ASME NQA.TR:2020 pdf download.Evolution of Quality Assurance Principles and Requirements in the U.S. Nuclear Industry.
— control of handling, lifting, and rigging activities
— selective application of quality assurance requirements and preparation of a quality assurance program index of procedures
— calibration and control of measuring and test equipment
— indoctrination, training, and qualification of personnel
— identification, reporting, and management of engineering holds
In a large construction project, e.g., the DOE’s Fast Flux Test Facility (FFTFJ, special quality assurance requirements and controls were incorporated through these amendments to RDT F2-2T. The amended requirements helped users to detect, eliminate, or prevent the installation or use of improperly identified and mixed weld filler metal and many other substandard materials purchased for FFTF construction.
Amendment 6 resulted from a rash of handling, lifting, and rigging incidents at DOE facilities. RDT also developed a stringent standard on testing and lifting controls, particularly for lifts over reactors.
Amendment 7 to RDT F2-2T abolished costly and voluminous quality assurance program descriptions that merely repeated the contents of implementing procedures. Instead, users were instructed to prepare a quality assurance program index including the organization structure and a listing of quality assurance procedures.
In his memorandum of March 1972 to RDT technical professionals, RDT Director Shaw called their attention to the promulgation of RDT F2-2T. This standard reinforced the many policy statements and related actions of Congress, AEC, ACRS, and standards-writing groups over several years on the need to significantly strengthen quality assurance in the conducting of reactor and technology development programs, whether in the national laboratories or in the commercial sector.
In a 1978 memorandum to DOE field office managers,6 the DOE Director for Nuclear Energy stated that DOE preferred the quality assurance program for civilian nuclear energy technology development programs to be established and implemented in accordance with applicable requirements of the nationally recognized, voluntary consensus standards. Unless otherwise directed, or where there was no cost advantage, major DOE reactor development programs were to employ ANSI/ASME N45.2. Where ANSI/ASME N45.2 was determined to be insufficient for technology development activities, it was to be supplemented by appropriate quality assurance requirements.
Acting on the recommendation of an RDT study group under Dan Garland to endorse a single national consensus standard for reactor and technology development programs, in April 1985 RDT management canceled and withdrew RDT F2-2T when it endorsed ANSI/ ASME NQA-1-1983. The shift to the ASME NQA-1 national consensus standard was consistent with an Office of Management and Budget (0MB) Circular A-i 19 regarding the use of such national consensus standards.
A comparison of RDT F2-2T with ANSI/ASME NQA-i—1983 revealed consistencies in their basic quality assurance program elements but significant differences in their degree of specificity, particularly when applied to reactor development and testing activities, and in their format.ASME NQA.TR pdf download.