Document: NRC Regulatory Guide
Document ID: bbd6ed7f-058c-4bd2-8849-f708d0179bbf
Document Type: regulatory_guide
Title: Flexible Mitigation Strategies for Beyond-Design-Basis Events + HISTORY - HISTORY 11/2015 – DG-1301 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1316/ML13168A031.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.226
CFR Part: 
CFR Title: 

Content:
red as part of the minimum set of parameters necessary to support strategy implementation. These criteria include the ability to demonstrate the success of the strategies at maintaining the key safety functions as well as indicating imminent or actual core damage to facilitate a decision to manage the response to the event within the EOPs and FSGs or within the Severe Accident Management Guidelines (SAMGs). Section 11.4 of NEI 12-06, Rev. 1A provides that FSGs will be used to supplement (not replace) the existing procedure that establishes the command and control for the event. This section further provides that the existing command and control procedure structure will be used to transition to SAMGs if FLEX mitigation strategies are not successful. Staff Position: Sections 3.2.1.10 and 11.4 provide appropriate coordination between the FSGs and voluntarily maintained SAMGs, retaining command and control direction as defined within the EOPs unless and until a licensee transitions to the use of SAMGs. 8. Guidance for AP-1000 Design Appendix F of NEI 12-06, Rev. 1A provides specific guidance for licensees with reactors of the AP-1000 design on how to satisfy provisions of the aforementioned regulations for sufficient offsite resources to sustain functions indefinitely. Staff Position: The guidance of NEI 12-06, Rev. 1A, Appendix F, provides an acceptable means to meet the requirements of the regulations or license conditions imposing similar requirements. D. IMPLEMENTATION. The purpose of this section is to provide information on how applicants and licensees1 may use this guide and information regarding the NRC’s plans for using this RG. In addition, it describes how the NRC complies with the Backfit Rule found in 10 CFR 50.109(a)(1) or any applicable finality provisions in 10 CFR Part 52. 1 In this section, “licensees” refers to holders of, and “applicants” refers to applicants for, licenses for nuclear power plants under 10 CFR Parts 50 and 52. DG-1301, Page