PREPARATION OF THE SAFETY ANALYSIS REPORT

Safety Series No. 35-GI Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report (1994). 

AR21 Safety assessment of research reactors and preparation of the safety analysis report, 35-Gl,... 

SAFETY ASSESSMENT OF RESEARCH REACTORS AND PREPARATION OF THE SAFETY ANALYSIS REPORT... 

For the design and licensing reguirement, the INET had prepared the technical documents which are the design criteria of the HTR-10 and the format and content of the safety analysis report of the HTR-10. These two documents were examined and approved by the NNSA in August 1992 and March 1993 respectively. 

Several summary tables are commonly presented to report safety data. Two examples of typical formats are provided here. Table 10.3 shows the format for the overall summary of adverse events falling within several adverse event categories. Such table shells are typically prepared by medical writers in advance of the study results being available and are based on the clinical study protocol and/or the statistical analysis plan written before the study started. Preparation in advance of the availability of the data saves time during the preparation of the clinical study report once the data are available. 

These topics are the subject of DOE Standard DOE-STD-1027-92, "Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23 Nuclear Safety Analysis Reports," which provides guidance for facility managers and Cognizant Secretarial Offices (CSOs). They are also discussed in the DOE Standard DOE-STD-3009-94, "Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports," which describes a SAR preparation method that is acceptable to DOE. 

Software safety analysis reports are prepared by the software safety engineers of software design team based on IEEE 1228-1994 standard requirements in each software development phase. These reports are reviewed by the IV V teams. 

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. 

DOE Standard 3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, describes a Safety Analysis Report (SAR) preparation method that is acceptable to the DOE (DOE 1994b). 

The MORT tools and techniques can be helpful in preparing a safety analysis report (SAR), the upstream safety product most frequently required for new DOE programs, but the more common system safety products (system safety program plan, preliminary hazard analysis, system/subsystem hazard analysis, operating hazard analysis) are not a dominant part of the MORT program and are seldom even referenced in System Safety Development Center (SSDC) documents. 

A change analysis report is prepared at any time during the life cycle when a change is made to a design, drawing, component, subsystem, or any other part of the project after the safety analysis of that particular part of the project is complete. 

An accident analysis report may be prepared by the system safety working group and/or an independent accident investigation board. The recommended method for serious accidents is for the SSWG to prepare an accident analysis report based on its own investigation and upon the findings of the traditional accident report prepared by the accident investigation board. 

Safety analysis report (SAR) A document prepared to document the results of a hazard analysis performed on a system, subsystem or operation. Hie specific minimum data elements for an SAR will be defined by data deliverable requirements for the program or project (NSTS 22254). 

This phase is to comprise detailed analysis and design of the individual systems, components and buildings. A non-site-specific safety analysis report is also to be prepared. The basic design phase is planned to be completed by the beginning of 1997. 

After the construction permit is issued, the applicant must, if it did not as part of the original application, submit a final safety analysis report (FSAR) to support its application for an OL. The FSAR describes the final design of the plant and its operating and emergency procedures. The NRC prepares a final SER for the OL, and also the ACRS makes an independent evaluation and presents its findings and recommendations to the NRC. 

In the late 1980s, DOE initiated tasks to provide new DOE orders that addressed nuclear safety documents and nuclear criticality safety. These documents were necessary to establish DOE nuclear safety policy and requirements in anticipation of the change to a regulated process. In 1991-1992, the DOE issued four DOE orders that defined the requirements for preparing Unreviewed Safety Questions (USQs) (DOE Order 5480.21), TSRs (DOE Order 5480.22), Safety Analysis Reports (DOE Order 5480.23), and Nuclear Criticality Safety (DOE Order 5480.24). They were used for the specification of nuclear safety requirements and used in conjunction with 10 CFR, Part 830 (10 CFR 830), Subpart A—Quality Assurance (QA) Requirements—for enforcement action under the PAAA regulatory process. These orders were deactivated on the issuance of 10 CFR 830, Subpart B—Safety Basis Requirements—and replaced by DOE guides. 

A Safety analysis report for the nuclear facility that considers the generic nuclear explosive operations and is prepared in accordance with DOE-STD-3009, Change Notice No. 1, January 2000, or successor document, and A Hazard Analysis Report for the specific nudear explosive operations prepared in accordance with DOE-STD-3016-99, Hazards Analysis Reports for Nuclear Explosive Operations, February 1999, or successor document. Using the methods in Chapters 2-5 of DOE-STD-3009, Change Notice No. 1, January 2000 ... 

As stated in DOE-STD-3009-94, a preparation guide for U.S. DOE Nonreactor Documented Safety Analysis reports, "It is not the intention of the DSA to cover safety as it relates to the common industrial hazards that make up a large portion of basic OSHA regulatory compliance." Therefore, in the context of 10 CFR 830, Subpart B requirements, the scope of HAZWOPER is taken to include those hazards, associated controls, and safety and health (S H) programs that must be identified and maintained within a Hazard Category 1, 2, or 3 facility s safety basis. 

In the case of an SMPR project it is necessary to review in more detail phases A and B. In the precontractual activities, the model schedule assumes a letter of intent and the submission of a preliminary safety analysis report (PSAR) to obtain the construction license as a pre-requisite to the final contract signature. Depending upon the state of readiness of an SMPR design this may or may not be possible to perform within the one year shown, and it could in some cases extend up to five years, i.e. until the supplier has been selected, the PSAR has been prepared and the construction licence given. 

First developed for the nuclear and aerospace industries. Safety Cases can be used in any activity or industry that poses high risk to workers or the community. One of the first examples was in the United Kingdom where the Nuclear Installations Act of 1965 that required covered facilities to create and maintain a Safety Case in order to obtain a license to operate. Since that time other industries that have used Safety Cases include pipelines, railways, and mining operations. Moreover, in spite of the fact that the term Safety Case is not widely used in the United States, the same approach to the development and application of Safety Management Systems is, in fact, used in other American industries. For example, the U.S. nuclear and space industries prepare Safety Analysis Reports (SARs) and Mission Safety Evaluations (MSEs), respectively. These documents have the same general intent and strucmre as a Safety Case. Within the onshore process... 

A complete safety analysis report, including the effects of postulated failures, shall be prepared. Further guidance on the safety analysis may be found in para. 301 of this guide. Copies of the current safety analysis report and the related operational safety requirements shall be made available to all members of the (qierat-ing staff. 

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