Safety Related Design Standards and Criteria cont'd

DOE-HDBK-6004-99

These standards and criteria cover both component level and system level design feature

considerations for safety systems. Component design features necessary for safety systems include

attributes such as equipment qualification, maintainability, failure criteria and testability. In addition

to these attributes, the system level design features should include but not be limited to reliability,

independence, redundancy, human factors and separation.

Each of the standards listed below form a portion of the overall design philosophy for I&C safety

systems. As such, the design intent of all of these standards should be taken as a whole for the

analysis and design of I&C systems.

IEC 964 (1989-03)

Design for control rooms of nuclear power plants.

IEEE 603

Standard Criteria for Safety Systems for Nuclear Power Generating Stations

IEEE 323

Qualifying Class IE Equipment for Nuclear Power Generating Stations

IEEE 352

IEEE Guide for General Principles for Reliability Analysis for Nuclear Power

Generating Station Safety Systems

IEEE 577

IEEE Standard Requirements for Reliability Analysis in the Design and Operation of

Safety Systems

IEEE 420

IEEE Standard for the Design and Qualification of Class IE Control Boards, Panels,

and Racks used in Nuclear Power Generating Stations.

IEEE 379

IEEE Standard Application of the Single Failure Criterion to Nuclear Power

Generating Station Safety Systems

IEEE 384

IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits

IEEE 338

IEEE Standard Criteria for Periodic Surveillance Testing of Nuclear Power

Generating Station Safety Systems

ISA 67.02

S67.02.01: Nuclear Safety-Related Instrument Sensing Line Piping and Tubing

Standard for Use in Nuclear Power Plants

ISA 67.04

S67.04--Part I: Setpoints for Nuclear Safety-Related Instrumentation-- ANSI/ISA-

1994

RP67.04--Part II: Methodologies for the Determination of Setpoints for Nuclear

Safety-Related Instrumentation-1994

ISA 67.06

S67.06: Response Time Testing of Nuclear Safety-Related Instrument Channels in

Nuclear Power Plants-- ANSI/ISA-1984