16/30324061 DC : 0
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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BS IEC 61504 ED2.0 - NUCLEAR FACILITIES INSTRUMENTATION AND CONTROL SYSTEMS IMPORTANT TO SAFETY - CENTRALIZED SYSTEMS FOR CONTINUOUS MONITORING OF RADIATION AND/OR LEVELS OF RADIOACTIVITY
Available format(s)
Hardcopy , PDF
Language(s)
English
Publisher
Superseded date
30-09-2017
Superseded by
£20.00
Excluding VAT
FOREWORD
INTRODUCTION
1 Scope
2 Normative references
3 Terms and definitions
4 Design requirements
5 General test procedures
6 Documentation
Annex A (informative) - Cross-reference for
centralized system for radiation monitoring
standards
Bibliography
BS IEC 61504 Ed2.0.
| Committee |
NCE/8
|
| DocumentType |
Draft
|
| Pages |
32
|
| PublisherName |
British Standards Institution
|
| Status |
Superseded
|
| SupersededBy |
| IEC 60761-5:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 5: Specific requirements for tritium monitors |
| IEC 60951-2:2009 | Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air |
| IEC 61226:2009 | Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions |
| IEC 61500:2009 | Nuclear power plants - Instrumentation and control important to safety - Data communication in systems performing category A functions |
| IEC 62138:2004 | Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions |
| IEC 62705:2014 | Nuclear power plants - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle |
| IEC 61772:2009 | Nuclear power plants - Control rooms - Application of visual display units (VDUs) |
| IEC 61559-1:2009 | Radiation protection instrumentation in nuclear facilities - Centralized systems for continuous monitoring of radiation and/or levels of radioactivity - Part 1: General requirements |
| IEC 61250:1994 | Nuclear reactors - Instrumentation and control systems important for safety - Detection of leakage in coolant systems |
| IEC 62003:2009 | Nuclear power plants - Instrumentation and control important to safety - Requirements for electromagnetic compatibility testing |
| IEC 62303:2008 | Radiation protection instrumentation - Equipment for monitoring airborne tritium |
| IEC 60761-2:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 2: Specific requirements for radioactive aerosol monitors including transuranic aerosols |
| IEC 60761-3:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 3: Specific requirements for radioactive noble gas monitors |
| IEC 60761-4:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 4: Specific requirements for radioactive iodine monitors |
| IEC 60987:2007+AMD1:2013 CSV | Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems |
| IEC 60951-1:2009 | Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 1: General requirements |
| IEC 61497:1998 | Nuclear power plants - Electrical interlocks for functions important to safety - Recommendations for design and implementation |
| IEC 61031:1990 | Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use in nuclear power plants during normal operation and anticipated operational occurrences |
| IEC 60910:1988 | Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors |
| IEC 62302:2007 | Radiation protection instrumentation - Equipment for sampling and monitoring radioactive noble gases |
| IEC 60951-3:2009 | Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 3: Equipment for continuous high range area gamma monitoring |
| IEC 60861:2006 | Equipment for monitoring of radionuclides in liquid effluents and surface waters |
| IEC 61771:1995 | Nuclear power plants - Main control-room - Verification and validation of design |
| IEC 60951-4:2009 | Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 4: Equipment for continuous in-line or on-line monitoring of radioactivity in process streams |
| IEC 60960:1988 | Functional design criteria for a safety parameter display system for nuclear power stations |
| IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
| IEC 60761-1:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 1: General requirements |
| IEC 60768:2009 | Nuclear power plants - Instrumentation important to safety - Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEC 62566:2012 | Nuclear power plants - Instrumentation and control important to safety - Development of HDL-programmed integrated circuits for systems performing category A functions |
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