severe Accident Personnel Senior Reactor Analysts NUREG/BR-0228 2
1 s.
The Expert Practitioner does not appear in the lists above because this position requires more education and experience than can be provided by the PRA training program. Also,it is recognized that NRC management may chose to provide selected individuals from the Basic or Advanced User categories with additional training and developmental assignments. For example, an Operator Licensing Examiner is a Basic User; however, if desired, one or two Operator Licensing Examiners in each region may receive training which would (along with experience) provide them with Advanced User skills. Although the KSAs needed for Basic Users will be primarily obtained through training, it must be emphasized that to obtain some of the most basic KSAs, on the job training is needed. Managers are encouraged to provide work assignments for all of their technical staff that will exercise their PRA training.
l l
III. Education College level courses in probability and statistics and reliability engineering may be needed to achieve desired the KSA levels. The availability and applicability of courses must be determined on a case-bycase basis. Some Advanced Level Users and t!xpert Practioners will require more extensive knowledge of the theory and development of PRA techniques that can be obtained j
through advanced degree programs. A number of universities offer such programs. The TTD staff will assist managers in determining what educational requirements are needed for a particular technical position.
IV. Technical Training This document provides listings of training course sequences for the Basic and Advanced User and should be used along with the TfD Catalog (which includes an integrated schedule). Appendix A contains a listing of all current PRA Training Courses, Appendix B lists recommended course sequences for selectedjob functions, and Appendix C contains PRA Course Descriptions. These appendices, along with the recommended course sequences, should be used to help determine PRA training needs for groups of NRC employees and for individual employee development.
The course descriptions also contain information about course premquisites and examinations.
Prerequisites have been established to ensure employees have previously acquired skills necessary to reasonably predict success in the training course. The employee's supervisor should ensure that all prerequisites are met. Examinations are given in the courses to provide feedback to employees, their supervisors, and the training instructors. By satisfactorily completing the examination, employees demonstrate mastery of minimum course skills. Examination results are reported to the employee's supervisor and may be used in employee development. Training instructors use examination results as one method of validating training. Examination questions which continuously receive a high or low score may be used for determining the necessity for course changes.
The Technical Training Division of AEOD, through the Idaho National Engineering Laboratory (INEL) and consultation with NRC offices, regularly updates PRA courses to incorporate the latest information available, and as needs change, adds new courses to the curriculum. If employees have not recently attended a particular PRA course, repetition of the course may benefit them.
Repetition of the course may be used as a part of employee retraining.
Development of employee KSAs may be broken down into three areas: training, education, and experience (Figure 1). While this document provides information on training opportunities, the other two aspects of employee development cannot be ignored. Employees and their supervisors should ensure that these two elements are included in the overall development program.
V.
Experience On-the-job-training and formal and informal development programs should make up the experience part of the PRA development program. These requirements should be formulated by the employee's supervisor. These programs should include elements that will provide the employee with sufficient opportunity to practice the KS As that have been obtained in the education and training part of his/her development. This work should contain projects where the staff member being developed can demonstrate the ability to preform various tasks that are part of doing a PRA-related job, under the mentorship of a more experienced user (such as a Senior Reactor Analyst for a Basic User or an Expert Practitioner for an Advanced User). Experience might be gained through rotational assignments performing accident sequence precursor event assessment or participation in reviews of risk-based technical specifications, for example. The TTD staff will assist managers in determining what experience is needed for a particular technical position.
Figure 1 - Necessary Components To Achieve PRA Knowledge, Skills, and Abilities Levels Development of New PRA Models Quality Assurance Work in PRA 7ju.,_- ~,- -. Ley,el KSAsa a R, a d i a,,i, a.y.y,,,.,,,,.,,, 7 m,ifj pert Prac.
er.
...m,
._.y..,,,
,,.y,,
y 2racug:ggf I
i Advanced Specialized Experience Work with PRA Education in Traimng in New Reviewing and Methods and Methods Specialized Areas Developing PRAs Tools and Techniques I
n,w I
n,mmne er.mpmynr.mmm Lg1SD3C.g7.. ggEw&wijioneMu2kl&MAuf uh kliuGa&1%LkdaA&:.uhdl
. ~.
