Document: NUREG-0800
Document ID: 43123a17-321c-4751-b3ba-9ba5e9b0b364
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A726.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
y the recirculation spray system, either Category 2 recirculation spray system heat exchanger inlet or outlet temperature instrumentation is an acceptable alternative. Makeup flow/letdown flow/ volume control tank (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 and 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. BTP 7-10-12 Draft Revision 6 – August 2015 C. REFERENCES 1. General Electric Report NEDO-31558-A, “Position on NRC RG 1.97, Revision 3, Requirement for Post-Accident Neutron Monitoring System,” March 1993. 2. General Electric Report, NEDO-33160-A, Revision 1, “Regulatory Relaxation for the Post Accident SRV Position Indication System,” October 2006. 3. IEEE Std 497, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.” 4. NUREG-0737, Supplement 1, “Clarification of TMI Action Plan Requirements: Requirements for Emergency Response Capability,” January 1983. 5. RG 1.100, “Seismic Qualification of Electric Equipment for Nuclear Power Plants.” 6. RG 1.75, “Criteria for Independence of Electrical Safety Systems.” 7. RG 1.97, Revision 2, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident.” 8. RG 1.97, Revision 3, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident.” 9. RG 1.97, Revision 4,