IEC 62705:2014
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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Nuclear power plants - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle
Hardcopy , PDF , PDF 3 Users , PDF 5 Users , PDF 9 Users
22-11-2022
English - French
24-07-2014
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FOREWORD
INTRODUCTION
1 Scope
2 Normative references
3 Terms and definitions
4 Abbreviations
5 RMS categorization and classification
6 RMS detailed design and implementation
7 RMS integration and validation
8 RMS installation
9 RMS design modification
10 RMS qualification
11 Calibration
Annex A (informative) - Example of safety classification
for RMS important to safety
Annex B (informative) - Relation between IEC 61513 system
lifecycle and IEC 62705 requirements
IEC 62705:2014 applies to radiation monitoring system (RMS) installed in the nuclear power plants (NPPs). This standard gives requirements for the lifecycle management of RMSs and gives guidance on the application of existing IEC standards covering the design and qualification of systems and equipment. This standard may be applicable to other nuclear facilities (e.g. nuclear fuel storage and processing sites) by evaluating the differences from NPPs.
| Committee |
TC 45/SC 45A
|
| DevelopmentNote |
Stability date: 2019. (07/2014)
|
| DocumentType |
Standard
|
| Pages |
42
|
| PublisherName |
International Electrotechnical Committee
|
| Status |
Superseded
|
| SupersededBy |
| Standards | Relationship |
| BS IEC 62705:2014 | Identical |
| 16/30324061 DC : 0 | 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 |
| BS IEC 61504:2017 | Nuclear facilities. Instrumentation and control systems important to safety. Centralized systems for continuous monitoring of radiation and/or levels of radioactivity |
| IEC 61504:2017 | Nuclear facilities - Instrumentation and control systems important to safety - Centralized systems for continuous monitoring of radiation and/or levels of radioactivity |
| IEC 60761-5:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 5: Specific requirements for tritium monitors |
| ISO/IEC 17025:2005 | General requirements for the competence of testing and calibration laboratories |
| 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 60532:2010 | Radiation protection instrumentation - Installed dose rate meters, warning assemblies and monitors - X and gamma radiation of energy between 50 keV and 7 MeV |
| 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 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 60980:1989 | Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations |
| 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 61504:2017 | Nuclear facilities - Instrumentation and control systems important to safety - Centralized systems for continuous monitoring of radiation and/or levels of radioactivity |
| 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 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 |
| ISO 2889:2010 | Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities |
| 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 |
| ISO 4037-1:1996 | X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Part 1: Radiation characteristics and production methods |
| IEC 60780:1998 | Nuclear power plants - Electrical equipment of the safety system - Qualification |
| IEC 60761-1:2002 | Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 1: General requirements |
| IEC 61513:2011 | Nuclear power plants - Instrumentation and control important to safety - General requirements for systems |
| 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 |
| ISO 4037-3:1999 | X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence |
| 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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