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2. SCOPE

The program was conducted in accordance with ASCO qualification specifications, which were written to comply with the requirements and suggestions, contained in the following documents:

2.1

IEEE 323-1983, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations".

2.2

IEEE 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations".

2.3

IEEE 382-1985, "IEEE Standard for Qualification of Actuators for Power Operated Valve Assemblies with Safety-Related Functions for Nuclear Power Plants".

2.4

IEEE 627-1980, "IEEE standard for Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations".

2.5 2.6

10 CFR 21, "Reporting of Defects and Non-Compliances".

10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants".

2.7 2.8

10 CFR 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants".

US NRC Regulatory Guide No. 1.73, "Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants".

2.9

US NRC Regulatory Guide No. 1.89, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants".

2.10

US NRC Regulatory Guide No. 1.100, "Seismic Qualification of Electric Equipment for Nuclear Power Plants".

2.11

ASCO documents for Acceptance and production testing contained in Appendices AI, AII, and AIII of Appendix A.

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