Codes and Standards - std0100t0187

Appendix A, "Radiological

Con-

SRP

15.4.9,

sequences of a Control Rod Drop Accident (BWR)."

Codes and Standards

15.4.3

ANSI/ISA-S67.04-1982, "Setpoints for Nuclear

Safety-Related Instrumentation Used in Nuclear Power Plants."

ASME Boiler and Pressure Vessel Code, "Rules for

Construction of Nuclear Power Plant Components," Section III,

Division 1, Article NB-7000, "Protection Against Overpressure."

379-1972, "IEEE Trial-Use Guide for the

IEEE

Application of the Single-Failure Criterion to Nuclear Power Gen-

erating Station Class 1E Systems." (This standard was revised and

issued as IEEE 379-1988, "IEEE Standard Application of the

Single-Failure Criterion to Nuclear Power Generating Station

Class 1E Systems.")

15.4.4

Supplemental Information

USNRC "Standard Review Plan," June

NUREG-0800,

1987.

15.4.1, "Uncontrolled Control Rod

SRP

Assembly Withdrawal from a Subcritical or Low Power Startup Con-

dition."

"Uncontrolled

Control

Rod

15.4.2,

SRP

Assembly Withdrawal at Power."

SRP 15.4.3, "Control Rod Misoperation (System

Malfunction or Operator Error)."

SRP 15.4.4, "Startup of an Inactive Loop or

Recirculation Loop at an Incorrect Temperature."

15.4.5, "F1ow Controller Malfunction

SRP

Causing an Increase in BWR Core Flow Rate."

SRP 15.4.6, "Chemical and Volume Control Sys-

tem Malfunction That Results in a Decrease in Boron Concentration

in the Reactor Coolant (PWR)."

SRP 15.4.7, "Inadvertent Loading and Opera-

tion of a Fuel Assembly in an Improper Position."

"Spectrum of Rod Ejection Acci-

15.4.8,

SRP

dents (PWR)."

15-9