Document: NRC Regulatory Guide
Document ID: c256f223-ee35-43e0-82e7-aa7b14469259
Document Type: regulatory_guide
Title: Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors + HISTORY - HISTORY DG-1253 , Proposed Revision 2 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1101/ML110110480.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.79
CFR Part: 
CFR Title: 

Content:
ograms for Water-Cooled Nuclear Power Plants,” Revision 3, issued March 2007 (Ref. 3), describes a method acceptable to the NRC staff for complying with the Commission’s regulations with regard to preoperational testing of nuclear power plant SSCs that perform DG-1253, Page 2 functions important to safety. This guide describes preoperational testing acceptable to the staff specifically for ECCSs in PWRs. This guide is applicable to all PWRs licensed under 10 CFR Part 50 and 10 CFR Part 52. Where a SSC is not part of the specific nuclear plant design, the associated testing would not apply. The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agency’s regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants and licensees. Regulatory guides are not substitutes for regulations and compliance with them is not required. This regulatory guide contains information collection requirements covered by 10 CFR Part 50 and 10 CFR Part 52 that the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0011 and 3150-0151, respectively. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number. The NRC has determined that this Regulatory Guide is not a major rule as designated by the Congressional Review Act and has verified this determination with OMB. The staff will consult the Advisory Committee on Reactor Safeguards concerning this guide before final issuance. B. DISCUSSION The NRC staff concluded that additional guidance should be provided regarding the scope of ECCS preoperational tests identified in RG 1.79, “Preoperational Testing of Emergency Core Cooling Systems for Pressurized-Water Reactors,” issued