DOE Safety Basis - Home (2024)

SBA-100DE, Nuclear Facility Safety Basis Fundamentals

This eLearning course familiarizes students with safety basis fundamentals. Upon completion of this course, students will have gained an overall understanding of the process of establishing and maintaining a safety basis for DOE nuclear facilities as dictated by 10 CFR 830 Subpart B, Safety Basis Requirements. Safety basis means the documented safety analysis and hazard controls that provide reasonable assurance that a DOE nuclear facility can be operated safely in a manner that adequately protects workers, the public, and the environment. (10 CFR 830)

SBA-110DE, Documented Safety Analysis Safe Harbors

This eLearning course provides students with the fundamental knowledge associated with selecting a documented safety analysis (DSA) that meets one of the methodologies called "safe harbors" set forth in Table 2 of Appendix A of 10 CFR 830 Subpart B, Safety Basis Requirements. Upon completion of this course, students will be able to identify the safe harbor needed to create a DSA based on specific facility types.

SBA-120DE, Hazard Identification, Categorization, and Evaluation Fundamentals

This eLearning course provide students with the fundamental knowledge of hazard identification, categorization, and evaluations as part of DSA development and review that meets 10 CFR 830 Subpart B and the safe harbor DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis. Upon completion of this course, students will be able to identify the processes and requirements associated with identifying, categorizing, and evaluating hazards for DOE nuclear facilities.

SBA-130DE Accident Analysis and Control Selection

This eLearning course provides students with the fundamental knowledge of performing and reviewing accident analysis and control selection as part of DSA development and review that meets 10 CFR 830 Subpart B and the safe harbor DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis. Upon completion of this course, students will be able to identify the processes and requirements associated with accident analysis, control selection, derivation of TSRs, and evaluation of beyond design basis accidents.

SBA-140DE Safety Design Basis Document Development

This eLearning course provides students with the fundamental knowledge of requirements and responsibilities for safety design basis document development as applied to the design and construction of new DOE nuclear facilities and major modifications to DOE nuclear facilities. Upon completion of this course, students will be able to identify the requirements and guidance provided in DOE-STD-1189-2016, Integration of Safety into the Design Process.

SBA-150DE Technical Safety Requirements (TSR) Development

This eLearning course provides students with the fundamental knowledge of requirements for the development and review of TSRs for DOE nuclear facilities that meet 10 CFR 830 Subpart B and DOE G 423.1-1B, Implementation Guide for Use in Developing Technical Safety Requirements. Upon completion of this course, students will be able to identify the purpose and scope of TSRs, relationship to the DSA, TSR organization (e.g., safety limits, limiting control settings, limiting conditions of operation, etc.), and violations of TSRs.

SBA-160DE Unreviewed Safety Question (USQ) Process Development

The eLearning course provides students with the fundamental knowledge of requirements for the development and implementation of the USQ Process for DOE nuclear facilities that meet 10 CFR 830 Subpart B and DOE G 424.1-1B, Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements. Upon completion of this course, students will be able to identify the requirements and processes associated with conducting reviews of contractor USQ procedures, USQ determinations, potential inadequacies of the safety analysis (PISAs), justification for continued operation (JCO), and evaluation of the safety of the situation (ESS).

SBA-170DE Safety Evaluation Report (SER) and Safety Review Letter (SRL) Development

The eLearning course provides students with the fundamental knowledge of requirements for the development of SERs or SRLs that meet DOE-STD-1104-2016, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents. Upon completion of this course, students will be able to identify the processes and requirements for the review and approval of DSAs, TSRs, safety basis related documents (e.g., JCO and ESS), and safety design basis documents.

SBA-220, Hazard Identification, Categorization, and Evaluation Review

This course provides the student with the tools to review and determine the adequacy of a hazard analysis (including hazard identification, hazard categorization, and hazard evaluation) for a DOE Hazard Category 1, 2, or 3 nuclear facility as documented in a Documented Safety Analysis (DSA). The students will learn and apply DOE policy in accordance with 10 CFR-830.204, Nuclear Safety Management, and best practices derived from DOE-STD-1027-2018, Hazard Categorization of DOE Nuclear Facilities, and DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis.

DOE Safety Basis - Home (1)

SBA-230, Accident Analysis and Control Selection Review

This instructor-led course leads students through the mandatory performance activities (MPAs) associated with performance competencies 3 and 4 identified in DOE-STD-1183-2016, Nuclear Safety Specialist Functional Area Qualification Standard. Performance competency 3 is stated as: "Nuclear Safety Specialists shall conduct reviews of accident analysis for DOE Hazard Category 1, 2, or 3 nuclear facilities that support DOE approval as required by 10 CFR 830 Subpart B, Safety Basis Requirements." Performance competency 4 is states as: "Nuclear Safety Specialists shall conduct reviews of safety control selection, classification, and description for DOE Hazard Category 1, 2, or 3 nuclear facilities that support DOE approval as required by 10 CFR 830 Subpart B, Safety Basis Requirements." Students will be expected to review the accident analysis and control selection as part of the DSA for the NTC Synergy Basis Site, identify deficiencies/issues, and document comments that include the identification of the safety significance of the comment.

SBA-240, Technical Safety Requirements Review and Approval

This course provides the student with the tools to review and determine the adequacy of the TSRs developed for a DOE Hazard Category 1, 2, or 3 nuclear facility as documented in a Documented Safety Analysis (DSA).