Theory and Training in Advanced User Experience Using Use of PRA Application of Reliability and Risk Skills (NRC PRA and Modifying Results Engineering Training Program)
PRAs (See Sequences) 1 I
gg,g gOgyg-~m-w 7 7pey-mwy'y:I-m7gmynvywmpg$.3
% w Mhwaa:wa :%3 u _... ~I M c m e s t %
.J a: %: m % za a.I Probability and Experience Using Statistics Risk Insights l
Training in Basic User Skills (NRC l
PRA Training l
Program)
Experience Fundamentals of (See Sequences)
Applying Engineering and Engineering Design (B.S. in Methods to Engineering)
Inspection and i
Rev*ew
{
Formal Education PRA Training Experience Typical Continuing in PRA Area Applying PRA or Refresher Activities 5
l l
Appendix A - Listing of PRA Courses Course Title Number Length Fundamentals Of PRA P-101 3 days Probability and Statistics for PRA P-102 5 days PRA Basics for Regulatory Application P-105 3 days PRA Insights into IPEs P-106 2 days PRA for Technical Managers
- P-107 3 days PRA Technology and Regulatory Perspectives
- P-111 2 weeks System Modeling Techniques for PRA P-200 4 days IRRAS Basics P-201 4 days Advanced IRRAS P-202 4 days Human Reliability Assessment P-203 3 days External Events
- P-204 3 days Accident Progression Analysis
- P-300 3 days Accident Consequence Analysis
- P-301 3 days Risk Assessment In Event Evaluation P-302 3 days
- Course 'mder development NUREG/BR-0228 6
AJ
Appendix B - Recommended Course Sequences Recommended PRA Training Course Sequences for Basic Users 1.
Knowledge of plant systems should be obtained by attending a reactor technology full course series. (R-304, R-504, and R-624) 2.
The Perspectives on Reactor Safety Course (R-800) is also recommended. This course provides a broad perspective of important reactor safety concerts with emphasis on topics important to risk.
3.
The fundamental concepts of probabilistic risk assessment should be obtained from either the PRA for Regulatory Applications course (P-105) or the Fundamentals of PRA course (P-101).
4.
The use of PRA results is taught in the PRA Insights Into IPEs course (P-106).
Notes:
The Human Reliability Assessment (P-203) course discusses the methods involved in modeling human error and various methods of estimating their probability. This course may be beneficial to some basic users. The prerequisite for this course is the PRA Basics for Regulatory Applications (P-105) course or the Fundamentals of PRA course (P-101).
The PRA Technology and Regulatory Perspectives (P-111) course will replace the PRA Basics for Regulatory Applications (P-105) course (or the Fundamentals of PRA course (P-101)) and the PRA Insights Into IPEs (P-106) as required training for reactor inspectors, reviewers, and other technical personnel within the reactor program.
P I
Figure 2 - Recommended Course Sequeuce for Inspectors and Program Managers Full Course Series in Reactor Technology if Perspectives on Reactor Safety (R 800)
V t
PRA Basics for Fundamentals Regulatory of PRA P,11c on
() )
(P-101) if PRA Insights into IPEs (P-106)
Figure 3 - Recommended Course Sequence for Technical Managers Full Course Series in Reactor Technology Y
Perspectives on Reactor Safety (R-800)
V PRA for Technical Managers (P-107) 9 NUREG/BR-0228 i
l
Recommended PRA Training Course Sequences for Advanced Users 1.
Knowledge of plant systems should be obtained by attending a reactor technology full course series. (R-304, R-504, and R-624) 2.
The Perspectives on Reactor Safety Course (R-800) provides a broad perspective of important reactor safety concepts with emphasis on topics important to risk.
3.
The fundamental concepts of probabilistic risk assessment should be obtained from either the PRA for Regulatory Applications course (P-105) or the Fundamentals of PRA course (P-101).
4.
The use of PRA results is taught in the PRA Insights Into IPEs course (P-106).
5.
The Applied Statistics course provides basic knowledge in probability and statistics required for the remainder of the sequence. The Applied Statistics course is tanght by the Office of Personnel.
