{"description":"Documents matching 'risk assessment severe accident information'","count":2476,"total_pages":50,"next_page_url":"https://www.federalregister.gov/api/v1/documents?conditions%5Bterm%5D=risk+assessment+severe+accident+information&format=json&page=2","results":[{"title":"Interim Staff Guidance: Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DRA-ISG-2026-01, \"Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications\" to clarify the scope and depth of the NRC staff review of the description of risk assessment and severe accident information in the Preliminary Safety Analysis Report (PSAR) for a light-water power reactor (LWR) construction permit (CP) application that uses risk assessment and severe accident information. The NRC is aware of one applicant's interest in submitting a CP application within the next few years, and this guidance is applicable to the review of all applications for a CP for a LWR but not to non-LWR applications.","document_number":"2026-01756","html_url":"https://www.federalregister.gov/documents/2026/01/29/2026-01756/interim-staff-guidance-content-of-risk-assessment-and-severe-accident-information-in-light-water","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-01-29/pdf/2026-01756.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-01756.pdf?1769607912","publication_date":"2026-01-29","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"issuing Interim Staff Guidance (ISG) DRA-ISG-2026-01, “Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications” to clarify the scope and depth of the NRC staff review of the description of risk assessment and severe accident information in the Preliminary Safety Analysis Report (PSAR) for a light-water power reactor (LWR) construction permit (CP) application that uses risk assessment and severe accident information. The NRC is aware of one applicant's interest in submitting a CP application"},{"title":"Draft Interim Staff Guidance: Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) \"Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications.\" This draft ISG clarifies the scope and depth of the NRC staff review of the content of risk assessment and severe accident information in a construction permit (CP) application for a light-water power reactor. The purpose of this draft ISG is to clarify existing guidance in NUREG-0800, \"Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-0800, formerly issued as NUREG-75 087),\" (\"the SRP\"; Ref. 1).","document_number":"2025-00989","html_url":"https://www.federalregister.gov/documents/2025/01/16/2025-00989/draft-interim-staff-guidance-content-of-risk-assessment-and-severe-accident-information-in","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2025-01-16/pdf/2025-00989.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2025-00989.pdf?1736948747","publication_date":"2025-01-16","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"comment. \n \n \n SUMMARY: \n \n The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) “Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications.” This draft ISG clarifies the scope and depth of the NRC staff review of the content of risk assessment and severe accident information in a construction permit (CP) application for a light-water power reactor. The purpose of this draft ISG is to clarify existing guidance in NUREG-0800,"},{"title":"Accidental Release Prevention Requirements: Risk Management Programs Under the Clean Air Act; Common Sense Approach to Chemical Accident Prevention","type":"Proposed Rule","abstract":"The U.S. Environmental Protection Agency (EPA or Agency) is proposing to amend its Risk Management Program (RMP) regulations by making several proposed changes to the 2024 Safer Communities by Chemical Accident Prevention (SCCAP) rule. The proposed revisions include changes to provisions relating to safer technology and alternatives analyses, information availability, third-party audits, employee participation, community and emergency responder notification, stationary source siting, natural hazards, power loss, declined recommendations documentation, emergency response exercises, process safety information (PSI) and recognized and generally accepted good engineering practices (RAGAGEP), deregistration form information collection, hot work permit retention, and the retail facility definition. These proposed amendments seek to improve chemical process safety by avoiding duplicative requirements, realigning RMP requirements with Occupational Safety and Health Administration (OSHA) Process Safety Management (PSM) requirements, and eliminating unnecessary burdens placed on facilities where there is not specific data available to show that the current RMP standards would reduce or have reduced the number of accidental releases.","document_number":"2026-03633","html_url":"https://www.federalregister.gov/documents/2026/02/24/2026-03633/accidental-release-prevention-requirements-risk-management-programs-under-the-clean-air-act-common","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-02-24/pdf/2026-03633.