Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Sensor Concepts and Applications Incorporated
The U.S. Nuclear Regulatory Commission (NRC) staff has received an application from Sensor Concepts and Applications, Incorporated (SCA or the licensee) to renew Special Nuclear Materials (SNM) License No. SNM-2017. The renewed license would authorize the applicant to continue to use SNM in greater than critical mass quantities for research and development of radiation detection instrumentation at its location in Glen Arm, Maryland as well as other locations selected by the United States Department of Defense. This license renewal, if approved, would authorize SCA to continue licensed activities for 10 years beyond its current license.
Service Contract Inventory
The U.S. Nuclear Regulatory Commission (NRC) is publishing this notice to advise the public of the availability of its Fiscal Year (FY) 2020 Service Contract Inventory and FY 2019 Service Contract Inventory Analysis. The NRC's FY 2020 Service Contract Inventory is included as part of a Government-wide service contract inventory. The inventory includes covered service contracts that were awarded in FY 2020. The FY 2019 Inventory Analysis provides information on specific contract actions that were analyzed as part of the NRC's FY 2019 Service Contract Inventory.
Determining Which Structures, Systems, Components and Functions Are Important to Safety
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), dated July 20, 2015, and supplemented on August 31, 2015, submitted by Kurt T. Schaefer (the petitioner). The petition was docketed by the NRC on September 4, 2015, and was assigned Docket No. PRM-50-112. The petitioner requested that the NRC amend its regulations to define the term ``important to safety'' and provide a set of specific criteria for determining which structures, systems, components and functions are ``important to safety.'' The NRC is denying the petition because the issue raised does not involve a significant safety or security concern, and the existing NRC regulations, guidance, and procedures adequately address the issue raised in the PRM. A prescriptive approach that defines criteria for structures, systems, components and functions ``important to safety'' would likely have unintended consequences for the licensing bases of the current operating fleet and could reduce operational flexibility without providing a clear safety benefit. The NRC's current regulations continue to provide reasonable assurance of adequate protection of public health and safety, promote the common defense and security, and protect the environment.
Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations that relate to the decommissioning of production and utilization facilities. The NRC's goals in amending these regulations are to maintain a safe, effective, and efficient decommissioning process; reduce the need for license amendment requests and exemptions from existing regulations; address other decommissioning issues deemed relevant by the NRC; and support the NRC's Principles of Good Regulation, including openness, clarity, and reliability. The NRC will hold a public meeting to promote full understanding of this proposed rule and to facilitate public comments.
Approval of American Society of Mechanical Engineers' Code Cases
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to incorporate by reference revisions of three regulatory guides to approve new, revised, and reaffirmed code cases published by the American Society of Mechanical Engineers. The NRC is also incorporating by reference one NRC NUREG associated with a condition on one of the regulatory guides. This action allows nuclear power plant licensees and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals, and manufacturing licenses to use the code cases listed in these regulatory guides as voluntary alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. These engineering standards are set forth in the American Society of Mechanical Engineers' Boiler and Pressure Vessel Codes and American Society of Mechanical Engineers' Operation and Maintenance Codes, which are currently incorporated by reference into the NRC's regulations. Further, this final rule announces the availability of a related regulatory guide, not incorporated by reference into the NRC's regulations, that lists code cases that the NRC has not approved for use.
Guidance for the Application of Radiological Sabotage Design-Basis Threat in the Design, Development, and Implementation of a Physical Security Program That Meets 10 CFR 73.55 Requirements
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.69, ``Guidance for the Application of Radiological Sabotage Design-Basis Threat in the Design, Development, and Implementation of a Physical Security Program that Meets 10 CFR 73.55 Requirements,'' as a final RG. RG 5.69 provides a method that the NRC staff finds acceptable for an applicant or licensee to use in applying the design-basis threats (DBTs) in the development of a physical security program that meets the requirements of NRC regulations. Through interactions with stakeholders during physical security inspections, including security baseline inspections, force- on-force exercises, and enforcement activities, the NRC identified areas where a need for additional clarity and/or sufficient technical information is warranted. Revision 1 to RG 5.69 addresses these areas. In addition, revisions to this guidance include changes to the DBT adversary characteristics necessary to align with changes to NRC security requirements made since the publication of Revision 0 to RG 5.69 in 2007.
Cyber Security Programs for Nuclear Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-5061, Revision 1, ``Cyber Security Programs for Nuclear Power Reactors.'' DG 5061, Revision 1, incorporates reference to industry whitepapers on identifying safety, important to safety, balance of plant, and emergency preparedness Critical Digital Assets. It also clarifies guidance on defense-in-depth for cyber security and includes updated text based on the latest National Institute of Standards and Technology (NIST) and International Atomic Energy Agency cyber security guidance. Specifically, this proposed revision clarifies issues identified from cyber security inspections, insights gained through the Security Frequently Asked Questions (SFAQ) process, documented cyber security attacks, new technologies, and new regulations. This proposed revision also considers the changes in the most recent revision to the NIST Special Publications (SP) 800-53, upon which Revision 0 of Regulatory Guide (RG) 5.71, ``Cyber Security Programs for Nuclear Facilities'' was based.