6.
The Probability and Statistics for PRA course (P-102) presents quantative concepts from the fields of probabilistic modeling, statistics, and reliability theory that arise frequently in PRA. Successful completion of this course is necessary for the understanding of advanced topics discussed in subsequent courses.
7.
The Integrated Reliability and Risk Analysis System (IRRAS) Basics course (P-201) provides hands-on training in the use of the IRRAS software to perform PRA analysis on the PC. Successful completion of this course is necessary for the Advanced IRRAS (P-202) and the Risk Assessment in Event Evaluation (P-302) courses.
8.
The Systems Modeling Techniques for PRA course (P-200) covers the calculation of initiating event frequencies, component failure rates, and the use of " super components" to create fault trees. This course provides information that will allow the student to successfully create or modify PRA models. This course is a prerequisite for the Advanced IRRAS (P-202) and Risk Assessment in Event EvMuation (P-302) courses.
9.
The Advanced IRRAS (P-202) course provides the student with information on the advanced features of the IRRAS software.
10.
The Human Reliability Assessment (P-203) course discusses the methods involved in modeling human error and various methods of estimating their probability. Although this information is necessary for a complete understanding of PRA methodology, the only prerequisite for this course is the PRA Basics for Regulatory Applications (P-105) or the Fundamentals of PRA (P-101).
I 1.
The Risk Assessment In Event Evaluation (P-302) course covers the use of PRA techniques to assess the significance of initiating events and condition assessments that occur at operating reactors. This course teaches the employee how to use and modify the Graphics Evaluation Module (GEM) software to obtain PRA results. An understanding of PRA concepts, Systems Modeling, IRRAS and Advanced IRRAS courses, and HRA are necessary prerequisites.
12.
The External Events (P-204) course deals with the analysis of external events such as fires, floods, earthquakes, high winds, and transportation accidents. A through understanding of PRA Level 1 is a prerequisite.
13.
The Accident Progression Analysis (P-300) course deals with the portion of PRA typically referred to as Level 3 analysis. The PRA Basics for Regulatory Applications course is a prerequisite.
14.
The Accident Consequence Analysis (P-301) course with the portion of probabilistic risk assessment typically referred to as Level 2 analysis. The PRA Basics for Regulatory Applications and Probability and Statistics for PRA courses are necessa.y prerequisites.
Note: The PRA Technology and Regulatory Perspectives (P-111) course will replace the PRA Basics for Regulatory Applications (P-105) course (or the Fundamentals of PRA course (P-101)) and the PRA Insights Into IPEs (P-106) as required training for reactor inspectors, reviewers, and other technical personnel within the reactor program.
l
\\
l l
11 NUREG/BR-0228 L
'l Figure 4 - Recommended Course Sequence for Senior Reactor Analysts and Events Assessment Personnel Full Course Human A plied Statistics Reliability P
Series in Reactor 9
Technology (or equivalent)
Assessment (P-303)
V if if Perspectives on Probability and Risk Assessment i
Reactor Safety Statistics for in Event 4
(R-800)
PRA Evaluation (P-102)
(P-302)
If If 1
1 PRA Basics for l
Regulatory IRRAS liasics 1
Application (P-201)
(P-105) i
)
If If PRA Insights System Modeling into IPEs Techniques
?
