 |
|||
|
|
|||
|
|
|||
| ||||||||||
|
|  SRP Appendix 7-A, Branch Technical Position ICSB
L.
21, "Guidance for Application of Regulatory Guide 1.47."
SRP Appendix 7-A, Branch Technical Position ICSB
M.
22, "Guidance for Application of Regulatory Guide 1.22."
Appendix A, "Acceptance Criteria and
SRP 7.1,
N.
Guidelines for Instrumentation and Control Systems Important to
Safety."
SRP 7.1, Appendix B, "Guidance for Evaluation of
O.
Conformance to IEEE Std. 279."
7.3.3
Codes and Standards
603-1980, "IEEE Standard Criteria for
ANSI/IEEE
A.
Safety Systems for Nuclear Power Generating Stations."
IEEE 279-1971, "Criteria for Protection Systems
B.
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.")
338-1987, "IEEE Standard Criteria for the
IEEE
C.
Periodic Surveillance Testing of Nuclear Power Generating Station
Safety Systems."
IEEE 379-1977, "IEEE Standard Application of the
D.
Single-Failure Criterion to Nuclear Power Generating Station
(This standard was revised and issued as
Class 1E Systems."
ANSI/IEEE 379-1988, "IEEE Standard Application of the Single-
Failure Criterion to Nuclear Power Generating Station Class 1E
Systems.")
384-1977, "IEEE Standard Criteria for Inde-
E.
IEEE
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.")
ISA S67.04-1982, "Setpoints for Nuclear Safety-
F.
Related Instrumentation Used in Nuclear Power Plants."
Supplemental Information
7.3.4
USNRC "Standard Review Plan," June
NUREG-0800,
A.
1987.
"Engineered Safety Features Sys-
SRP
7.3,
1.
tems."
7-9
|
|
Privacy Statement - Press Release - Copyright Information. - Contact Us |
Click
here for thousands of PDF manuals