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-03633.pdf?1771854312","publication_date":"2026-02-24","agencies":[{"raw_name":"ENVIRONMENTAL PROTECTION AGENCY","name":"Environmental Protection Agency","id":145,"url":"https://www.federalregister.gov/agencies/environmental-protection-agency","json_url":"https://www.federalregister.gov/api/v1/agencies/145","parent_id":null,"slug":"environmental-protection-agency"}],"excerpts":"document summarizing the source's risk management program—called a risk management plan (RMP). \n \n The EPA's risk management program requirements include conducting a worst-case scenario analysis and a review of accident history, coordinating emergency response procedures with local response organizations, conducting a hazard assessment, documenting a management system, implementing a prevention program and an emergency response program, and submitting a risk management plan that addresses all aspects of the risk management program for all covered"},{"title":"Voluntary Adoption of Revised Design Basis Accident Dose Criteria","type":"Proposed Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking, dated November 23, 2019, submitted by John G. Parillo. The petition requested that the NRC develop a rule that would allow nuclear power plant licensees to voluntarily adopt a revised accident dose acceptance criteria for the control room, exclusion area boundary, and the low population zone outer boundary. The petition further requested revisions to clarify footnotes discussing these dose acceptance criteria in the applicable regulations. The NRC docketed the petition on February 19, 2020, and assigned it Docket No. PRM-50-121. The NRC is denying the petition because the information presented does not support rulemaking and the proposed changes are not necessary to provide reasonable assurance of adequate protection of public health and safety.","document_number":"2025-14146","html_url":"https://www.federalregister.gov/documents/2025/07/28/2025-14146/voluntary-adoption-of-revised-design-basis-accident-dose-criteria","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2025-07-28/pdf/2025-14146.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2025-14146.pdf?1753447513","publication_date":"2025-07-28","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"engineered safety features to reduce likelihood of severe accidents, emergency planning) to minimize risk of public exposure following an accident. Research studies (\n e.g., \n NUREG-1935, “State-of-the-Art Reactor Consequence Analysis (SOARCA) Report;” NUREG-1150, “Severe Accident Risks: An Assessment of Five U.S. Nuclear Power Plants;” and the ongoing Level 3 probabilistic risk assessment project) and licensing experience demonstrate that these defense-in-depth measures maintain an appropriately low risk of radiation exposure to the public.\n \n \n Regarding"},{"title":"Pipeline Safety: Information Collection Activities","type":"Notice","abstract":"In accordance with the Paperwork Reduction Act of 1995, PHMSA invites comments on proposed revisions to incident, accident, and annual report forms for gas and hazardous liquid (carbon dioxide) pipeline facilities, as well as the National Pipeline Mapping System information collection.","document_number":"2026-12315","html_url":"https://www.federalregister.gov/documents/2026/06/18/2026-12315/pipeline-safety-information-collection-activities","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-06-18/pdf/2026-12315.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-12315.pdf?1781700319","publication_date":"2026-06-18","agencies":[{"raw_name":"DEPARTMENT OF TRANSPORTATION","name":"Transportation Department","id":492,"url":"https://www.federalregister.gov/agencies/transportation-department","json_url":"https://www.federalregister.gov/api/v1/agencies/492","parent_id":null,"slug":"transportation-department"}],"excerpts":"relevant production data is captured for accident analysis. \n PHMSA proposes to remove Question D1a, which requires operators to specify the type of wildlife impact resulting from an accident. PHMSA has determined that this information is not necessary for incident analysis. \n PHMSA proposes to remove Question D3, which asks operators to indicate if a long-term impact assessment is planned or underway. Because environmental remediation and assessments generally fall outside of the scope of PHMSA's accident analysis and are overseen by local, State"},{"title":"Licensing Requirements for Microreactors and Other Reactors With Comparable Risk