(P-106) for PRA (P-200)
II Advanced IRRAS (P-202)
Figure 5 - Recommended Course Sequence for Severe Accident Personnel Applied Statistics Relfa i ty Ser i
cactor Technology (or eqmvalent)
Assessment (P-203) 1r V
V Perspectives on Probability and External Reactor Safety Statistics for Events (R-800)
PRA (P-204)
(P-102)
V V
V Fundamentals Accident of PRA IRRAS Basics Progression (P-101)
(P-201)
Analysis (P-300)
V y
y PRA Insights System Modeling Accident into IPEs Techniques Consequence (P-106) for PRA Analysis (P-200)
(P.301)
V Advanced IRRAS (P-202) 13 NUREG/BR-0228
Figure 6 - Recommended Course Sequence for NMSS Performance Assessment and Hydrology Personnel Human Courses.in Applied Statistics Reliabilit Appropriate (or equivalent)
Assessment Technology P-203)
If if if Fundamentals Probability and Additional of PRA Statistics for Courses in (P-101)
PRA Performance (P-102)
Assessment (Future Development)
If If IRRAS Basics (P-201) if System Modeling Techniques for PRA (P-2')0) 1f Advanced 1
IRRAS (P-202)
Appendix C - Course Descriptions Fundamentals of Probabilistic Risk Assessment (P-101)
Course
Description:
This course is for those personnel seeking to acquire introductory level skills in PRA and includes a broad introduction to PRA and its applications. The course includes an introduction of PRA methods used in system modeling, accident progression analysis, and accident consequence analysis. Also included is a discussion of PRA strengths, limitations, and results. Specific topics include: accident initiators; event tree and fault tree analysis and quantification; data development and common cause failures; human reliability analysis; external events analysis; accident progression analysis; fission product transport and release; fundamentals
)
of consequence evaluation; and PRA program and requirements. In-class instruction is i
supplemented with workshops and problem-solving sessions.
Length:
3 Days 21 Instructional Hours i
Examination:
Written Comprehensive Final Examination Prerequisites:
Reactor Technology Full Course Series Applicability:
NRC personnel with a general interest in learning basic PRA techniques and concepts Course Topics Initiating Events and Success Criteria Event Tree Analysis Fault Tree Analysis Data Development and Common Cause Failures Human Interactions Accident Sequence Quantification External Events a
Accident Process and Consequence Analysis PRA Programs and Requirements PRA Results PRA Strengths, Limitations, and Uncertainties a
PRA Uses and Applications
=
15 NUREG/BR-0228 i
Probability and Statistics for PRA (P-102)
Course
Description:
This course presents selected quantitative concepts from the fields of probabilistic modeling, statistics, and reliability theory that arise frequently in PRA. Through lecture and workshop problems, participants are presented with mathematical techniques from probability and statistics that have applications in current PRA. The topics covered include a review of classical probability and statistics, selected distributions important to PRA, uncertainty analysis techniques, and Bayesian analysis.
Length:
5 Days 35 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Participants should have at least a bachelor's degree in mathematics, science, or engineering. Participants must be familiar with calculus and be able to perform proficiently in probability and statistics at the undergraduate level. An alternative would be completion of the NRC course " Applied Statistics."
Applicability:
Designed to appeal to those personnel tasked with reviewing or managing PRAs Course Topics Random Variables, Sample Spaces, and Set Theory I
Probability Discrete Probability Distributions Continuous Probability Distributions Cumulative Distribution Functions Joint, Marginal, and Conditional Distributions
+
Expectation of Random Variables Sample Moments Measures of Reliability StatisticJ Models Used in Reliability ModelIdentification and Selection
+
Bayesian Inference in Reliability Performing a Bayesian Reliability Analysis
=
Bayesian Decision Theory Uncertainty Analyses a
Sensitivity Analyses NUREG/BR-0228 16
PRA Basics for Regulatory Applications (P-105)
Course
Description:
This course addresses the special needs of the regulator who requires knowledge of PRA issues and insights to better evaluate the effects of design, testing, maintenance, and operating strategies on system reliability. The full range of PRA topics is presented in abbreviated form with the goal of introducing the regulatory staff to the basic concepts and terminology of PRA as applied to the inspection process. The course uses actual plant PRAs and IPEs and stresses the uses and applications of these publications in planning audits and inspections and evaluating plant safety issues.
