Document: NUREG-0800
Document ID: 924aeba2-7603-48d5-9467-ab37f7d036f0
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A169.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
As an alternative to Category 2 containment sump water temperature instrumentation, either Category 2 residual heat removal heat exchanger inlet or outlet temperature instrumentation is an acceptable alternative for determining containment cooling status. In plants for which the containment cooling function is provided by 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 7-10-13 Revision 6 – August 2016 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. Institute of Electrical and Electronics Engineers, IEEE Std 497, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.” 4. U.S. Nuclear Regulatory Commission, “Clarification of TMI Action Plan Requirements: Requirements for Emergency Response Capability,” NUREG-0737, Supplement 1, January 1983. 5. U.S. Nuclear Regulatory Commission, “Seismic Qualification of Electric Equipment for Nuclear Power Plants,”