Profiles","type":"Proposed Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to establish a risk-informed and performance- based regulatory framework for rapid licensing of new microreactors and other reactors with comparable risk profiles and for high-volume deployment of these reactors. The proposed rule would provide a flexible set of licensing pathways, reduce regulatory burden, and ensure that safety and security requirements remain commensurate with the potential hazards posed by these facilities.","document_number":"2026-08550","html_url":"https://www.federalregister.gov/documents/2026/05/01/2026-08550/licensing-requirements-for-microreactors-and-other-reactors-with-comparable-risk-profiles","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-05-01/pdf/2026-08550.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-08550.pdf?1777553125","publication_date":"2026-05-01","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"” \n Proposed § 57.7, “Completeness and accuracy of information,” would govern the completeness and accuracy of information provided to the NRC. These requirements would be equivalent to those in §§ 50.9 and 52.6, both entitled “Completeness and accuracy of information.” \n Proposed § 57.8, “Information collection requirements: OMB approval,” would establish requirements for information collection requirements and OMB approval. These requirements would be equivalent to those in § 50.8, “Information collection requirements: OMB approval.” \n Proposed"},{"title":"Accidental Release Prevention Requirements: Risk Management Programs Under the Clean Air Act; Safer Communities by Chemical Accident Prevention","type":"Rule","abstract":"The Environmental Protection Agency (EPA) is amending its Risk Management Program (RMP) regulations as a result of Agency review. The revisions include several changes and amplifications to the accident prevention program requirements, enhancements to the emergency preparedness requirements, improvements to the public availability of chemical hazard information, and several other changes to certain regulatory definitions or points of clarification. As major and other serious and concerning RMP accidents continue to occur, the record shows and EPA believes that this final rule will help further protect human health and the environment from chemical hazards through advancement of process safety based on lessons learned. These amendments seek to improve chemical process safety; assist in planning, preparedness, and response to Risk Management Program-reportable accidents; and improve public awareness of chemical hazards at regulated sources. While many of the provisions of this final rule reinforce each other, it is EPA's intent that each one is merited on its own, and thus severable.","document_number":"2024-04458","html_url":"https://www.federalregister.gov/documents/2024/03/11/2024-04458/accidental-release-prevention-requirements-risk-management-programs-under-the-clean-air-act-safer","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2024-03-11/pdf/2024-04458.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2024-04458.pdf?1709905524","publication_date":"2024-03-11","agencies":[{"raw_name":"ENVIRONMENTAL PROTECTION AGENCY","name":"Environmental Protection Agency","id":145,"url":"https://www.federalregister.gov/agencies/environmental-protection-agency","json_url":"https://www.federalregister.gov/api/v1/agencies/145","parent_id":null,"slug":"environmental-protection-agency"}],"excerpts":"and other serious and concerning RMP accidents have continued to occur. EPA anticipates that promulgation and implementation of this final rule will reduce the risk of such accidents and the severity of the impacts when they occur. RMP accident data show past accidents have generated highly variable impacts, so the impacts of future accidents are difficult to predict. Nevertheless, it is clear from RMP accident data \n 1 \n \n and other relevant data from RMP regulated industry sectors,\n 2 \n \n that chemical accidents can impose substantial costs on firms"},{"title":"Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors","type":"Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations by adding a risk-informed, performance-based, and technology-inclusive regulatory framework for commercial nuclear plants in response to the Nuclear Energy Innovation and Modernization Act (NEIMA). The current application and licensing requirements were primarily developed to address license requests concerning light water- cooled reactors and operational requirements for those types of reactors. This final rule responds to NEIMA by creating an alternative, technology-inclusive regulatory framework to accommodate licensing of future commercial nuclear plants, including advanced reactor designs that may not employ light-water technology.","document_number":"2026-06048","html_url":"https://www.federalregister.gov/documents/2026/03/30/2026-06048/risk-informed-technology-inclusive-regulatory-framework-for-advanced-reactors","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-03-30/pdf/2026-06048.