Document: NUREG-0800
Document ID: d2f0cc81-920c-4065-b74b-67114ba68b0e
Document Type: srp
Title: through 7.9 of the SAR. Where exceptions are taken to the guidance provided by regulatory guides, and
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500493.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
16 Containment Design Containment and Severe Accident Branch (SCSB) SRP Section 6.2 GDC 28 Reactivity Limits SRXB SRP Section 4.3 GDC 33 Reactor Coolant Makeup SRXB SRP Chapter 9 GDC 34 Residual Heat Removal SRXB SRP Sections 5.4.6 and 5.4.7 GDC 35 Emergency Core Cooling SRXB SRP Section 6.3 GDC 38 Containment Heat Removal SCSB SRP Section 6.2.2 GDC 41 Containment Atmosphere Cleanup Plant Systems Branch (SPLB) SRP Section 6.5 GDC 44 Cooling Water SPLB SRP Chapter 9 Depending upon the applicant/licensee instrumentation and control system architecture, review of instrumentation and controls for these functions may be an HICB primary review responsibility as part of the review of SAR Chapter 7, or a secondary responsibility supporting other branches' review of other SAR sections. The review methods described in this Appendix should be used as appropriate. The review guidance of Appendix 7.1-B or Appendix 7.1-C should also be applied to I&C systems required for operation of engineered safety feature systems or their essential auxiliary systems. e. Criterion 19 — Control Room "A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. Rev. 4 — June 1997 SRP 7.1-A-15 "Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of