Document: NUREG-0800
Document ID: 5c379bc2-cb0b-42ca-93af-dedf43c6cb30
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500542.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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CFR Title: 

Content:
ger inlet or outlet temperature instrumentation is an acceptable alternative. Makeup flow/letdown flow/VCT level Category, Direct measurement Category 3 instrumentation is an acceptable alternative to Category 2 instrumentation if the charging and letdown lines are isolated with an accident signal and no credit is taken for indication of these variables in post-accident procedures, emergency procedures, or functional recovery guidelines. Radiation exposure rate & variables used to monitor airborne radioactive materials released from plant Category If the instrument is located in a mild environment and is not part of a safety system, Category 3 instrumentation is an acceptable alternative to Category 2 instrumentation. Appendix 7-A Rev. 4 — June 1997 BTP HICB-10-9 C. References General Electric Report NEDO-31558-A. "Position on NRC Regulatory Guide 1.97, Revision 3, Requirement for Post-Accident Neutron Monitoring System." March 1993. NUREG 0737 Supplement 1. "Clarification of TMI Action Plan Requirements-Requirements for Emergency Response Capability." January 1983. Regulatory Guide 1.100. "Seismic Qualification of Electric Equipment for Nuclear Power Plants." Revision 2, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, June 1988 Regulatory Guide 1.75. "Physical Independence of Electric Systems," Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1978. Regulatory Guide 1.97. "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." Revision 3, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 1983. Regulatory Guide 1.97. "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." Revision 2, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, December 1980. Safety Evaluation by the Office of Nuclear Reactor