Document: NUREG-0800
Document ID: 243e1ce7-857c-48e4-9eb7-6125311da9be
Document Type: srp
Title: RESIDUAL HEAT REMOVAL (RHR) SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070437.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.7
CFR Part: 
CFR Title: 

Content:
dated April 2, 1993.159 13. Staff Requirements Memorandum, “SECY 93-087 - Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs,” dated July 21, 1993.160 14. NRC Letter to all Holders of Operating Licenses and Construction Permits for Pressurized Water Reactors (PWRs), “Loss of Decay Heat Removal (Generic Letter 88- 17),” October 17, 1988.161 15. NRC Letter to All Holders of Light Water Reactor Operating Licenses and Construction Permits, "Guidance on Developing Acceptable Inservice Testing Programs (Generic Letter 89-04)," April 3, 1989.162 16. NRC Letter to all Pressurized Reactor Licensees and Construction Permit Holders, “Resolution of Generic Issue 70, ‘Power-Operated Relief-Valve and Block Valve Reliability,’ and Generic Issue 94, ‘Additional Low-Temperature Overpressure Protection For Light-Water Reactors, (Generic Letter 90-06)," June 25, 1990.163 17. NRC Letter to all Holders of Operating Licenses or Construction Permits for Pressurized Water Reactors (PWRs), "Resolution of Generic Issue 79, 'Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown' (Generic Letter 92-02)," March 6, 1992.164 18. NRC Bulletin 86-01, "Minimum Flow Logic Problems That Could Disable RHR Pumps," May 23, 1986.165 19. NRC Bulletin 88-04, "Potential Safety-Related Pump Loss," May 5, 1988.166 20. NRC Bulletin 88-08, “Thermal Stresses in Piping Connected to Reactor Coolant Systems,” June 22, 1988 and its Supplements 1 through 3.167 21.10 NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident." 227. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License." 238. NUREG-0737, "Clarification of TMI Action Plan Requirements." 24. NUREG-1316, “Technical Findings and Regulatory Analysis Related to Generic Issue 70 - Evaluation of Power-Operated Relief Valve and Block Valve Reliability in PWR Nuclear Power