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
CFR Part: 
CFR Title: 

Content:
s 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 Regulation. "Boiling Water Reactors, Regulatory Guide 1.97, Post-Accident Neutron Flux Monitoring Instrumentation." January 13, 1993. Safety Evaluation by the Office of Nuclear Reactor Regulation. "Pressurized Water Reactors Accumulator Pressure and Volume Instrumentation-Relaxation of Regulatory Guide 1.97 Environmental Qualification Requirements." January 21, 1992. Safety Evaluation by the Office of Nuclear Reactor Regulation. "Pressurized Water Reactors Containment Sump Water Temperature Instrumentation Regulatory Guide 1.97." November 22, 1993. Rev. 4 — June 1997 Appendix 7-A BTP HICB-10-10