Length:
3 Days 21 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Reactor Technology Full Course Series Applicability:
Regional Inspectors, Resident inspectors, Licensing Project Managers, Project Engineers and other technical personnel involved in the plant regulatory process Course Topics Risk Assessment Concepts General PRA Results Generic Letter 88-20 PRA Elements Accident Sequence Interpretation Importance Measures BWR Accident Sequences PWR Accident Sequences Component Failure Data Uncertainties in PRA Event Significance Analysis Configuration Management 17 NUREG/BR-0228
PRA Insights Into IPEs (P-106)
Course
Description:
This course provides a realistic, intensive opportunity to use actual PRA/IPE results and information. Through examples and workshops,. students participate in a number of exercises which reinforce and build on concepts presented in the PRA Basics for Regulatory Applications course. The course is tailored to the specific needs of regional inspection personnel and licensing project managers. The course consists almost entirely of exercises and workshop problems which teach students to use PRA information as an input to real decisions regarding inspection priorities, Temporary Waivers of Compliance, integrated scheduling, license amendments, and other regulatory issues. To the extent possible, real PR A/IPE studies are used as the basis for the workshops.
Length:
2 Days 14 InstructionalIlours Examination:
None Prerequisites:
PRA Basics for Regulatory Applications and college level familiarity with probability, statistics, and calculus Applicability:
Regional Inspectors, Resident inspectors, Licensing Project Managers, Project Engineers, Project Directors and other technical personnel who may have to use PRA information as an input to regulatory decision-making Course Topics IPE/PRA Orientation and Review IPE Status IPE Workshops IRRAS Demonstrations Question / Answer Session R
l NUREG/BR-0228 18 i
PRA for Technical Managers (P-107)
Course
Description:
This three day course is designed to introduce the NRC technical manager to PRA concepts including reactor and non-reactor applications. The course includes an introduction to PRA methods used in system modeling, accident progression analysis, accident consequence analysis, and performance assessment. Also included is a discussion of PRA strengths, limitations, and uncertainty. The course will discuss agency applications of PRA methodology.
Length:,
3 Days 21 Instructional Hours Examination:
None Prerequisites:
None I
Applicability:
Any NRC Technical Manager Course Topics PRA Policy Statement and Implementation Plan Risk Assessment Concepts and PRA Event Tree Analysis Fault Tree Analysis Reliability Data Analysis Human Interactions Sequence Quantification Accident Progression and Consequence Analysis Uncertainties in PRA Extemal Events Configuration Management Testing and Maintenance Optimization Overview of Performance Assessment PRA Strengths and Limitations 1
1 i
PRA Technology and Regulatory Perspectives (P-111)
Course
Description:
This course addresses the special needs of Regional Inspectors, Resident Inspectors; and other technical personnel who require knowledge of PRA issues and insights to better evaluate the effects of design, testing, maintenance, and operating strategies on system reliability. The course will concentrate on the application of PRA results in inspection planning, monitoring licensee performance, and reviewing licensee risk-based submittals.
Length:
14 Days 67 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Previous knowledge of nuclear power plant systems as provided in either the BWR or PWR series Applicability:
Regional and Resident inspectors or others involved in the plant inspection or review process Course Topics Introduction to PRA Concepts
= Introduction to Probability and Statistics Event Tree Concepts i
- Fault Tree Concepts
- Fault TreeEvent Tree Linking
- PRA Data 1
= Importance Measures Human Reliability Analysis Common Cause Failures Configuration Management
- Risk Based Technical Specifications Accident Precursors Shutdown Risk i
System Modeling Techniques for PRA (P-200)
Course
Description:
'This course will help develop advanced user level skills in performing event tree and fault tree analysis, with numerous practice workshops. The course covers the calculation of initiating event frequencies, component failure rate calculation, and the use of " super components" to create fault trees. A second focus of the course is dependent failure analysis, including multiple Greek letter, binomial failure rate, basic parameter methods, and alpha factor methods for estimating common cause/ common mode failure probabilities.
Length:
4 Days 28 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Fundamentals of PRA or PRA Basics for Regulatory Applications, Applying Statistics or college-level knowledge of probability and statistics, Probability and Statistics for PRA, and IRRAS Basics i
Applicability:
Any Advanced User involved in creating or modifying PRA data Course Topics f
Overview of PRA for Nuclear Power Plants j
Developing System Models Useful Results of a Risk Analysis i
Method Selection Level 1 Modeling Generating Results Validity Checks i
Limitations of Fault and Event Trees Modeling Support Systems l
Modeling Dependent Failures Alternative Common Cause Failure Models i
j Practical Issues in Treating Common Cause Failure j
Modeling Common Cause Failure in System Models I
I r
21 NUREG/BR-0228 i
Integrated Reliability and Risk Analysis System (IRRAS) Basics (P-201)
Course
Description:
This course provides hands-on training in the use of Integrated Reliability and Risk Ane. lysis System (IRRAS) to perform probabilistic risk assessment (PRA) analysis on the PC. When the course is completed, the participants are able to: build fault tree models on the PC, assign reliability data, analyze the fault trees and develop minimal cut sets, calculate various importance measures, perform uncertainty analysis, analyze accident sequences, create and quantify accident sequences, and generate reports.
