Document: NUREG-0800
Document ID: 2c839e4a-a342-4e25-9a7c-82d678a0f754
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340657.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
llance and administrative control will be maintained over the vacuum relief devices. 7. Upon request, the SEB will review the design of unique flow-limiting devices which are identified during the CSB review of the containment subcompartments. 8. The CSB reviews the accuracy and range of the instrumentation provided to monitor the post-accident environment. The ICSB, under SRP Section 7.5 and the EQB, under SRP Section 3.11, have review responsibility for the acceptability of, and the qualification test program for the sensing and actuation instrumentation of the plant protection system and the post- accident monitoring instrumentation and recording equipment. IV. EVALUATION FINDINGS The conclusions reached on completion of the review of this SRP section are presented under SRP Section 6.2.1. V. IMPLEMENTATION The following is intended to provide guidance to applicants and-licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides, NUREGs and the following: 1. Revision 2 to Appendix A of this SRP section does not contain any new criteria or guidelines, therefore implementation remains the same and is as stated in Appendix A. 2. LOCA-related pool dynamic loads criteria are implemented on all plants with Mark I containments in accordance with section 5 of NUREG-0661 and supplement 1 to it; for all Mark II containments in accordance with section 3.1 of NUREG-0808 and/or Appendix B of this SRP section; and for all Mark III containment designs in accordance with Section 4 of NUREG-0978. 3. Reactor coolant system safety/relief valve(s) - related pool dynamic loads