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| 379-1972, "IEEE Trial-Use Guide for the
C.
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.")
Supplemental Information
15.2.4
USNRC "Standard Review Plan," June
A.
NUREG-0800,
1987.
SRP 15.2.1, "LOSS of External Load."
1.
15.2.2, "Turbine Trip."
2.
SRP
3.
SRP
15.2.4, "Closure of Main Steam Isolation
4.
SRP
Valve (BWR)."
15.2.5, "Steam Pressure Regulator Failure
5.
SRP
(Closed)."
SRP 15.2.6, "Loss of Nonemergency AC Power to
6.
the Station Auxiliaries."
15.2.7, "Loss of Normal Feedwater Flow."
7.
SRP
15.2.8, "Feedwater System Pipe Breaks
8.
SRP
Inside and Outside Containment (PWR)."
"Licensing Requirements for Pending
B.
NUREG-0718,
Applications for Construction Permits and Manufacturing License,"
USNRC, March 1981.
"Clarification of TMI Action Plan
C.
NUREG-0737,
Requirements," USNRC, November 1980.
NUREG/CR-2260, "Technical Basis for Regulatory
D.
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.
Bulletin 79-13, Rev. 2, "Cracking in Feedwater
E. IE
System Piping."
F.
IE
Information
Notice
84-76,
"LoSS of All AC
Power."
15-5
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