Document: NUREG-0800
Document ID: ea7ce8f5-32bf-4d8c-a653-e964bff0ef48
Document Type: srp
Title: EMERGENCY CORE COOLING SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070448.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.3
CFR Part: 
CFR Title: 

Content:
April 2, 1993.173 24. Staff Requirements Memorandum, "SECY 93-087 - Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs," dated July 21, 1993.174 25. NRC Letter to all Boiling Water Reactor Licensees, "NUREG-0737 Technical Specifications (Generic Letter No. 83-02)," January 10, 1983.175 26. NRC Letter to all Holders of Operating Licenses or Construction Permits for Pressurized Water Reactors (PWRs), "Loss of Decay Heat Removal (Generic Letter No. 88-17)," October 17, 1988.176 27. 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, 1989.177 28. NRC Bulletin 79-24, "Frozen Lines," September 27, 1979.178 29. NRC Bulletin 80-18, "Maintenance of Adequate Minimum Flow Thru Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture," July 24, 1980.179 30. NRC Bulletin 86-03, "Potential Failure of Multiple ECCS Pumps Due to Single Failure of Air-Operated Valve in Minimum Flow Recirculation Line," October 8, 1986. 180 31. NRC Bulletin 88-04, "Potential Safety-Related Pump Loss," May 5, 1988.181 32. NRC Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems," June 22, 1988 and its Supplements 1 through 3.182 3315. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 6.3-25 DRAFT Rev. 3 - April 1996 3416. NUREG-0737, "Clarification of TMI Action Plan Requirements." 35. NUREG-0927, Revision 1, "Evaluation of Water Hammer Occurrences in Nuclear Power Plants," March 1984.183 36. American National Standard, "Single Failure Criteria for PWR Fluid Systems," ANSI N658 (ANS 51.7).184 DRAFT Rev. 3 - April 1996 6.3-26 BRANCH TECHNICAL POSITION RSB 6-1 CURRENTLY THE RESPONSIBILITY OF THE REACTOR SYSTEMS BRANCH (SRXB)185 PIPING FROM THE RWST (OR BWST) AND CONTAINMENT SUMP(S) TO THE