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|  SRP Appendix 7-A, Branch Technical Position ICSB
J.
14, "Spurious Withdrawals of Single Control Rods in pressurized
Water Reactors."
SRP Appendix 7-A, Branch Technical Position ICSB
K.
21, "Guidance for Application of Regulatory Guide 1.47."
SRP Appendix 7-A, Branch Technical Position ICSB
L.
22, "Guidance for Application of Regulatory Guide 1.22."
SRP Appendix 7-A, Branch Technical Position ICSB
M.
26, "Requirements for Reactor Protection System Anticipatory
Trips."
Appendix A, "Acceptance Criteria and
N.
SRP 7.1,
Guidelines for Instrumentation and Control Systems Important to
Safety."
SRP 7.1, Appendix B, "Guidance for Evaluation of
O.
Conformance to IEEE Std. 279."
7.2.3
Codes and Standards
A.
ANSI/IEEE 603-1980, "IEEE Standard Criteria for
Safety Systems for Nuclear Power Generating Stations."
B.
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.")
C.
338-1987, "IEEE Standard Criteria for the
IEEE
Periodic Surveillance Testing of Nuclear Power Generating Station
Safety Systems."
D.
379-1977, "IEEE Standard Application of the
IEEE
Single-Failure Criterion to Nuclear Power Generating Station
Class 1E Systems."
(This standard was revised and issued as
ANSI/IEEE 379-1988, "IEEE Standard Application of the Single-
Failure Criterion to Nuclear Power Generating Station Class 1E
Systems.")
E.
IEEE 384-1977, "IEEE Standard Criteria for Inde-
pendence of Class 1E Equipment and Circuits." (This standard was
revised and issued as ANSI/IEEE 384-1981, "IEEE Standard Criteria
for Independence of Class 1E Equipment and Circuits.")
F.
ISA S67.04-1982, "Setpoints for Nuclear Safety-
Related Instrumentation Used in Nuclear Power Plants."
7-6
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