Status of SFR Codes and Methods QA Implementation

Brunett, Acacia J.; Briggs, L.L.; Fanning, T. H.

doi:10.2172/1342175

Cited by 5 publications

(7 citation statements)

References 6 publications

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“…This work continued through January 2017 with Phase 1 (Figure 1.1). The efforts completed in Phase 1 [3] were focused on the initial development of a provisional SQA program for SAS4A/SASSYS-1 are summarized in Section 1.3. The Argonne-developed severe accident systems-level analysis code SAS4A/SASSYS-1 [6] was selected for this effort due to its prevalent use in a wide range of steady state and transient safety analyses, making it a key tool for use in a license application.…”

Section: Project Backgroundmentioning

confidence: 99%

“…This report also discusses the completion of Phase 2 SQA-related technical activities, including improvements to qualification testing and code documentation. The ultimate goal of this ongoing RTDP task is to develop an SQA framework that satisfies the fundamental requirements of relevant SQA standards and guidance [3] while still maintaining sufficient flexibility and efficiency such that the framework can be sustained with modest resources.…”

Section: Introductionmentioning

confidence: 99%

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Implementation of Software QA for SAS4A/SASSYS-1 Rev. 1

Brunett

Fanning

2018

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In an effort to support closure of gaps in advanced reactor licensing pathways, a multi-year task to systematically develop sodium-cooled fast reactor (SFR) codes and methods for use in a licensing framework was launched as part of the DOE-NE Advanced Reactor Technologies (ART) Program's Regulatory Technology Development Plan (RTDP). This report documents Phase 2 of this task, which was focused on the finalization and initial implementation of a software quality assurance (SQA) program for SAS4A/SASSYS-1 and completion of highpriority SQA-related technical activities. The ultimate goal of this ongoing RTDP task is to develop an SQA framework that satisfies the fundamental requirements of relevant SQA standards and guidance while still maintaining sufficient flexibility and efficiency such that the framework can be sustained with modest resources.The provisional SAS4A/SASSYS-1 SQA Program has undergone a trial application period during which numerous code development activities were completed and version 5.2 of the code was released in accordance with Program procedures. As a result of lessons learned during the trial application, SQA Program documentation has been revised to improve clarity and consistency. In addition to revision of Program documentation, several key quality-enhancing technical activities were also completed, including addition of 117 new V&V Test Suite cases, reconstruction of historical validation test cases based on TREAT experiments, improvement in coverage of the regression test suite, development of unit testing capabilities, and modernization of the Code Manual.Despite the improvements to the SAS4A/SASSYS-1 SQA Program, several gaps still remain. These gaps are primarily related to engagement with the NRC, DOE, and industry regarding the acceptability of the SAS4A/SASSYS-1 SQA Program and code pedigree as it relates to the use of the code as a safety analysis tool. Resolution of these gaps requires sustained, direct engagement with these groups regarding the acceptability of design, requirement, and testing documentation for critical characteristics relevant to reactor designs anticipated to enter the licensing phase in the near term. Early engagement with these groups can help to reduce licensing obstacles for advanced reactors as a path toward SAS4A/SASSYS-1 acceptance is identified.It should be noted that the SQA Program itself, including the Program plans, procedures, configuration management, and testing strategies, is considered to be at a fairly mature stage at the conclusion of this task. It is anticipated that the only revisions to the Program that may be required would be related to alignment with specific standards or requirements (e.g. NQA-1, DOE O 414.1D, etc.) as per feedback from the licensee or regulator. In this case, interaction with these groups is again required to determine if any Program revisions are required.

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Section: Project Backgroundmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Implementation of Software QA for SAS4A/SASSYS-1 Rev. 1

Brunett

Fanning

2018

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“…[4] An objective of the RTDP was to assess SFR computer code capabilities and the activities required to support qualification for regulatory use. Over the course of the program (see Figure 2), [7] a software quality assurance program was formally established for SAS and went into effect in March 2018. [8]…”

Section: Software Quality Assurancementioning

confidence: 99%

“…[4] One of the tasks was to establish software quality assurance (SQA) practices for SFR safety analysis codes that would be used in an authorization or licensing framework. [5] [6] [7] [8] This new task was limited in scope and duration. The limited scope focused on computer codes that were in active use for SFR design and safety analysis and whose maintenance was the responsibility of DOE.…”

Section: Introductionmentioning

confidence: 99%

Fast Reactor Methods Development Plan

Fanning

Smith

Brunett

2018

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Fast reactor design and safety analysis methods (computer codes) have been under development for approximately sixty years. During the first forty years, code development was driven by the immediate needs of operational facilities such as Experimental Breeder Reactors I and II and the Fast Flux Test Facility. Development was further driven by programmatic needs to support advanced reactor programs such as the Clinch River Breeder Reactor Project and the Advanced Liquid Metal Reactor Program. By the early 1990s, design and safety analysis codes had been well established to addressed the unique characteristics of fast reactors.During the subsequent twenty years, however, development was nearly stagnant as a result of U.S. Government policy changes that abruptly canceled nearly all of the fast reactor research in the United States. As a result, the state of fast reactor design and safety analysis methods has deteriorated.This report defines a Fast Reactor Methods Development Plan that describes the scope of maintenance and development activities that are required to ensure the existing fast reactor design and safety analysis codes are available to adequately support a fast reactor authorization basis or license application. Of highest priority is the need to establish a software development team that will implement and execute quality software engineering practices to preserve the tremendous amount of knowledge and experience gained during the preceding six decades.Design and safety analysis codes for fast reactors provide unique capabilities not available in codes designed for light-water reactors. By 1980, the number of codes available for fast reactor design and safety analysis was around 130 in the U.S. alone. By 2010, the number had dwindled to approximately 60 worldwide, with less than eighteen potentially available in the U.S. Of these, seven are identified in this report as being critical for design and safety analysis:

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“…Code maintenance activities have shifted into a more formal software quality assurance Program that has been developed under the Regulatory Technology Development Plan. [12,13] Source code and documentation are maintained within a software configuration management system and formal code changes are tracked in an electronic ticket system according to SQA procedures. These activities are vital for any software that will be used to assess the safety of a nuclear installation, but they do require resources to maintain.…”

Section: Software Quality Assurancementioning

confidence: 99%

FY2017 Updates to the SAS4A/SASSYS-1 Safety Analysis Code

Fanning

2017

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Status of SFR Codes and Methods QA Implementation

Cited by 5 publications

References 6 publications

Implementation of Software QA for SAS4A/SASSYS-1 Rev. 1

Implementation of Software QA for SAS4A/SASSYS-1 Rev. 1

Fast Reactor Methods Development Plan

FY2017 Updates to the SAS4A/SASSYS-1 Safety Analysis Code

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