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:
ew Procedure added to cover shutdown and low power operations. 160. Integrated Impact # 105 Added a reference to the SRM for SECY 93-087 to support the Review Procedure added to cover shutdown and low power operations. 161. Integrated Impact # 103, 105 and Added a reference to Generic Letter 88-17 to support 108 the new Review Procedure covering RHR concerns related to Mid-loop operations, RHR reliability and RHR suction valve interlock concerns. 162. Integrated Impact # 110. Added a reference covering Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs." This Generic Letter contains guidance on the design of the miniflow systems for the RHR system. 163. Integrated Impact # 109 Added a reference to Generic Letter 90-06 which provides guidance and staff positions on the resolution of Generic Issue 70 “Power Operated Relief Valve and Block Valve Reliability.” 164. Integrated Impact # 109. Added a reference to Generic Letter 92-02 to address the potential for voiding in the reactor vessel head during natural circulation cooldown. 165. Integrated Impact # 110 Added a reference for NRC Bulletin 86-01, "Minimum Flow Logic Problems that Could Disable RHR Pumps." This Bulletin contains guidance on miniflow design considerations including adverse single failure conditions. 166. Integrated Impact #110 Added a reference for NRC Bulletin 88-04, "Potential Safety-Related Pump Loss." This Bulletin contains guidance on miniflow design considerations including parallel pump operation under miniflow conditions. 167. Integrated Impact # 112 Added a reference to NRC Bulletin 88-08 to provide additional information on the review of RHR systems in regard to thermal stratification of unisolable piping connected to the reactor coolant system. SRP Draft Section 5.4.7 Attachment A - Proposed Changes in Order of Occurrence Item Source Description DRAFT Rev. 4 - April 1996 5.4.7-46 168. Integrated Impact # 109 Added a reference to NUREG-1316 which provides