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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home About NRC How We Regulate Risk Assessment Current Risk-Informed Activities

Completed Risk-Informed Activities

The following risk-informed activities were removed from the public website because they are no longer active.

FY 2017

Risk Informed Activities Completed or Not Active, FY 2017

  • Risk Prioritization Initiatives (RPI)
  • Emergency Core-Cooling System (ECCS) Requirements: Redefinition of Loss-of-Coolant Accidents (LOCA)
  • Emergency Core Cooling System (ECCS) Requirements: Loss of Coolant Accident and Loss of Offsite Power (ECCS-LOCA/LOOP)
  • Risk-Informed In-service Inspection (ISI)
  • Standard Review Plan, Chapter 19.0 Severe Accidents (NUREG-0800) Staff Review of NuScale Licensing Topical Report on Risk Significance Determination
  • Use of Risk Insights to Enhance Technical Reviews of Design Certification (DC) Applications
  • Revise the Fuel Cycle Oversight Program (RFCOP)
  • Enhance Regulatory Framework for Extended Storage and Transportation
  • Risk Management Regulatory Framework (RMRF)

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FY 2018

Risk Informed Activities Completed or Not Active, FY 2018

  • NRC Grow Your Own PRA Capability
  • Interim Staff Guidance on PRA Technical Adequacy for Advanced Light Water Reactors
  • Methods, Tools and Guidance for Including Digital Systems in Nuclear Power Plant PRAs

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FY 2019

Risk Informed Activities Completed or Not Active, FY 2019

  • Consequential SG Tube Rupture Probability and Consequence Assessment
  • Implementation of Lessons Learned from Uranium Accumulation Event
  • Medical Use of Byproduct Materials 10CFR35 – Medical Event Definitions, Training and Experience, and Clarifying Amendments
  • Increasing License Terms for Uranium Recovery Facilities
  • Aligning the Inspection Hours with the Stage of Decommissioning for Power Reactors

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FY 2020

Risk Informed Activities Completed or Not Active, FY 2020

  • Extension of Timeframe for Uranium Recovery Inspection
  • Multi-Layered National Security Framework and Design Basis Threat

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FY 2021

Risk Informed Activities Completed or Not Active, FY 2021

  • Rulemaking – Cyber Security for Fuel Cycle Facilities
  • Rulemaking Activities
  • Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning Rulemaking
  • Design Compliance Enforcement Discretion (DCED): a Risk-Informed Approach for Addressing Low Risk, Low Safety Significance Design Compliance Issues
  • Risk-Informed Compensatory Measures
  • Accident Sequence Precursor (ASP) Program

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FY 2022

Risk Informed Activities Completed or Not Active, FY 2022

  • RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities (LWRs)
  • PRA Standards Development
  • Industry Peer Review Guidance Development
  • Regulatory Guide 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant Specific Changes to the Licensing Basis
  • NUREG 1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking
  • Achieving the Vision of Becoming a Modern, Risk-Informed Regulator
  • ANS Standard 57.11, "Integrated Safety Assessments for Fuel Cycle Facilities"
  • Rulemaking – Cybersecurity for Fuel Cycle Facilities
  • Rulemaking for Reprocessing Facilities

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FY 2023

Risk Informed Activities Completed or Not Active, FY 2023
 

  • Risk-Informed Reviews of Instrumentation and Control (I&C) Systems and Components:
  • Integrating Risk Insights into the Digital I&C Regulatory Framework
  • Risk-Informed Adversary Timeline Calculations
  • Ensure Force-on-Force (FoF) Scenarios Are Realistic and Reasonable
  • ANS Standard 57.11, "Integrated Safety Assessments for Fuel Cycle Facilities"
  • Rulemaking for Reprocessing Facilities
  • Consolidated Decommissioning Guidance (NUREG-1757)
  • Methodology for Defining Authorized Shielding-Related Specifications of Spent Fuel Storage System Contents

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The ADAMS package for all years is ML23255A028

Page Last Reviewed/Updated Tuesday, April 02, 2024