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-06048.pdf?1774615514","publication_date":"2026-03-30","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"comprehensive risk metric or set of metrics and associated risk performance objectives against which calculated values of the risk metrics are compared. The comprehensive risk metrics or set of metrics and associated risk performance objectives support a performance-based approach to developing an appropriate combination of design features and programmatic controls to prevent or mitigate LBEs other than DBAs. The applicant must propose the comprehensive risk metric or set of metrics and associated risk performance objectives, and the comprehensive risk metric"},{"title":"Pacific Gas & Electric Company; Diablo Canyon Power Plant, Unit Nos. 1 and 2; Petition","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is giving notice that by petition dated March 4, 2024, as supplemented on June 7, 2024, San Luis Obispo Mothers for Peace, Friends of the Earth, and Environmental Working Group (the petitioners) requested that the NRC exercise its supervisory authority to order the immediate closure of Diablo Canyon Nuclear Power Plant, Unit Nos. 1 and 2 (Diablo Canyon) due to \"the unacceptable risk of a seismically induced severe accident.\" The Commission referred the request to the enforcement petition process under NRC regulations. The petitioners' request is included in the SUPPLEMENTARY INFORMATION section of this document.","document_number":"2024-19630","html_url":"https://www.federalregister.gov/documents/2024/09/03/2024-19630/pacific-gas-and-electric-company-diablo-canyon-power-plant-unit-nos-1-and-2-petition","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2024-09-03/pdf/2024-19630.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2024-19630.pdf?1725021921","publication_date":"2024-09-03","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"(Diablo Canyon) due to “the unacceptable risk of a seismically induced severe accident.” The Commission referred the request to the enforcement petition process under NRC regulations. The petitioners' request is included in the \n SUPPLEMENTARY INFORMATION \n section of this document.\n \n \n \n DATES: \n September 3, 2024. \n \n \n ADDRESSES: \n Please refer to Docket ID NRC-2024-0148 when contacting the NRC about the availability of information regarding this document. You may obtain publicly available information related to this document using any of the"},{"title":"25-Hour Cockpit Voice Recorder (CVR) Requirement, New Aircraft Production","type":"Rule","abstract":"This final rule increases the recording time of cockpit voice recorders (CVRs) from the currently mandated 2 hours to 25 hours for all affected future manufactured aircraft. This action provides accident investigators, aircraft operators, and civil aviation authorities with substantially more CVR data to help determine the probable causes of incidents and accidents and prevent future incidents and accidents. The action will also align the Federal Aviation Administration's (FAA) regulations more closely with existing international requirements.","document_number":"2026-02110","html_url":"https://www.federalregister.gov/documents/2026/02/02/2026-02110/25-hour-cockpit-voice-recorder-cvr-requirement-new-aircraft-production","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-02-02/pdf/2026-02110.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-02110.pdf?1769780739","publication_date":"2026-02-02","agencies":[{"raw_name":"DEPARTMENT OF TRANSPORTATION","name":"Transportation Department","id":492,"url":"https://www.federalregister.gov/agencies/transportation-department","json_url":"https://www.federalregister.gov/api/v1/agencies/492","parent_id":null,"slug":"transportation-department"},{"raw_name":"Federal Aviation Administration","name":"Federal Aviation Administration","id":159,"url":"https://www.federalregister.gov/agencies/federal-aviation-administration","json_url":"https://www.federalregister.gov/api/v1/agencies/159","parent_id":492,"slug":"federal-aviation-administration"}],"excerpts":"aircraft. This action provides accident investigators, aircraft operators, and civil aviation authorities with substantially more CVR data to help determine the probable causes of incidents and accidents and prevent future incidents and accidents. The action will also align the Federal Aviation Administration's (FAA) regulations more closely with existing international requirements. \n \n \n DATES: \n February 2, 2026. \n \n \n ADDRESSES: \n \n For information