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:
ures to address the proper design Review Procedures of the miniflow systems required to ensure ECCS References pump protection. 604 Add an Areas of Review (review interface) to address Areas of Review the concerns of Generic Issue 105 on ISLOCA. Proposed new SRP section 3.12 will address ISLOCA issues. 605 Add Acceptance Criteria and Review Procedures to Areas of Review (review address the capability of the ECCS systems to interfaces) provide injection and core cooling following a station References blackout event. 606 Add Review Procedures to address the ECCS Review Procedures capability to provide reactor coolant system inventory References additions during reduced inventory operations. 661 The BTP cites ANSI N658 with no date specified. BTP RSB 6-1 ANSI N658 is also specified as ANS 58.9. If appropriate specify the reaffirmed version of ANS 58.9. 1001 See integrated impact # 593 for details on actions None. taken in regard to the issues described in this integrated impact. 1017 Update the Acceptance Criteria and other Acceptance Criteria subsections to reflect the requirement of 10 CFR Review Procedures 50.34(f)(2)(xxvi) and NUREG-0737 TMI Action Plant Evaluation Findings item III.D.1.1 related to leakage detection and control. References 1034 Revise the Areas of Review discussion associated Areas of Review (review with TMI Action Plan item I.C.6. regarding verification interfaces) of correct performance of operating activities. 1064 This is a duplicate integrated impact and will not be None. processed further, see integrated impact # 596 for details on the changes necessary to address the issues described in this integrated impact. 1067 Delete the existing citation of TMI Action Plan item Acceptance Criteria II.K.3.10. This item should be reviewed under SRP Review Procedures Section 7.1 as it is primarily related to the reactor trip Evaluation Findings and turbine trip systems. 1072 This integrated impact will not be processed further None due to development of