Increase In Reactor Coolant Inventory

"Spectrum of Rod Drop Accidents

S R P 15.4.9,

(BWR)."

"Functional Criteria for Emergency

NUREG-0696,

Response Facilities," USNRC, February 1981.

"Clarification of TMI Action Plan

NUREG-0737 ,

Requirements," USNRC, November 1980.

NUREG-0660, "NRC Action Plan Developed as a Result

of the TMI-2 Accident," USNRC, Vol. 1, May 1980 and Vol. 1, Rev.

1, August 1980.

NUREG-0224, "Final Report on Reactor Vessel Pres-

sure Transient Protection for Pressurized Water Reactors," USNRC,

September 1978.

This section identifies criteria for initiating events

that involve

inadvertent operation of emergency core cooling

systems and malfunction of the chemical and volume control system

that increases reactor coolant inventory.

15.5.1

Code of Federal Regulations

10 CFR 50.34, "Contents of Applications; Technical

Information."

10 CFR 50.61 "Fracture Toughness Requirements for

Protection Against Pressurized Thermal Shock Events."

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

Nuclear Power Plants."

GDC 10, "Reactor Design."

GDC 15, "Reactor Coolant System Design."

GDC 26, "Reactivity Control System Redundancy

and Capability."

USNRC Regulatory Guides, SRP Branch Technical Positions

15.5.2

and Appendices

Regulatory

Guide

1.53, "Application of the

Single-Failure Criterion to Nuclear Power Plant Protection Sys-

tems."

Regulatory Guide

1.105, "Instrument Setpoints for

Safety-Related Systems."

15-10