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Hazards And Accident Analysis To Meet Non Reactor Nuclear Facility Safety Analysis Requirements
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Book Synopsis Hazards and Accident Analysis to Meet Non-reactor Nuclear Facility Safety Analysis Requirements by : Los Alamos National Laboratory
Download or read book Hazards and Accident Analysis to Meet Non-reactor Nuclear Facility Safety Analysis Requirements written by Los Alamos National Laboratory and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A DOE-STD-3009 Hazard and Accident Analysis Methodology for Non-reactor Nuclear Facilities by :
Download or read book A DOE-STD-3009 Hazard and Accident Analysis Methodology for Non-reactor Nuclear Facilities written by and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper demonstrates the use of appropriate consequence evaluation criteria in conjunction with generic likelihood of occurrence data to produce consistent hazard analysis results for nonreactor nuclear facility Safety Analysis Reports (SAR). An additional objective is to demonstrate the use of generic likelihood of occurrence data as a means for deriving defendable accident sequence frequencies, thereby enabling the screening of potentially incredible events (
Author :American Nuclear Society. Standards Committee Working Group ANS-58.16 Publisher : ISBN 13 : Total Pages : pages Book Rating :4.:/5 (119 download)
Book Synopsis American National Standard by : American Nuclear Society. Standards Committee Working Group ANS-58.16
Download or read book American National Standard written by American Nuclear Society. Standards Committee Working Group ANS-58.16 and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This standard specifies criteria for categorization of SSCs and SACs that have a safety function based on radiological and/or chemical dose and exposure levels for the public and workers. The safety categorization leads to codes and standards that are needed for reliable design, construction, and operations commesurate with the safety categorization. The purpose of this standard is: Specify criteria for categorization of safety SSCs; Select industry codes and standards for reliable design, construction, and operations commesurate with the safety organization. To meet these objectives, the standard specifies the requirements in the following steps: identification of hazards; evaluation of hazards; selection of DBEs; unmitigated accident analysis of DBEs; identification of safety functions and categorizations; selection of safety SSCs to fulfill safety function requirements; evaluation, selection, and implmementation of applicable industry codes and standards to ensure safety SSCs are designed, constructed, and maintained to fulfill the intended safety functions.
Book Synopsis Risk and Safety Analysis of Nuclear Systems by : John C. Lee
Download or read book Risk and Safety Analysis of Nuclear Systems written by John C. Lee and published by John Wiley & Sons. This book was released on 2012-01-12 with total page 504 pages. Available in PDF, EPUB and Kindle. Book excerpt: The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems. The second half of the book covers the safety analysis of nuclear energy systems, an analysis of major accidents and incidents that occurred in commercial nuclear plants, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical PRA examples, and emerging techniques in the structure of dynamic event trees and fault trees that can provide a more realistic representation of complex sequences of events. The book concludes with a discussion on passive safety features of advanced nuclear energy systems under development and approaches taken for risk-informed regulations for nuclear plants.
Book Synopsis Guidance for Safety Analysis of Other Than Nuclear Facilities/Activities at the INEEL. by :
Download or read book Guidance for Safety Analysis of Other Than Nuclear Facilities/Activities at the INEEL. written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy Idaho Operations Office (DOE-ID) provided guidance per DOE-ID Orders 420.C, "Safety Basis Review and Approval Process," and 420.D, "Requirements and Guidance for Safety Analysis," for conducting safety analysis for facilities and activities that do not meet either the nuclear facility criteria or the criteria for not requiring additional safety analysis (NRASA). These facilities and activities are thus designated as "other than nuclear" (OTN), and hazard analyses are performed using a graded approach. This graded approach is done in accordance with DOE-ID Order 420.D. DOE-ID guidance is used to format these OTN facilities and activities into 3-chapter documents, rather than the 17-chapter format specified in DOE-STD-3009-94, "Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports."
Book Synopsis Format and Content of the Safety Analysis Report for Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Format and Content of the Safety Analysis Report for Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2004 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide is intended primarily for use with land based stationary thermal nuclear power plants but it may, in parts, have a wider applicability to other nuclear facilities. It provides recommendations and guidance on the possible format and content of a SAR in support of a request to the State regulatory body for authorization to construct and or operate a nuclear power plant. As such, it contains recommendations on meeting the requirements of Safety guide GS-R-1 "Legal and governmental infrastructure for nuclear, radioactive waste and transport safety" (2000, ISBN 9201008007)
Book Synopsis Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade by : R. T. McCracken
Download or read book Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade written by R. T. McCracken and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The regulatory requirement to develop an upgraded safety basis for a DOE nuclear facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830).1 Subpart B of 10 CFR 830, "Safety Basis Requirements," requires acontractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements.110 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants"2 as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology thatwas developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.
Book Synopsis Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports by :
Download or read book Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports written by and published by . This book was released on 1992 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this DOE Standard is to establish guidance for facility managers and Program Secretarial Officers (PSOs) and thereby help them to comply consistently and more efficiently with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports. To this end, this guidance provides the following practical information: (1) The threshold quantities of radiological material inventory below which compliance with DOE Order 5480.23 is not required. (2) The level of effort to develop the program plan and schedule required in Section 9.b. (2) of the Order, and information for making a preliminary assessment of facility hazards. (3) A uniform methodology for hazard categorization under the Order. (4) Insight into the ''graded approach'' for SAR development, especially in hazard assessment and accident analysis techniques. Individual PSOs may develop additional guidance addressing safety requirements for facilities which fall below the threshold quantities specified in this document.
