Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants
Technical Report
·
OSTI ID:6350117
Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6350117
- Report Number(s):
- EGG-PBS-6850; ON: TI86003249
- Country of Publication:
- United States
- Language:
- English
Similar Records
Summary and recommendations of the NRC/INEL Activated Carbon Testing Program
Testing nuclear-grade gas-phase iodine adsorbents
Radiological Effluent Technical Specifications (RETS) implementation - Point Beach Nuclear Plant
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5469098
Testing nuclear-grade gas-phase iodine adsorbents
Conference
·
Tue Dec 31 23:00:00 EST 1985
· ASHRAE Trans.; (United States)
·
OSTI ID:7254212
Radiological Effluent Technical Specifications (RETS) implementation - Point Beach Nuclear Plant
Technical Report
·
Wed May 01 00:00:00 EDT 1985
·
OSTI ID:5698096
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTIVATED CARBON
ADSORBENTS
AIR CLEANING SYSTEMS
CARBON
COMPARATIVE EVALUATIONS
DESIGN BASIS ACCIDENTS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
EVALUATION
HALOGENS
IODINE
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE TESTING
POWER PLANTS
REACTOR ACCIDENTS
REMOVAL
SPECIFICATIONS
STANDARDS
TESTING
THERMAL POWER PLANTS
VENTILATION SYSTEMS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTIVATED CARBON
ADSORBENTS
AIR CLEANING SYSTEMS
CARBON
COMPARATIVE EVALUATIONS
DESIGN BASIS ACCIDENTS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
EVALUATION
HALOGENS
IODINE
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE TESTING
POWER PLANTS
REACTOR ACCIDENTS
REMOVAL
SPECIFICATIONS
STANDARDS
TESTING
THERMAL POWER PLANTS
VENTILATION SYSTEMS