Supplemental Information

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.")

15.6.4

Supplemental Information

USNRC "Standard Review Plan," June

NUREG-0800,

1987.

15.6.1, "Inadvertent Opening of a PWR

SRP

Pressurizer Pressure Relief Valve or a BWR Pressure Relief

Valve."

SRP 15.6.2, "Radiological Consequences of the

Failure of Small Lines Carrying Primary Coolant Outside Contain-

ment."

SRP

15.6.3, "Radiological Consequences of

Steam Generator Tube Failure (PWR)."

SRP

15.6.4, "Radiological Consequences of

Main Steam Line Failure Outside Containment (BWR)."

SRP

15.6.5,

"Loss-of-Coolant Accidents

Resulting from Spectrum of Postulated Piping Breaks Within the

Reactor Coolant Pressure Boundary."

NUREG-0737 ,

"Clarification of TMI Action Plan

Requirements," USNRC, November 1980.

NUREG-0718,

"Licensing Requirements for Pending

Applications for Construction Permits and Manufacturing License,"

USNRC, March 1981.

NUREG-0409, "Iodine Behavior in a PWR Cooling Sys-

tem Following a Postulated Steam Generator Tube Rupture Acci-

dent," USNRC, January 1978.

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

sure Transient Protection for Pressurized Water Reactors," USNRC,

September 1978.

NUREG/CR-2260, "Technical Basis for Regulatory

Guide 1.145, Atmospheric Dispersion Models for Potential Accident

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

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

15-14