Decrease in Heat Removal by the Secondary System

"Increase in Feedwater Flow."

SRP

15.1.2,

"Increase in Steam Flow."

SRP

15.1.3,

"Inadvertent Opening of a Steam

SRP 15.1.4,

Generator Relief or Safety Valve."

"Steam System Piping Failures

15.1.5,

SRP

Inside and Outside of Containment (PWR)."

"Licensing Requirements for Pending

NUREG-0718,

Applications for Construction Permits and Manufacturing License,"

USNRC, March 1981.

"Clarification of TMI Action Plan

NUREG-0737 ,

Requirements," USNRC, November 1980.

"TMI-Related Requirements for New

NUREG-0694 ,

Operation Licenses," USNRC, June 1980.

"Final Report on Reactor Vessel Pres-

NUREG-0224,

sure Transient Protection for Pressurized Water Reactors," USNRC,

September 1978.

NUREG/CR-2260, "Technical Basis for Regulatory

Guide 1.145, Atmosphere Dispersion Models for Potential Accident

Consequence Assessments at Nuclear Power Plants," W.G. Snell and

R.W. Jubach, NUS Corp., October 1981.

This section identifies criteria for initiating events

that involve loss of external load, turbine trip, loss of con-

denser vacuum, closure of BWR main steam isolation valve, steam

pressure regulator failure, loss of nonemergency ac power to the

station auxiliaries, loss of normal feedwater flow, and feedwater

system pipe breaks.

15.2.1

Code of Federal Regulations

10 CFR 50.34, "Contents of Applications; Technical

Information."

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

Nuclear Power Plants."

GDC 10, "Reactor Design."

GDC 15, "Reactor Coolant System Design."

15-3