IEEE 338-2012
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
Available format(s)
PDF
Superseded date
04-07-2023
Language(s)
English
Published date
03-23-2012
1. Overview
2. Normative references
3. Definitions
4. System design requirements for testing
5. Testing program requirements
Annex A (informative) - Bibliography
Annex B (informative) - General overview of risk-informed
surveillance testing
Annex C (informative) - Evaluation process for surveillance
test changes
Annex D (informative) - Programmatic approach to risk-informed
surveillance test interval management
The standard provides criteria for the performance of periodic testing of nuclear power generating station safety systems.
| Committee |
Nuclear Power Engineering Committee
|
| DevelopmentNote |
Supersedes IEEE DRAFT 338. (07/2007)
|
| DocumentType |
Standard
|
| ISBN |
978-0-7381-7210-1
|
| Pages |
72
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 741-2007 | IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| BS IEC 61888:2002 | Nuclear power plants. Instrumentation important to safety. Determination and maintenance of trip setpoints |
| IEEE DRAFT 387 : D9A MAR 95 | DRAFT STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS |
| ISA 67.06.01 : 2002 | PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| IEEE DRAFT 833 : D3 2004 | PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS |
| IEEE 384-2018 | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEC 61888:2002 | Nuclear power plants - Instrumentation important to safety - Determination and maintenance of trip setpoints |
| IEEE 387-1995 | IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| ANS 56.3 : 77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| IEEE 1205-2014 | IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 1819-2016 | IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities |
| ISA 67.06 : 1984 | RESPONSE TIME TESTING OF NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEEE DRAFT 741 : D1 2006 | CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS |
| ANS 51.1 : 83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 420-2013 REDLINE | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| ANS 52.1 : 83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 1682-2011 | IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations |
| IEEE 741-2017 | IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| IEEE 577-2022 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 308-2020 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 741-2022 REDLINE | IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| IEEE 420-2013 REDLINE | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| IEEE 566 : 1977 | RECOMMENDED PRACTICE FOR THE DESIGN OF DISPLAY AND CONTROL FACILITIES FOR CENTRAL CONTROL ROOMS OF NUCLEAR POWER GENERATING STATIONS |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| CFR 10(PTS0-199) : JAN 87 | ENERGY - NUCLEAR REGULATORY COMMISSION |
| ISA 67.06.01 : 2002 | PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE 7-4.3.2-2010 REDLINE | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| NACE RP 01 89 : 2002 | ON-LINE MONITORING OF COOLING WATERS |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEEE 308-2001 | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| 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 |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 450-2010 REDLINE | IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications |
| ANS 3.2 : 2012(R2017) | MANAGERIAL, ADMINISTRATIVE, AND QUALITY ASSURANCE CONTROLS FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS |
| 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 |
| IEEE 946-2004 | IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 387-1995 | IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| ASME RA-S : 2008 | LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS |
| IEEE 317-2013 REDLINE | IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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