on where to obtain copies of rulemaking documents and other information related to this final rule"},{"title":"Initial Decision That Certain Frontal Driver Air Bag Inflators Manufactured by Jilin Province Detiannuo Safety Technology Co., Ltd. (DTN) Contain a Safety Defect","type":"Notice","abstract":"NHTSA has made an initial decision that certain air bag inflators manufactured by DTN contain a defect related to motor vehicle safety. Available information demonstrates that the inflators were imported into the United States by unknown importers (likely illegally). NHTSA is aware of twelve instances in which the inflators have ruptured in vehicles in the United States, resulting in ten fatalities and two severe injuries. Following this initial decision, NHTSA is required by statute to seek public comment and allow the manufacturer an opportunity to dispute the initial decision. After review of any comments or additional relevant information, should NHTSA makes a final determination that the subject inflators contain a defect related to motor vehicle safety, the sale of the inflators (whether separately or installed in an air bag module) in the United States would be illegal.","document_number":"2026-06620","html_url":"https://www.federalregister.gov/documents/2026/04/06/2026-06620/initial-decision-that-certain-frontal-driver-air-bag-inflators-manufactured-by-jilin-province","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-04-06/pdf/2026-06620.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-06620.pdf?1775220313","publication_date":"2026-04-06","agencies":[{"raw_name":"DEPARTMENT OF TRANSPORTATION","name":"Transportation Department","id":492,"url":"https://www.federalregister.gov/agencies/transportation-department","json_url":"https://www.federalregister.gov/api/v1/agencies/492","parent_id":null,"slug":"transportation-department"},{"raw_name":"National Highway Traffic Safety Administration","name":"National Highway Traffic Safety Administration","id":345,"url":"https://www.federalregister.gov/agencies/national-highway-traffic-safety-administration","json_url":"https://www.federalregister.gov/api/v1/agencies/345","parent_id":492,"slug":"national-highway-traffic-safety-administration"}],"excerpts":"resulted in fatal injuries to the driver, for a total of twelve crashes involving ten deaths and two severe injuries. \n \n As part of its investigation, NHTSA sent an information request to DTN on December 23, 2025 asking for information about the subject components.\n 5 \n \n DTN responded on February 3, 2026 with certain production and component data.\n 6 \n \n NHTSA sent DTN a supplemental information request on March 6, 2026 seeking additional information.\n 7 \n \n DTN failed to respond by the due date of March 23, 2023.\n \n \n \n 5 \n \n https://static.nhtsa"},{"title":"Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors","type":"Proposed Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is proposing to revise the NRC's regulations by adding a risk-informed, performance- based, and technology-inclusive regulatory framework for commercial nuclear plants in response to the Nuclear Energy Innovation and Modernization Act (NEIMA). The NRC plans to hold a public meeting to promote full understanding of the proposed rule and facilitate public comments.","document_number":"2024-23434","html_url":"https://www.federalregister.gov/documents/2024/10/31/2024-23434/risk-informed-technology-inclusive-regulatory-framework-for-advanced-reactors","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2024-10-31/pdf/2024-23434.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2024-23434.pdf?1729687518","publication_date":"2024-10-31","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"comprehensive risk metric or set of metrics and associated risk performance objectives must provide an appropriate level of safety. Comprehensive risk metrics should consist of a proposed plant risk metric or set of proposed risk metrics that approximate the total, overall risk from the facility and that address the range of possible plant configurations and associated internal and external hazards to the extent practicable. The associated risk performance objectives are preestablished, indicative values of the comprehensive risk metrics that are"},{"title":"Enhancing Surface Cyber Risk Management","type":"Proposed Rule","abstract":"The Transportation Security Administration (TSA) is proposing to impose cyber risk management (CRM) requirements on certain pipeline and rail owner/operators and a more limited requirement, on certain over-the-road bus (OTRB) owner/operators, to report cybersecurity incidents. With the proposed addition of requirements applicable to pipeline facilities and systems, TSA is also proposing that a requirement to have a Physical Security Coordinator and report significant physical security concerns be extended to the same facilities and systems. Finally, TSA is proposing clarifications and reorganization of other regulatory requirements necessitated by these changes.","document_number":"2024-24704","html_url":"https://www.federalregister.gov/documents/2024/11/07/2024-24704/enhancing-surface-cyber-risk-management","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2024-11-07/pdf/2024-24704.