WG_3.1 - Testing Working Group

Yvonne Williams

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 surveillance 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 management.

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 IEEE nuclear standards.

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.

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.

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

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.

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.

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.