Training Courses
The workshop will offer a number of training sessions designed to help safety professionals work efficiently and effectively in managing risks and promoting safety within their organizations.
Analytical Modeling Techniques Overview
Saturday and Sunday, 8 am to 5 pm
| Ray Sartor, LANL sartor@lanl.gov 505-665-3166 |
Don Siebe, LANL dsiebe@lanl.gov 505-665-3166 |
J.C. Laul, LANL jclaul@lanl.gov 505-665-9791 |
The Analytical Modeling Techniques Overview course is designed to familiarize Safety Analysts with selected analytical modeling codes (DOE Toolbox Codes) used in accident analyses in support of DOE facility safety basis document development. Upon completion of the course, participants will be able to: (1) describe the purpose of analytical modeling in accident analysis, (2) describe the types of design basis accidents each Toolbox code is best suited to model, (3) describe major strengths and limitations of each analytical modeling in the DOE Safety Analysis Toolbox, and (4) recommend the most appropriate analytical code(s) to model selected DOE facility design basis accidents (DBAs). This is a 2-day course.
Hazard Evaluation Techniques II
Saturday & Sunday, 8 am to 5 pm and
Monday, 8 am to 12 pm
| James Kuropatwinski, LANL wujek@lanl.gov 505-606-0473 |
John Farquharson, ABS Consulting jfarqufarson@absconsulting.com 865-671-5807 (Knoxville office) 865-241-5233 (Oakridge office) |
The Hazard Evaluation Techniques II course focuses on hazard evaluation techniques normally used in special situations requiring detailed analysis of one or more specific hazardous situations of concern. The four techniques covered require specially trained and skilled practitioners. These techniques should only be used on tightly focused problems since they require significantly more time and effort to perform than do the more broad-brush approaches. Techniques covered include: (1) Fault Tree Analysis, (2) Event Tree Analysis, (3) Hazard and Barrier Analysis, and (4) Human Reliability Analysis. Course provides working knowledge and skills needed to perform a comprehensive assessment of facility hazards and to provide a risk perspective to help in decision making for risk reduction. These evaluation techniques may be used to perform hazard analyses at a DOE facility.
This will be condensed into a 2-day course.
Controls
Saturday 8 am to 5 pm
Jim McCormick – WSMS • Jim.McCormick@wsms.com
865-765-0881
The course will discuss how controls are derived from a hazards and/or accident analysis and how that information is used to form facility-specific Technical Safety Requirements (TSR) controls. The course will be based on information found in 1) DOE Standard 1186–2004, Specific Administrative Controls; 2) DOE Guide 423.1–1, Implementation Guide for Use in Developing Technical Safety Requirements; 3) the 10 CFR 830 Rule, Nuclear Safety Management; 4) DOE–STD–3009–94, Preparation Guide for DOE Nonreactor Nuclear Facility Safety Analysis Reports; 5) DOE–STD–1189–2008 Integration of Safety into the Design Process and other pertinent DOE requirements. The course is designed to address general DOE TSR facility situations however during the course open-floor discussions will be invited as well as facility-specific situations. It is important that participants have an understanding of their site-specific TSRs so their situations can be addressed during this course.
1186
Sunday, 8 am to 5 pm
John Rice – Epsilon Systems Solutions
jrice@epsilonsystems.com or jwrice@srv.net
208-522-3661
This course is intended to be a follow-on class to the initial basic training on Specific Administrative Controls (SACs); however, enough of the key materials from the initial course are reviewed such that an individual new to the topic can easily participate. The course reviews the key elements of the DOE guidance and expectations in DOE-STD-1186-2004, Specific Administrative Controls, and clarifies and focuses on the implementation of this guidance in conjunction with the general requirements and guidance for developing safety basis documents contained in 10 CFR 830 and its implementation guides. The course presents lessons learned from several sites across the DOE complex in implementing DOE-STD-1186-2004 and suggests potential solutions to general problem areas. The students will review a number of examples of SACs and prepare several SACs during the class exercises.
USQ Refresher Course
Sunday, 8 am to 5 pm
Mark Mitchell – Lawrence Livermore
National Laboratory
Mitchell36@llnl.gov •
925-422-8600
This course is a one-day refresher on the Unreviewed Safety Question (USQ) process. The class focuses on the requirements and guidelines for implementing the USQ process for nuclear facilities/activities, and shares lessons learned from across the DOE Complex. This class is for individuals who have already completed initial USQ training and have experience with the USQ process, although individuals with an interest in learning more about the USQ process are also welcome to attend.
10 CFR 830.203, "Unreviewed Safety Question Process," allows contractors to make physical or procedural changes and to conduct tests and experiments without prior DOE approval if the proposed activity can be accommodated within the existing DOE-approved safety basis. Each site's USQ procedure provides requirements and guidelines for implementing the USQ process at nuclear facilities. It thus establishes the mechanism to determine who has the authority to approve a change: the Department of Energy (DOE) or the contractor.
Topics include:
- Key components of the general USQ process
- 10 CFR 830.203
- DOE G 424.1-1A
- Site USQ procedures
- Definitions
- Scope
- Categorical Exclusions
- Screening
- USQ Determinations (USQD)
- PISA Process
- Logistical issues (e.g., submittal of annual USQD summaries)
- Lessons learned
Credit: The EFCOG USQ refresher training may count towards meeting your contractor's requirements for refresher training. Upon completion of the test, a signed certificate will be provided. Check with your contractor's Safety Basis management for more information.
RISK
Monday, 8 am to 12 pm
John Farquharson - ABS Consulting Inc.
www.absconsulting.com •
865-671-5807
The Risk Analysis Fundamentals course will present basis frequency analysis techniques, including fault tree and event tree analysis. Trainees will learn to identify the systems, subsystems, and components that contribute most to loss exposure. The course will provide the skills needed for making more precise judgments than can be made with qualitative tools alone. Previous experience with probability theory or statistics is helpful but not required. Attendees should bring a scientific calculator to the course.
RSAC 7
Monday, 8 am to 12 pm
Dr. Bradley Schrader, Idaho National Laboratory
Bradley.Schrader@inl.gov •
208-526-0912
The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version in RSAC legacy. RSAC 7 combines a user friendly interface with a powerful analysis tool. It calculates the dose consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC 7 includes the dose conversion factors from ICRP 68 and ICRP 72. In addition, it includes the analysis tool for generation of 24 hour acute organ dose. Joint frequency meteorological analysis combined with a summary of 50% and 95% conditions allows for an easy check or analysis of the sensitivity of conditions met.
RSAC-7 is fully verified and validated in accordance with NQA-1 2000 for Quality Level 1 applications. It has been proposed for inclusion in the Safety Software Toolbox. RSAC-7 can be used either as the primary or secondary dose consequence analysis tool. Participants need to bring a laptop computer.
1189
Monday, 8 am – 5 pm
Brad Evans, Pacific Northwest National Laboratory
Brad.evans@pnl.gov •
509-376-4447
Bob Lowrie Washington, Safety Management Solutions
Bob.Lowrie@wsms.com • 803.215.4555
Richard Englehart, Longenecker & Associates
trahelgne_east@verizon.net • 301.975.9684
Integration of safety into design has become a hot topic within DOE and the DNFSB. To address the underlying issues, DOE has rolled out a new technical standard, DOE-STD-1189, “Integration of Safety into the Design Process.” This course presents highlights of the Standard integrated with the standard project development process as defined by DOE O 413.3A, “Program and Project Management for the Acquisition of Capital Assets.” The course will provide trainees with a fundamental understanding of both the project process (for development of nuclear facilities) and the safety analysis activities, products, and issues that support the process.
