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|  J.
IEEE 279-1971, "Criteria for Protection Systems
for Nuclear Power Generating Stations." (This standard was with-
drawn on June 14, 1984 and incorporated into ANSI/IEEE 603-1980,
"IEEE Standard Criteria for Safety Systems for Nuclear Power Gen-
erating Stations.")
10.1.4
Supplemental Information
None.
10.2.1
Code of Federal Regulations
A.
10 CFR 50.55a, "Codes and Standards."
10 CFR 50, Appendix A, "General Design Criteria for
B.
Nuclear Power Plants."
1.
GDC
4,
"Environmental and Missile Design
Bases."
10.2.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
A.
Regulatory Guide 1.68, "Initial Test Programs for
Water-Cooled Reactor Power Plants."
B.
SRP
3.6.1,
Branch Technical Position ASB 3-1,
"Protection Against Postulated Piping Failures in Fluid Systems
Outside Containment."
C.
SRP
3.6.2,
Branch Technical Position MEB 3-1,
"Postulated Break and Leakage Locations in Fluid System Piping
Outside Containment."
10.2.3
Codes and Standards
A.
ASME Boiler and Pressure Vessel Code.
1.
Section II, "Material Specifications."
2.
Section III, "Rules for
Construction
of
Nuclear Power Plant Components," Division 1.
3.
Section V, "Nondestructive Examination."
Section VIII, "Rules for Construction of Pres-
4.
sure Vessels," Division 1.
10-3
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