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|  Code of Federal Regulations
4.5.1
10 CFR 50.55a, "Codes and Standards."
A.
Appendix A, "General Design Criteria
B.
10 CFR 50,
for Nuclear Plants."
"Quality Standards and Records."
1.
GDC 1,
"Reactor Coolant Pressure Boundary."
GDC 14,
2.
Control
System
GDC
26,
3.
Redundancy and Capability."
USNRC Regulatory (Widen, SRP Branch Technical Positions
4.5.2
and Appendices
"Control of Ferrite Con-
Regulatory Guide 1.31,
A.
tent in Stainless Steel Weld Metal."
"Quality Assurance
1.37,
Guide
B.
Regulatory
Requirements for Cleaning of Fluid Systems and Associated Com-
ponents of Water-Cooled Nuclear Power Plants."
"Control of the Use of
1.44,
Regulatory Guide
C.
Sensitized Stainless Steel."
1.85, "Materials Code Case
Guide
D.
Regulatory
Acceptability-ASME Section III, Division 1."
4.5.3
Codes and Standards
A.
ANSI N45.2.1-1973, "Cleaning of Fluid Systems and
Associated Components During Construction Phase of Nuclear Power
Plants."
(This standard was withdrawn on November 21, 1985 and
incorporated into ANSI/ASME NQA-2-1986, "Quality Assurance
Requirements for Nuclear Power Plants")
B.
ASME Boiler and Pressure Vessel Code.
Section II, "Material Specifications."
1.
Section III, "Rules for
Construction
of
2.
Nuclear Power Plant Components," Division 1.
3.
Section XI, "Rules for Inservice Inspection of
Nuclear Power Plant Components."
C.
ASTM A262-86, "Practices for Detecting Suscep-
tibility to Intergranular Attack in Austenitic Stainless Steels.
4-6
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