Book Synopsis Calculational Framework for Safety Analyses of Non-reactor Nuclear Facilities by :
Download or read book Calculational Framework for Safety Analyses of Non-reactor Nuclear Facilities written by and published by . This book was released on 1994 with total page 116 pages. Available in PDF, EPUB and Kindle. Book excerpt: A calculational framework for the consequences analysis of non-reactor nuclear facilities is presented. The analysis framework starts with accident scenarios which are developed through a traditional hazard analysis and continues with a probabilistic framework for the consequences analysis. The framework encourages the use of response continua derived from engineering judgment and traditional deterministic engineering analyses. The general approach consists of dividing the overall problem into a series of interrelated analysis cells and then devising Markov chain like probability transition matrices for each of the cells. An advantage of this division of the problem is that intermediate output (as probability state vectors) are generated at each calculational interface. The series of analyses when combined yield risk analysis output. The analysis approach is illustrated through application to two non-reactor nuclear analyses: the Ulysses Space Mission, and a hydrogen burn in the Hanford waste storage tanks.
Book Synopsis Safety Analysis Report Upgrade Program at the Plutonium Facility, Los Alamos National Laboratory by :
Download or read book Safety Analysis Report Upgrade Program at the Plutonium Facility, Los Alamos National Laboratory written by and published by . This book was released on 1993 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements.
Book Synopsis Safety of Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Safety of Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.
Book Synopsis Hazard Analysis for 300 Area N Reactor Fuel Fabrication and Storage Facilty by :
Download or read book Hazard Analysis for 300 Area N Reactor Fuel Fabrication and Storage Facilty written by and published by . This book was released on 1994 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt: This hazard analysis (HA) has been prepared for the 300 Area N Reactor Fuel Fabrication and Storage Facility (Facility), in compliance with the requirements of Westinghouse Hanford Company (Westinghouse Hanford) controlled manual WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual, and to the direction of WHC-IP-0690, Safety Analysis and Regulation Desk Instructions, (WHC 1992). An HA identifies potentially hazardous conditions in a facility and the associated potential accident scenarios. Unlike the Facility hazard classification documented in WHC-SD-NR-HC-004, Hazard Classification for 300 Area N Reactor Fuel Fabrication and Storage Facility, (Huang 1993), which is based on unmitigated consequences, credit is taken in an HA for administrative controls or engineered safety features planned or in place. The HA is the foundation for the accident analysis. The significant event scenarios identified by this HA will be further evaluated in a subsequent accident analysis.
Book Synopsis Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities by :
Download or read book Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.
Book Synopsis Overall Risk Estimation for Nonreactor Nuclear Facilities and Implementation of Safety Goals by :
Download or read book Overall Risk Estimation for Nonreactor Nuclear Facilities and Implementation of Safety Goals written by and published by . This book was released on 1993 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: A typical safety analysis report (SAR) contains estimated frequencies.and consequences of various design basis accidents (DBA). However, the results are organized and presented in such a way that they are not conducive for summing up with mathematical rigor to express total or overall risk. This paper describes a mathematical formalism for deriving total risk indicators. The mathematical formalism is based on the complementary cumulative distribution function (CCDF) or exceedance probability of radioactivity release fraction and individual radiation dose. A simple protocol is presented for establishing exceedance probabilities from the results of DBA analyses typically available from an SAR. The exceedance probability of release fraction can be a useful indicator for gaining insights into the capability of confinement barriers, characteristics of source terms, and scope of the SAR. Fatality risks comparable to the DOE Safety Goals can be derived from the exceedance probability of individual doses. Example case analyses are presented to illustrate the use of the proposed protocol and mathematical formalism. The methodology is finally applied to proposed risk guidelines for individual accident events to show that these guidelines would be within the DOE Safety Goals.
Book Synopsis Probabilistic Safety Assessment in the Chemical and Nuclear Industries by : Ralph Fullwood
Download or read book Probabilistic Safety Assessment in the Chemical and Nuclear Industries written by Ralph Fullwood and published by Butterworth-Heinemann. This book was released on 2000 with total page 554 pages. Available in PDF, EPUB and Kindle. Book excerpt: In addition to presenting methodology, it shows how to identify accident vulnerability in the two industries. It reviews the causes of the two major nuclear accidents and many fatal accidents in the chemical industry, including Bhopal. Many examples of applications of PSA to both industries are presented."--BOOK JACKET. "Problems are included at the end of many chapters with answers at the back of the book."--Jacket.
Book Synopsis Process Hazards Analysis (PrHA) Program, Bridging Accident Analyses and Operational Safety by :
Download or read book Process Hazards Analysis (PrHA) Program, Bridging Accident Analyses and Operational Safety written by and published by . This book was released on 2003 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker safety are incorporated so the worker can readily identify the safety parameters of the their work. System safety tools such as Preliminary Hazard Analysis, What-If Analysis, Hazard and Operability Analysis as well as other techniques as necessary provide the groundwork for both determining bounding conditions for facility safety, operational safety, and day-to-clay worker safety.
Book Synopsis Basic Safety Principles for Nuclear Power Plants by : International Nuclear Safety Advisory Group
Download or read book Basic Safety Principles for Nuclear Power Plants written by International Nuclear Safety Advisory Group and published by . This book was released on 1999 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.
