Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process Page: 3 of 10
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Advanced Test Reactor Design Basis Reconstitution Project
Issue Resolution Process
Steven D. Winter
Gregg L. Sharp, William E. Kohn, Richard T. McCracken
Idaho National Laboratory / Battelle Energy Alliance
P.O. Box 1625
Idaho Falls, ID 83415-7136
Phone (208) 533-4264 / Fax (208) 533-4173
Steven.Winter@inl. gov
Introduction
The Advanced Test Reactor (ATR) is a Department of Energy (DOE)-owned pressurized-water
nuclear reactor whose principal function is to provide a high neutron flux for experiments
involving reactor fuels and materials. The reactor also provides other irradiation services such as
radioisotope production. The reactor has a design thermal power of 250 MW, a nominal
operating pressure of 360 psig at the core inlet (top of core), and a nominal core inlet temperature
of 125 F. The nominal core outlet temperature is 170 F at the design thermal power level. The
ATR and its support facilities are located at the Reactor Technology Complex (RTC) of the
Idaho National Laboratory (INL).
The original safety basis for the ATR was documented in a Safety Analysis Report (SAR) dated
April 1965. The ATR Plant Protection System (PPS) and Technical Specifications Design Basis
Report (DBR), dated May 1976, was prepared to support design of an upgraded PPS and
development of technical specifications. The PPS includes the reactor shutdown system and the
engineered safety features that were part of the facility at the time the DBR was prepared. The
DBR contained analyses of accident sequences from which the performance requirements
(setpoints and response times) for the PPS and technical specifications for initial conditions
(pressure, temperature, flow, power) were derived. The DBR served as the facility accident
analysis from 1976 until the upgraded SAR (SAR-153) was implemented in 1998. The DBR was
maintained as a configuration controlled document with periodic updates. SAR-153 was
prepared in response to requirements in DOE Order 5480.23 and now Title 10 of the Code of
Federal Regulations, Part 830, Nuclear Safety Management for upgrading and maintaining a
DSA describing the facility safety basis. SAR-153 development did not include a design basis
reconstitution effort. Rather, SAR-153 built on the DBR and referred to the 1965 SAR. SAR-153
has been maintained via the annual update process as required by DOE regulations.
The Design Basis Reconstitution Program (DBRP) is part of the on-going ATR Life Extension
Program (LEP). The purpose of the DBRP is to update and bring the ATR design basis to a level
comparable to contemporary commercial nuclear power plants. The DBRP focuses on
identification of system requirements and performance criteria essential to the system's
performance of its safety function, the basis for the requirements, and how the current system
configuration satisfies the functional requirements and criteria. In addition to establishing the
baseline documentation important to the system's or structure's safety function, the functionality
of the structures and systems will be validated.
The publications processing office has reviewed and released this
document for publication (reference INL/CON-07-12514)
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Winter, Steven D.; Sharp, Gregg L.; Kohn, William E. & McCracken, Richard T. Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process, article, May 1, 2007; [Idaho Falls, Idaho]. (https://digital.library.unt.edu/ark:/67531/metadc888374/m1/3/: accessed May 6, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.