Advisory Committee on the Medical Uses of Isotopes: Charter Renewal
The U.S. Nuclear Regulatory Commission (NRC) has determined that renewal of the charter for the Advisory Committee of the Medical Uses of Isotopes (ACMUI) until February 28, 2024, is in the public interest in connection with duties imposed on the Commission by law. This action is being taken in accordance with the Federal Advisory Committee Act, after consultation with the Committee Management Secretariat, General Services Administration.
Advisory Committee on the Medical Uses of Isotopes: Call for Nominations
The U.S. Nuclear Regulatory Commission (NRC) is soliciting nominations for the position of Nuclear Cardiologist on the Advisory Committee on the Medical Uses of Isotopes (ACMUI). Nominees should currently be practicing as a Nuclear Cardiologist.
Acceptability of ASME Code Section III, Division 5, High Temperature Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment supplemental information for draft regulatory guide (DG), DG-1380 (proposed Revision 2 to Regulatory Guide [RG] 1.87), ``Acceptability of ASME Code Section III, Division 5, `High Temperature Reactors.''' This DG endorses, with conditions, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) Section III, ``Rules for Construction of Nuclear Facility Components,'' Division 5, ``High Temperature Reactors,'' and Code Cases N-861 and N- 862. On August 20, 2021, the NRC published DG-1380 requesting public comment. Since then, the NRC staff has reviewed Code Cases N-872 and N- 898 for potential endorsement. This supplemental notice informs the public that the NRC staff is considering endorsement of these two additional Code Cases in the final RG 1.87 (Revision 2) and requests comments on the proposed endorsement and revisions.
Guidance for Implementation of 10 CFR 50.59, “Changes, Tests and Experiments,” at Non-Power Production or Utilization Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 2.8 (Revision 0), Guidance for Implementation of 10 CFR 50.59, ``Changes, Tests and Experiments,'' at Non-Power Production or Utilization Facilities. This RG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements, ``Changes, tests and experiments,'' at a non-power production and utilization facility, as defined in RG 2.8.
Reassessment of NRC's Dollar per Person-Rem Conversion Factor Policy
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 1530, Revision 1, ``Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy.'' This revision to NUREG-1530 updates the dollar per person-rem conversion factor and establishes a method for keeping this factor up-to-date. The NRC uses the dollar per person-rem conversion factor in cost-benefit analyses to determine the monetary valuation of the consequences associated with radiological exposure and establishes this factor by multiplying a value of a statistical life (VSL) coefficient by a cancer mortality risk coefficient.
Holtec Decommissioning International, LLC; Indian Point Nuclear Generating Station; Units 1, 2, and 3; Exemption From Certain Low-Level Waste Shipment Tracking Requirements
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request dated November 19, 2021, from Holtec Decommissioning International, LLC (HDI), for Indian Point Nuclear Generating Station Units 1, 2, and 3 or Indian Point Energy Center (IPEC), from the requirement to investigate, trace, and report to the NRC any low-level radioactive waste shipment or part of a shipment for which acknowledgement of receipt is not received by HDI within 20 days after transfer from IPEC. HDI requested that this time period be extended from 20 to 45 days. HDI requested this change to avoid the administrative burden of investigating, tracing, and reporting on shipments that continue to be under requisite controls.
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2022
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend the licensing, inspection, special project, and annual fees charged to its applicants and licensees. These proposed amendments are necessary to implement the Nuclear Energy Innovation and Modernization Act, which requires the NRC to recover, to the maximum extent practicable, approximately 100 percent of its annual budget less certain amounts excluded from this fee-recovery requirement. In addition, on August 20, 2021, the Chief Financial Officer granted a public interest exemption from the provisions in the fiscal year 2021 final fee rule that required fees for import and export licensing actions. Therefore, this proposed rule would not assess fees for import and export licensing activities in fiscal year 2022.
Idaho State University
The U.S. Nuclear Regulatory Commission (NRC) staff has received, a revised application from Idaho State University (ISU or the licensee) to renew Special Nuclear Materials (SNM) License No. SNM- 1373. The renewed license would authorize the applicant to continue to use SNM in greater than critical mass quantities for education, research, and training programs at its campus in Pocatello, Idaho. This license renewal, if approved, would authorize ISU to continue to possess and use SNM under NRC regulations for 10 years beyond its current license.
