Control Systems Not Required for Safety

379-1977, "IEEE Standard Application of the

IEEE

Single-Failure Criterion to Nuclear Power Generating Station

(This standard was revised and issued as

Class 1E Systems."

ANSI/IEEE 379-1988, "IEEE Standard Application of the Single-

Failure Criterion to Nuclear Power Generating Station Class 1E

Systems.")

IEEE 384-1977, "IEEE Standard Criteria for Inde-

pendence of Class1E Equipment and Circuits." (This standard was

revised and issued as ANSI/IEEE 384-1981, "IEEE Standard Criteria

for Independence of Class 1E Equipment and Circuits.")

ISA S67.04-1982, "Setpoints for Nuclear Safety-

Related Instrumentation Used in Nuclear Power Plants."

7.6.4

Supplemental Information

USNRC "Standard Review Plan," June

NUREG-0800,

1987.

"Interlock Systems Important to

SRP

7.6,

Safety."

NUREG-0737,

"Clarification of TMI Action Plans,"

USNRC, November 1980.

7.7

CONTROL SYSTEMS NOT REQUIRED FOR SAFETY

7.7.1

Code of Federal Regulations

10 CFR 50, Appendix A, "General Design Criteria for

Nuclear Power Plants."

GDC 13,

"Instrumentation and Control."

"Control Room."

GDC 19,

7.7.2

USNRC Regulatory Guides, SRP Branch Technical Positions

and Appendices

"Instrument Sensing

Guide

Regulatory

1.151,

Lines."

SRP Appendix 7-A, Branch Technical Position ICSB

14, "Spurious Withdrawals of Single Control Rods in Pressurized

Water Reactors."

SRP 7.1, Appendix A, "Acceptance Criteria and

Guidelines for Instrumentation and Control Systems Important to

Safety."

7-17