Functional interfaces between safety system software components and the system- level design.

DOE-STD-1183-2004

Discuss why the application of the graded approach does not apply to the USQ process.

m. Review a USQ Determination including walking down the proposed change/potential

inadequacy.

24. Nuclear safety specialists shall demonstrate a familiarity level knowledge of the

functional interfaces between safety system software components and the system-

level design.

Supporting Knowledge and/or Skills

a. Identify how system-level requirements are established and then assigned to hardware,

software, and human components of a digital instrumentation and control system.

b. Identify the typical requirements that define functional interfaces between safety system

software components and the system-level design, as described in standards such as

ANSI/IEEE 830, IEEE Guide to Software Requirements Specifications and IEEE 7-4.3.2,

Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating

Stations. Identify where this information is documented.

c. Identify the specific records that must be maintained and the requirements for maintaining

these records to document the development of safety system software.

d. Review a development project for safety system software. Explain how the functional

interfaces between components and the system level design were established and

controlled.

25. Nuclear safety specialists shall demonstrate a familiarity level knowledge of the

relationships between the problems being addressed by safety analysis and design

codes, the design requirements for the codes, and the components of the codes.

Supporting Knowledge and/or Skills

a. Identify how functional requirements and applicability of safety analysis and design

computer codes are defined, documented, and controlled relative to modeling and data

assumptions, design constraints, sizing and timing conditions and input/output parameters.

b. Review a development project for safety analysis or design software. Explain how the

problem being addressed by the software was translated into functional requirements, how

the requirements were established and controlled, and how the code was reconciled with

the original problem.

c. Discuss the DOE toolbox codes (reference http://tis.eh.doe.gov/techstds/

toolbox_codes.html), their strengths, weaknesses and other factors governing their

appropriate use and the applicable DOE standards and guides for modeling their

phenomena.

26. Nuclear safety specialists shall demonstrate a familiarity level knowledge of

Department of Energy (DOE) Policy 450.4, Safety Management System Policy and

Policy 450.5, Line Environment, Safety and Health Oversight as applied to nuclear

safety.

Supporting Knowledge and/or Skills

a. Discuss the fundamentals of Integrated Safety Management and direct application to

nuclear safety.