SBA-250, USQ Process Implementation Review

This instructor-led course leads students through the mandatory performance activities (MPAs) associated with performance competency 6 identified in DOE-STD-1183-2016, Nuclear Safety Specialist Functional Area Qualification Standard. Performance competency 6 is stated as: "Nuclear Safety Specialists shall conduct reviews of a contractor Unreviewed Safety Question (USQ) procedure, USQ Determinations (USQDs), Potential Inadequacy of the Safety Analysis (PISAs), Justification for Continued Operations (JCOs), and Evaluation of the Safety of the Situation (ESSs).

SBA-260, New Facility Safety Design Basis Document Review

This instructor-led course leads students through the mandatory performance activities (MPAs) associated with performance competency 7 identified in DOE-STD-1183-2016, Nuclear Safety Specialist Functional Area Qualification Standard. Performance competency 7 is stated as: "Nuclear Safety Specialists shall conduct reviews of safety design basis documents for new DOE Hazard Category 1, 2, or 3 nuclear facilities, or major modifications that support DOE approval as required by 10 CFR 830 Subpart B, Safety Basis Requirements" and DOE-STD-1189-2018, Integration of Safety into the Design Process.

DOE Safety Basis - Home (2024)

FAQs

What are the safety basis requirements for 10 CFR 830 nuclear safety management subpart B? ›

The safety basis requirements of Part 830 require the contractor responsible for a DOE nuclear facility to analyze the facility, the work to be performed, and the associated hazards and to identify the conditions, safe boundaries, and hazard controls necessary to protect workers, the public and the environment from ...

What is the difference between safety class and safety significant? ›

Risk-Informed Safety Class (RISC)–4 structures, systems and components (SSCs) means non-safety-related SSCs that perform low safety significant functions. Safety significant function means a function whose degradation or loss could result in a significant adverse effect on defense-in-depth, safety margin, or risk.

What is the DOE standard review plan? ›

The SRP has been developed as a collaborative effort between EM and the Chief of Nuclear Safety (CNS), Office of the Under Secretary. It is modeled after similar principles used extensively and successfully by the Nuclear Regulatory Commission (NRC) for evaluating U.S. commercial nuclear industry licensed activities.

What is a category 1 nuclear facility? ›

The NRC groups special nuclear materials and the facilities that possess them into three categories based upon the materials' potential for use in nuclear weapons or their “strategic significance”: Category I: High strategic significance. Category II: Moderate strategic significance.

What is the DOE PISA process? ›

Purpose of PISA Process

The purpose of the PISA process is to evaluate situations where it is discovered that the existing configuration of the facility may be different from that described in the safety basis.

What is 10 CFR part 71? ›

10 CFR Part 71 - PART 71—PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL. Authority: Atomic Energy Act of 1954, secs. 53, 57, 62, 63, 81, 161, 182, 183, 223, 234, 1701 (42 U.S.C.

What do you mean by safety first class? ›

Safety 1st is a slogan that means it's always best to avoid unnecessary risks. It sounds like an easy task, but sometimes we so hurry in making deadlines and meeting the goals that we forget about the safety of ourselves and others. We encourage you to remember this slogan because it can ultimately save lives!

What is the definition of safety significant? ›

Safety-significant structures, systems, and components means the structures, systems, and components which are not designated as safety-class structures, systems, and components, but whose preventive or mitigative function is a major contributor to defense-in-depth and/or worker safety as determined from safety ...

How many different types of safety are there? ›

By focusing on environmental, physical, health and biological, psychological, and cyber safety, businesses can establish a safe environment for employees and customers. From protection against hazards in the workplace to psychological and emotional well-being, all aspects of safety are crucial.

What are DOE standards? ›

DOE standards provide specific standardized approaches, methodologies, technical criteria, or other information on accomplishing a task, developing a plan, and/or performing a calculation or assessment to implement a DOE requirement.

How often does the DOE review efficiency standards? ›

The agency's Appliance and Equipment Standards Program reviews energy efficiency rules for a broad range of products every six years.

What is the DOE operational readiness review? ›

A disciplined, systematic, documented, performance-based examination of facilities, equipment, personnel, procedures and management control systems for ensuring that a facility can be operated safely within its approved safety envelope as defined by the facility safety basis plan.

What is a Level 7 nuclear accident? ›

Level 7. (major accident): • Significant release of the radioactive. material to the environment. resulting in widespread health and.

What is a hazard Category 1 2 or 3 DOE nuclear facility? ›

Category 1 Hazard: The Hazard Analysis shows the potential for significant off-site consequences. Category 2 Hazard: The Hazard Analysis shows the potential for significant on-site consequences. Category 3 Hazard: The Hazard Analysis shows the potential for only significant localized consequences.

What is a Category 2 facility? ›

Category II facilities are licensed to possess SNM of moderate strategic significance as defined in 10 CFR 70.4 and 73.2. These facilities include HALEU fuel cycle facilities (e.g., uranium enrichment plants and fuel fabrication facilities), non-power reactors, and medical isotope facilities.

What is 10 cfr 835? ›

The occupational radiation protection program is governed by the Rule, specified as 10 CFR 835. The requirements given in 10 CFR 835 are matters of law, punishable by civil and criminal penalties.

What is a DOE nuclear facility? ›

Definition. A Department of Energy reactor or nonreactor nuclear facility where an activity is conducted for, or on behalf of, DOE, including any related area, structure, facility, or activity to the extent necessary to ensure proper implementation of the requirements established in 10. C.F.R.

Which federal regulation requires a written radiation protection program? ›

The statutes are found in the Health and Safety Code, Division 104-Environmental Health.

What is a DOE order? ›

The Order provides DOE and NNSA with program and project management direction for the acquisition of capital assets with the goal of delivering projects within the original performance baseline (PB), cost and schedule, and fully capable of meeting mission performance, safeguards and security, and environmental, safety, ...

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