Length:
4 Days 28 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Fundamentals of PRA (or PRA for Regulatory Applications) and Probability and Statistics for PRA Applicability:
PRA Advanced Users who independently develop and quantify fault and event tree models Course Topics Course Introduction IRRAS Database Concepts IRRAS Familiarization i
Event Tree Construction Fault Tree Construction Basic Event Data Entry IRRAS Graphical Output Fault Tree Minimal Cut Set Generation Fault Tree Uncertainty Analysis Importance Measures Fault Tree / Basic Event Reports Fault Tree Sensitivity Analysis Event Tree / Fault Tree Linking Accident Sequence Generation Accident Sequence Uncertainty Analysis Accident Sequence Importance Analysis Event Tree Reports Event Tree Sensitivity Analysis Recovery Actions Modeling NUREG/BR-0228 22
Advanced Integrated Reliability and Risk Analysis System (IRRAS) (P-202)
Course
Description:
This course provides hands-on training in the advanced features of Integrated Reliability and Risk Analysis System (IRRAS) to perfonn PRA analysis on the PC.
IRRAS allows the user to build and evaluate the models used in PRA. IRRAS can provide the base models to be used in sensitivity analyses using System Analysis and Risk Assessment System (SARA).
Length:
4 Days 28 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Fundamentals of PRA or PRA for Regulatory Applications, Probability and Statistics for PRA, IRRAS Basics, and System Modeling Techniques Applicability:
PRA Advanced Users who have completed the IRRAS Basics course or have an equivalent working knowledge ofIRRAS. Knowledge of PRA methodology is required for a student to reahze the full benefit of the course. The course is directed toward those who use IRRAS with existing databases for confirmatory and sensitivity analysis.
Course Topics IRRAS Database Concepts Text Editors
" Link Event Trees" Rule Editor a
Recovery Rules End State Analysis System Cut Set Generation Sequence Cut Set Generation Large Event Tree Methodology a
Event Analysis Using Change Sets Mutually Exclusive Esents Analysis a
Using the M AR-D Module Evaluating Cut Sets Using Min-Max Quantification a
Human Reliability Assessment (HRA) (P-203)
Course
Description:
This course serves as an introduction to Human Reliability Assessment (HRA) including the methods used in modeling of human errors and various methods of estimating their probabilities. This course is designed to teach introductory level skills in HRA and includes a broad introduction to HRA and its applications. A discussion of HRA strengths, limitations, and results is also included.
Length:
3 Days 21 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Fundamentals of PRA or PRA for Regulatory Applications Applicability:
Advanced Users with a interest in learning basic HRA techniques and concepts Course Topics Integration of HRA with Other PRA Activities The Nature of Human Error a
HRA Data Collection HRA Model Building Techniques Introduction to HRA Methods j
HRA Model Quantification l
NUREG/BR-0228 24 3
-.e
External Events (P 204)
Course
Description:
This three day course deals with the analysis of external events such as fires, floods, earthquakes, high winds, and transportation accidents. The course has been l
developed to provide the student with information that can be used in the review of IPEEE results.
