13/30249610 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Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 EN 62705 ED 1.0 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - RADIATION MONITORING SYSTEMS (RMS) CHARACTERISTICS AND TEST METHODS
Available format(s)
Hardcopy , PDF
Superseded date
31-08-2014
Superseded by
Language(s)
English
Publisher
Important note : Users cannot be edited or removed once added to your Multi user PDF.
INTRODUCTION
1 Scope
2 Normative references
3 Terms and definitions
4 Abbreviations
5 RMS requirement and specification
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
BS EN 62705 ED 1.0
| Committee |
NCE/8
|
| DocumentType |
Draft
|
| Pages |
19
|
| 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Superseded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 |
| 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 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 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 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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