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|  1.62, "Manual Initiation of Pro-
Guide
D.
Regulatory
tection Actions."
Regulatory Guide 1.68, "Initial Test Programs for
E.
Water Cooled Nuclear Power Plants."
1.75, "Physical Independence of
Guide
F.
Regulatory
Electric Systems."
1.105, "Instrument Setpoints for
Guide
G.
Regulatory
Safety-Related Systems."
"Periodic Testing of
Guide
1.118,
H.
Regulatory
Electric Power and Protection Systems."
1.153, "Criteria for Power,
Guide
I.
Regulatory
Instrumentation, and Control Portions of Safety Systems."
SRP Appendix 7-A, Branch Technical Position ICSB
J.
21, "Guidance for Application of Regulatory Guide 1.47."
K.
SRP Appendix 7-A, Branch Technical Position ICSB
22, "Guidance for Application of Regulatory Guide 1.22."
Appendix A, "Acceptance Criteria and
L.
SRP 7.1,
Guidelines for Instrumentation and Control Systems Important to
Safety."
SRP 7.1, Appendix B, "Guidance for Evaluation of
M.
Conformance to IEEE Std. 279."
Codes and Standards
7.4.3
ANSI/IEEE 603-1980, "IEEE Standard Criteria for
A.
Safety Systems for Nuclear Power Generating Stations."
B.
ASME Boiler and Pressure Vessel Code, Section XI,
"Rules for Inservice Inspection of Nuclear Power Plant Com-
ponents."
C.
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-
crating Stations.")
338-1987, "IEEE Standard Criteria for the
D.
IEEE
Periodic Surveillance Testing of Nuclear Power Generating Station
Safety Systems."
7-11
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