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2024-24704.pdf?1730900722","publication_date":"2024-11-07","agencies":[{"raw_name":"DEPARTMENT OF HOMELAND SECURITY","name":"Homeland Security Department","id":227,"url":"https://www.federalregister.gov/agencies/homeland-security-department","json_url":"https://www.federalregister.gov/api/v1/agencies/227","parent_id":null,"slug":"homeland-security-department"},{"raw_name":"Transportation Security Administration","name":"Transportation Security Administration","id":494,"url":"https://www.federalregister.gov/agencies/transportation-security-administration","json_url":"https://www.federalregister.gov/api/v1/agencies/494","parent_id":227,"slug":"transportation-security-administration"}],"excerpts":"vulnerability assessments and security planning. \n See \n TSA-2016-0002-0013, available at \n https://www.regulations.gov \n under Docket No. TSA-2016-0002. This commenter indicated that, at the time of the comment, the Rail Information Security Committee of the Association of American Railroads focuses on cybersecurity and the “industry's physical and cyber security committees annually conduct risk assessments using “relevant security information” from a variety of resources. As part of this effort, they evaluate specific information technology and"},{"title":"Pipeline Safety: Breakout Tank Inspection Rule","type":"Proposed Rule","abstract":"Breakout tanks are used to \"relieve surges in a hazardous liquid pipeline system\" or to \"receive and store hazardous liquid transported by a pipeline for reinjection and continued transportation by pipeline.\" American Petroleum Institute Standard 653 (API Std 653) sets industry standards for the inspection, repair, alteration, and reconstruction of aboveground storage tanks. PHMSA currently incorporates the 3rd edition of API Std 653 (issued December 2001) by reference into its regulations for breakout tanks. In this rulemaking, PHMSA is proposing to update its regulations for breakout tanks to incorporate the 5th edition of API Std 653 (issued November 2014) by reference. As a key part of this, PHMSA is proposing to authorize the use of risk-based inspection (RBI) procedures for establishing the inspection intervals of in-service breakout tanks.","document_number":"2026-10969","html_url":"https://www.federalregister.gov/documents/2026/06/02/2026-10969/pipeline-safety-breakout-tank-inspection-rule","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-06-02/pdf/2026-10969.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-10969.pdf?1780317916","publication_date":"2026-06-02","agencies":[{"raw_name":"DEPARTMENT OF TRANSPORTATION","name":"Transportation Department","id":492,"url":"https://www.federalregister.gov/agencies/transportation-department","json_url":"https://www.federalregister.gov/api/v1/agencies/492","parent_id":null,"slug":"transportation-department"},{"raw_name":"Pipeline and Hazardous Materials Safety Administration","name":"Pipeline and Hazardous Materials Safety Administration","id":408,"url":"https://www.federalregister.gov/agencies/pipeline-and-hazardous-materials-safety-administration","json_url":"https://www.federalregister.gov/api/v1/agencies/408","parent_id":492,"slug":"pipeline-and-hazardous-materials-safety-administration"}],"excerpts":"elect to use an RBI would have to make and retain records documenting the risk assessment in accordance with the 5th edition of API Std 653. \n \n PHMSA will submit information collection requests to OMB for approval based on the requirements in this rule. The following information is provided for each information collection request: (1) title of the information collection; (2) OMB control number; (3) current expiration date; (4) type of request; (5) abstract of the information collection activity; (6) description of affected public; (7) estimate of"},{"title":"Implementation of the National Environmental Policy Act","type":"Proposed Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is proposing to revise the NRC's regulations to streamline and modernize its implementation of the National Environmental Policy Act of 1969, as amended (NEPA). These proposed revisions address Presidential directives in Executive Order (E.O.) 14300, \"Ordering the Reform of the Nuclear Regulatory Commission,\" E.O. 14154, \"Unleashing American Energy,\" Executive Order 14192, \"Unleashing