Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
e regulator transient. SRP Draft Section 15.5.1 Attachment A - Proposed Changes in Order of Occurrence Item Source Description 15.5.1-17 DRAFT Rev. 2 - April 1996 77. Integrated Impact No. 796 Added a reference to the CE System 80+ FSER as the source of the staff-approved model for transient analyses for the CE System 80+ reactor. 78. Editorial revision Eliminated the reference to another section of the SRP. Renumbered subsequent references. 79. Editorial revision Listed each GDC as a separate reference to make this section consistent with the other SRP sections. 80. Integrated Impact No. 686 This standard may need to be updated to reflect the current version. 81. Integrated Impact No. 686 This standard may need to be updated to reflect the current version. 82. SRP-UDP format item Re-ordered references to be consistent with other SRP sections. DRAFT Rev. 2 - April 1996 15.5.1-18 [This Page Intentionally Left Blank] SRP Draft Section 15.5.1 Attachment B - Cross Reference of Integrated Impacts 15.5.1-19 DRAFT Rev. 2 - April 1996 Integrated Issue SRP Subsections Affected Impact No. 686 Standards may need to be updated to reflect their VI current versions. 795 Add analytical models approved for the ABWR. II and VI 796 Add analytical models approved for the II and VI CE System 80+. 1488 Modified the Acceptance Criteria to include GDC 17 II, III, IV, and VI and revised the Review Procedures to incorporate staff guidance regarding the assumption of LOOP, in addition to a limiting single failure event, for the analysis of reactor coolant pump rotor seizure and reactor coolant pump shaft breaks. 1489 Added a discussion regarding a unique acceptance III and VI criterion for the ABWR’s postulated downscale failure of pressure regulators.