The standard provides criteria for the performance of periodic testing of nuclear power generating station safety systems. The scope of periodic testing consists of functional tests and checks, calibration verification, and time response measurements, as required, to verify that the safety system performs its defined safety function. Post-maintenance and post-modification testing are not covered by this document. This standard amplifies the periodic testing requirements of other nuclear safety-related IEEE standards. Remarks: Revision of IEEE Std 338-1987
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
- Status
- Superseded Standard
- PAR Approval
- 2001-06-14
- Superseded by
- 338-2012
- Superseding
- 338-1987
- Board Approval
- 2006-12-06
- History
-
- ANSI Approved:
- 2007-05-24
- Published:
- 2007-06-06
Working Group Details
- Society
- IEEE Power and Energy Society
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
- Working Group
-
WG_3.1 - Testing Working Group
- IEEE Program Manager
- Christian Orlando
Contact Christian Orlando - Working Group Chair
- Yvonne Williams
Other Activities From This Working Group
Current projects that have been authorized by the IEEE SA Standards Board to develop a standard.
P1819
Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Systems and Components at Nuclear Power Generating Stations and Other Nuclear Facilities
This standard identifies and discusses criteria for risk-informed categorization and treatment of electrical and electronic systems and components that are designated by the user to be placed into safety significant categories at nuclear power generating stations and other nuclear facilities.
Standards approved by the IEEE SA Standards Board that are within the 10-year lifecycle.
1819-2016
IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
This standard addresses the following: Risk-informed methods have been established to appropriately categorize components as either safety significant or low safety significant. Application of these methods has been shown to be safety-beneficial for existing nuclear power generating stations and nuclear facilities. No standardized approach currently exists for the detailed application of these methods to electrical and electronic components. The results of the categorization process are not easily integrated with traditional Class 1E/non-Class 1E classifications or the resulting treatment for these components. This standard provides methods to categorize electrical and electronic components using a risk-informed process and identifies how the categorization results relate to Class 1E/non-Class 1E classifications. This standard also provides a standardized and accepted method for alternate treatment of categorized components commensurate with their safety significance.
336-2020
IEEE Recommended Practice for Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities
Considerations for the pre-installation, installation, inspection, and testing of Class 1E power, instrumentation, and control equipment and systems of a nuclear facility while in the process of installing, inspecting, and testing during new construction, modification, or maintenance are provided in this recommended practice. This recommended practice does not apply to periodic surveillance testing. For purposes of this recommended practice, in addition to a nuclear power plant, a nuclear facility is defined as a facility related to the nuclear fuel cycle from fuel processing to reprocessing and waste management.
338-2022
IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
Criteria for the performance of periodic surveillance testing of nuclear power generating station safety systems are provided in this standard. The scope of periodic surveillance testing consists of functional tests and checks, calibration verification, and time response measurements, as required, to verify that the safety system performs its defined safety function. Post-maintenance and post-modification testing are not covered by this document. The periodic surveillance testing requirements of IEEE NPEC nuclear standards are amplified in this standard. Some design requirements are also identified in this standard.
These standards have been replaced with a revised version of the standard, or by a compilation of the original active standard and all its existing amendments, corrigenda, and errata.
336-1985
IEEE Standard Installation, Inspection and Testing Requirements for Power, Instrumentation, and Control Equipment at Nuclear Facilities
Requirements for installation, inspection, and testing of power, instrumentation, and control equipment and systems during the construction phase of a nuclear facility are set forth. These requirements also cover modifications and those operating phase activities that are comparable in nature and extent to related initial construction activities of the facility. The intent is to establish requirements for safety systems equipment. However, this standard may also be applied to nonsafety systems equipment.
336-2005
IEEE Guide for Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities
This guide provides considerations for the pre-installation, installation, inspection, and testing of Class 1E power, instrumentation, and control equipment and systems of a nuclear facility. This guidance is applicable to initial construction, modification (backfit), and maintenance activities. This guide does not apply to periodic testing.
336-2010
IEEE Recommended Practice for Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities
Considerations for the pre-installation, installation, inspection, and testing of Class 1E power, instrumentation, and control equipment and systems of a nuclear facility while in the process of installing, inspecting, and testing during new construction, modification, or maintenance are provided. This recommended practice does not apply to periodic testing. For purposes of this standard, in addition to a nuclear power plant, a nuclear facility is defined as a facility related to the nuclear fuel cycle from fuel processing to reprocessing and waste facilities.
338-1987
IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
Design and operational criteria are provided for the performance of periodic testing as part of the surveillance program of nuclear power generating station safety systems. Such testing consists of functional tests and checks, calibration verification, and time-response measurements, as required, to verify that the safety system performs to meet its defined safety function. The system status, associated system documentation, test intervals, and test procedures during operation are also addressed.
338-2012
IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
The standard provides criteria for the performance of periodic surveillance testing of nuclear power generating station safety systems. The scope of periodic surveillance testing consists of functional tests and checks, calibration verification, and time response measurements, as required, to verify that the safety system performs its defined safety function. Post-maintenance and post-modification testing are not covered by this document. This standard amplifies the periodic surveillance testing requirements of other nuclear safety-related IEEE standards.
These standards have been removed from active status through a ballot where the standard is made inactive as a consensus decision of a balloting group.
No Inactive-Withdrawn Standards
These standards are removed from active status through an administrative process for standards that have not undergone a revision process within 10 years.
No Inactive-Reserved Standards