Length:
3 Days 21 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Advanced User knowledge of PRA Level 1 Applicability:
Any NRC employee with a need to understand external event modeling and the effects of external events on plant risk Course Topics History of External Events PRA Prior to GL 88-20 Genesis of the IPEEE Supplement to GL 88-20 Requirements of the IPEEEs and Ways in which these Requirements Can Be Met Overview of the EPRI CDFM Method and Seismic PRA Overview of the EPRI FIVE Method for Fire Analysis Overview of Flood and Fire PRAs, including Use of Location Transformations To Obtain Zone Cut Sets, Compare and Coritrast with Internal Events PRA Methods Databases for External Events Analysis (e.g., Fire Frequencies, Component Seismic Fragilities)
Areas of Current Research 25 NUREG/BR-0228
Accident Progression Analysis (P-300)
Course
Description:
This course deals with the portion of probabilistic risk assessment typically referred to as Level 2 analysis. The course will address accident phenomenology under post-core damage conditions and will discuss development of PRA models for this severe accident regime. The emphasis of the course is on the important modeling issues and how they are dealt with, rather than how to use specific modeling software.
Length:
3 Days 21 Instructional Hours i
Examination:
Written Comprehensive Final Examination Prerequisites:
PRA Basics for Regulatory Applications and Probability and Statistics for PRA Applicability:
Any NRC employee involved in Level 2 PRA analysis Course Topics Design Basis Accidents Extension to Beyond Design Basis Accidents j
Review of PRA Methods l
Containment Event Tree Construction and Quantification In-vessel Accident Progression In-containment Accident Progression Radionuclide Release and Transport Accident Progression Analysis Codes Extended Burnup Fuel Behavior Direct Containment Heating Core Reflood and Debris Coolability Steam Generator Tube Degradation Workshop 1
NUREG/BR-0228 26 j
l
Accident Consequence Analysis (P-301)
Course
Description:
This course deals with the portion of PRA typically referred to as Level 3 analysis. The course addresses environmental transpon of radio nuclides and the estimation of offsite consequences from core damage accidents. The emphasis of the course is on important modeling issues and how they are dealt with, rather than how to use specific modeling software.
Length:
3 Days 21 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
PRA Basics for Regulatory Applications Applicability:
Any NRC employee involved in Level 3 PRA analysis Course Topics Purpose and Scope of Analysis History of Consequence Analysis for Nuclear Reactors Interface with Level 2 Analysis Atmospheric Dispersion Dose Pathways to Man
=
Protective Measures to Reduce Doses Health Effects and Health Effects Models Economic Consequences Overview of MACCS and Other Codes Uncertainty and Sensitivity Analysis Verification and Validation Activities Ongoing Research and Development 27 NUREG/BR-0228 l
Risk Assessment in Event Evaluation (P-302)
Course
Description:
This course covers the use of PRA techniques to assess the risk significance of initiating events and condition assessments that occur at operating reactors. The course addresses the use of simplified PRA models to estimate conditional damage probability using the Graphical Evaluation Module (GEM) of the SAPHIRE suite of programs. In addition, common cause and non-recovery probabilities will also be addressed. The course includes conventional workshops and GEM program workshops.
Length:
3 Days 21 Instructional Hours Examination:
Written Comprehensive Final Examination Prerequisites:
Fundamentals of PRA or PRA Basics for Regulatory Applications, Applying Statistics or college-level knowledge of probability and statistics, Probability and Statistics for PRA, IRRAS Basics, System Modeling Techniques, Advanced IRRAS, and Human Reliability Assessment Applicability:
Any Advanced User involved in event evaluation or plant condition assessments Course Topics PRA Models for Event Assessment Risk Measures for Event Assessment Initiating Event Assessments Condition Assessments Treatment of Common Cause Events Treatment of Recovery Events Overview of GEM Module GEM Database Concepts Processing Initiating Events with GEM Processing Condition Assessments with GEM Uncertainty Analysis Displaying and Interpreting Results l
NUREG/BR-0228 28 1
t
Printed on recycled paper Federal Recycling Program
UNITED STATES NUCLEAR REGULATORY COMMISSION POSTAGE FEE PM WASHINGTON, DC 20555-0001 USNRC PEFMT NO. G47.'
OFFCAL BUSINESS PENALTY FOR PRfVATE USE, $300 120555139531 1 laOlcL US NPC-0ACP DIV FOIA & DUBLICATIONS SVCS TPS-POD-NUREG 2WFN-6E7 WASHINGTON DC 20555
/
_ _. -