Prosperity Through Deregulation,\" Executive Order 14270, \"Zero-Based Regulatory Budgeting to Unleash American Energy;\" recent amendments to NEPA; and relevant NEPA case law. In addition, these proposed revisions aim to reduce regulatory burden while complying with NEPA requirements. The proposed rule would narrow the scope of NEPA reviews to effects (or impacts) within the NRC's substantive statutory authority; revise definitions; update procedures for determining the level of NEPA review; establish new categorical exclusions; provide new flexibility for licensees, applicants, and petitioners for rulemaking to submit environmental information; and remove outdated requirements and consolidate content provisions to improve clarity and efficiency. Consistent with section 102(2)(B) of NEPA and E.O. 14300, the NRC consulted with the Council on Environmental Quality (CEQ) during the development of this proposed rule. The NRC is issuing new draft guidance NUREG-2270, \"Environmental Review Guidance for U.S. Nuclear Regulatory Commission Actions,\" for the implementation of the proposed requirements in this rulemaking. The NRC staff will carry out its NEPA responsibilities consistent with the proposed requirements in this rulemaking and the guidance in NUREG-2270.","document_number":"2026-13687","html_url":"https://www.federalregister.gov/documents/2026/07/07/2026-13687/implementation-of-the-national-environmental-policy-act","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-07-07/pdf/2026-13687.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-13687.pdf?1783341914","publication_date":"2026-07-07","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"of the proposed amendment renders a severe accident mitigation design alternative previously rejected in the earlier environmental assessment to become cost beneficial, or results in the identification of new severe accident mitigation design alternatives, in which case the costs and benefits of new severe accident mitigation design alternatives and the bases for not incorporating new severe accident mitigation design alternatives in the design certification must be addressed. \n (d) An environmental assessment for a manufacturing license under subpart"},{"title":"Public Protective Actions During a General Emergency","type":"Proposed Rule","abstract":"The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process issues raised in a petition for rulemaking (PRM), PRM-50-123, submitted by Thomas McKenna. The petitioner requested that the NRC amend its regulations to ensure protective actions in the event of a general emergency will likely do more good than harm.","document_number":"2025-13606","html_url":"https://www.federalregister.gov/documents/2025/07/21/2025-13606/public-protective-actions-during-a-general-emergency","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2025-07-21/pdf/2025-13606.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2025-13606.pdf?1752842711","publication_date":"2025-07-21","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"disagrees with the comment. Following the Fukushima Dai-ichi reactor accident, the NRC developed NUREG-2201, “Probabilistic Risk Assessment and Regulatory Decisionmaking: Some Frequently Asked Questions,” to address complaints that probabilistic risk assessment-based estimates of the likelihood of major accidents were significantly smaller than simple statistical estimates based on international events (notably the accidents at Three Mile Island, Chernobyl, and Fukushima). Plant risk is heavily dependent on plant-specific details, and major safety improvements"},{"title":"Maine Yankee Atomic Power Company; Independent Spent Fuel Storage Installation; Exemption; Safety Evaluation and Environmental Assessment With Finding of No Significant Impact","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is issuing three exemptions requested by Maine Yankee Atomic Power Company (Maine Yankee). The requested exemptions are from NRC regulations that require compliance with the terms, conditions, and specifications of Certificate of Compliance (CoC) No. 1015 for the NAC-UMS[supreg] Universal Storage System at Maine Yankee's Independent Spent Fuel Storage Installation (ISFSI). Maine Yankee currently stores sixty NAC- UMS[supreg] Systems under Amendment No. 6 to CoC No. 1015. In order to adopt Amendment No. 9 to CoC No. 1015, Maine Yankee is requesting the continuation of three previously approved exemptions.","document_number":"2025-02253","html_url":"https://www.federalregister.gov/documents/2025/02/05/2025-02253/maine-yankee-atomic-power-company-independent-spent-fuel-storage-installation-exemption-safety","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2025-02-05/pdf/2025-02253.