Supplemental Information

Supplemental Information

15.3.4

NUREG-0800, USNRC "Standard Review Plan," June

1987.

SRP 15.3.1, "Loss of Forced Reactor Coolant

Flow Including Trip of Pump Motor."

"Flow Controller Malfunctions."

SRP

15.3.2,

"Reactor Coolant Pump Rotor Sei-

SRP

15.3.3,

zure."

"Reactor Coolant Pump Shaft

15.3.4,

SRP

Break."

"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.

NUREG-0158, "Staff Discussion of Twelve Additional

Technical Issues Raised by Responses to November 3, 1976

Memorandum from the Director, NRR to NRR Staff," USNRC, December

1976.

NUREG-0138, "Staff Discussion of Fifteen Technical

Issues Listed in Attachment to November 3, 1976, Memorandum from

Director NRR to NRR Staff," USNRC, November 1976.

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.

IE Information Notice 85-03, "Separation of Pri-

mary Reactor Coolant Pump Shaft and Impeller."

This section identifies criteria for initiating events

that involve uncontrolled control rod withdrawal from a subcriti-

cal or low power startup condition, uncontrolled control rod

withdrawal at power, control rod misoperation, startup of an

inactive primary or recirculation loop at an incorrect tempera-

ture, flow controller malfunction, decrease in chemical poisons

dissolved in the moderator, inadvertent loading and operation of

a fuel assembly in an improper position, and control rod ejection

15-7