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2025-02253.pdf?1738676716","publication_date":"2025-02-05","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"requesting the continuation of three previously approved exemptions. \n \n \n DATES: \n The environmental assessment (EA) and finding of no significant impact (FONSI) referenced in this document are available on February 5, 2025. The exemptions take effect on February 5, 2025. \n \n \n ADDRESSES: \n Please refer to Docket ID NRC-2024-0184 when contacting the NRC about the availability of information regarding this document. You may obtain publicly available information related to this document using any of the following methods: \n \n • \n Federal Rulemaking Website:"},{"title":"Duke Energy Carolinas, LLC; McGuire Nuclear Station, Units 1 and 2; Exemption","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request dated August 18, 2025, from Duke Energy Carolinas, LLC, to allow the use of AXIOM[supreg] fuel cladding at McGuire Nuclear Station, Units 1 and 2. Current NRC regulations limit applicability to the use of fuel rod cladding with zircaloy or ZIRLOTM.","document_number":"2026-05254","html_url":"https://www.federalregister.gov/documents/2026/03/18/2026-05254/duke-energy-carolinas-llc-mcguire-nuclear-station-units-1-and-2-exemption","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-03-18/pdf/2026-05254.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-05254.pdf?1773751511","publication_date":"2026-03-18","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"probability or consequences of an accident previously evaluated? \n \n Response: \n No.\n \n The proposed exemption to allow the use of AXIOM® fuel rod cladding does not involve a significant increase in the probability or consequences of an accident previously evaluated. \n For the set of previously evaluated accidents, their probability is governed by the failure or malfunction of equipment or components other than the fuel rod cladding. The fuel rod cladding itself is not an accident initiator and does not affect the accident probability. Therefore, the"},{"title":"Duke Energy Carolinas, LLC; Catawba Nuclear Station, Unit 1; Exemption","type":"Notice","abstract":"The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request dated August 18, 2025, from Duke Energy Carolinas, LLC, to allow the use of AXIOM[supreg] fuel cladding at Catawba Nuclear Station, Unit 1. Current NRC regulations limit applicability to the use of fuel rod cladding with zircaloy or ZIRLOTM.","document_number":"2026-05255","html_url":"https://www.federalregister.gov/documents/2026/03/18/2026-05255/duke-energy-carolinas-llc-catawba-nuclear-station-unit-1-exemption","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2026-03-18/pdf/2026-05255.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2026-05255.pdf?1773751511","publication_date":"2026-03-18","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"probability or consequences of an accident previously evaluated? \n \n Response: \n No.\n \n The proposed exemption to allow the use of AXIOM® fuel rod cladding does not involve a significant increase in the probability or consequences of an accident previously evaluated. \n \n For the set of previously evaluated accidents, their probability is governed by the failure or malfunction of equipment or components other than the fuel rod cladding. The fuel rod cladding itself is not an accident initiator and does not affect the accident probability. Therefore, the"},{"title":"726th Meeting of the Advisory Committee on Reactor Safeguards (ACRS)","type":"Notice","abstract":null,"document_number":"2025-08714","html_url":"https://www.federalregister.gov/documents/2025/05/16/2025-08714/726th-meeting-of-the-advisory-committee-on-reactor-safeguards-acrs","pdf_url":"https://www.govinfo.gov/content/pkg/FR-2025-05-16/pdf/2025-08714.pdf","public_inspection_pdf_url":"https://public-inspection.federalregister.gov/2025-08714.pdf?1747313114","publication_date":"2025-05-16","agencies":[{"raw_name":"NUCLEAR REGULATORY COMMISSION","name":"Nuclear Regulatory Commission","id":383,"url":"https://www.federalregister.gov/agencies/nuclear-regulatory-commission","json_url":"https://www.federalregister.gov/api/v1/agencies/383","parent_id":null,"slug":"nuclear-regulatory-commission"}],"excerpts":"meeting.\n \n \n 8:35 a.m.-10:30 a.m.: Draft Interim Staff Guidance: Content of Risk Assessment and Severe Accident Information in Light-Water Power Reactor Construction Permit Applications \n (Open)—The Committee will have presentations and discussions with NRC staff regarding the subject topic and proceed to preparation of reports.\n \n \n 10:30 a.m.-1:00 p.m.: Committee Deliberation on Draft Interim Staff Guidance: Content of Risk Assessment and Severe Accident Information in Light-Water Reactor Construction Permit Applications \n (Open)—The Committee"}]}