Design-Basis Floods for Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1290, ``Design Basis Floods for Nuclear Power Plants.'' This DG is proposed Revision 3 of Regulatory Guide (RG) 1.59. DG-1290 proposes methods that the NRC staff considers acceptable for use in the determination of design-basis floods for nuclear power plants (NPPs).
Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person. This monthly notice includes all amendments issued, or proposed to be issued, from January 7, 2022, to February 3, 2022. The last monthly notice was published on January 25, 2022.
Notice of Intent To Conduct Scoping Process and Prepare Environmental Impact Statement; Kairos Energy, LLC, Kairos Test Reactor
The U.S. Nuclear Regulatory Commission (NRC) will conduct a scoping process to gather information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for a construction permit (CP) requested by Kairos Power, LLC. The NRC is seeking public comment on this action and has scheduled a joint public outreach and public scoping meeting.
Information Collection: Domestic Licensing of Source Material
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Domestic Licensing of Source Material.''
Information Collection: NRC Form 664, “General Licensee Registration”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, NRC Form 664, ``General Licensee Registration.''
NextEra Energy Duane Arnold, LLC; Duane Arnold Energy Center Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption to NextEra Energy Duane Arnold, LLC (NEDA), for the Duane Arnold Energy Center (DAEC) Independent Spent Fuel Storage Installation (ISFSI). The exemption allows a failed fuel can (FFC) and its contents at DAEC to exceed the limits specified in Table 1-1t in Appendix B, Technical Specifications, of NRC Certificate of Compliance (CoC) No. 1004, Renewed Amendment No. 17.
Issuance of Multiple Exemptions in Response to COVID-19 Public Health Emergency
The U.S. Nuclear Regulatory Commission (NRC) issued five exemptions in response to requests from four licensees for relief due to the coronavirus 2019 disease (COVID-19) public health emergency (PHE). The exemptions afford these licensees temporary relief from certain requirements under NRC regulations. The NRC is issuing a single notice to announce the issuance of the exemptions.
Receipts-Based NRC Size Standards
The U.S. Nuclear Regulatory Commission (NRC) is amending its small business size standards, which are used to qualify an NRC licensee as a ``small entity'' under the Regulatory Flexibility Act of 1980, as amended. The purpose of these size standards is for reducing annual NRC license fees for small entities. These standards do not apply to the NRC's contracts for goods and services. The NRC is increasing the upper and lower tiers for its receipts-based small entity size standards for small businesses and small not-for-profit organizations. This change allows NRC standards to remain consistent with the inflation adjustments made by the Small Business Administration size standard for nonmanufacturing concerns. In addition, in accordance with the Small Business Runway Extension Act of 2018, the NRC is changing the calculation of annual average receipts for the receipts-based NRC size standard for small businesses that provide a service or small businesses not engaged in manufacturing from a 3-year averaging period to a 5-year averaging period.
University of Massachusetts Lowell; University of Massachusetts Lowell Research Reactor
The U.S. Nuclear Regulatory Commission (NRC) has issued a renewal of Facility Operating License No. R-125, held by the University of Massachusetts Lowell (UML, the licensee), for the continued operation of the University of Massachusetts Lowell Research Reactor (UMLRR) for an additional 20 years from the date of issuance. The facility is located on the UML campus in Lowell, Massachusetts.
Information Collection: NRC Form 655, “EEO Counselor's Report”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed information collection. The information collection is entitled, NRC Form 655, ``EEO Counselor's Report.''
Information Collection: NRC Form 646, “Formal Discrimination Complaint”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed information collection. The information collection is entitled, NRC Form 646, ``Formal Discrimination Complaint.''
Kairos Power, LLC
The U.S. Nuclear Regulatory Commission (NRC) is providing notice that an uncontested hearing will be held on the Kairos Power, LLC (Kairos) construction permit application that proposes the construction of a test reactor, identified as Hermes, in Oak Ridge, Tennessee, at a time and place to be set in the future by the Commission or designated by the Atomic Safety and Licensing Board. This notice provides the public an opportunity to request a hearing and petition for leave to intervene (i.e., contested hearing) with respect to that application. The NRC staff is currently conducting a detailed technical review of the construction permit application. If the NRC issues a construction permit, the applicant, Kairos, would be authorized to construct its proposed test reactor in accordance with the provisions of the construction permit. Because the application contains sensitive unclassified non-safeguards information (SUNSI), this notice includes an order that imposes procedures to obtain access to SUNSI for contention preparation.
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of one amendment request. The amendment request is for Catawba Nuclear Station, Units 1 and 2 and McGuire Nuclear Station, Units 1 and 2. For the amendment request, the NRC proposes to determine that it involves no significant hazards consideration (NSHC). Because the amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation by persons who file a hearing request or petition for leave to intervene.
Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1385, ``Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident.'' This DG is proposed Revision 5 to Regulatory Guide (RG) 1.82, which describes an approach that may be used to determine quality standards acceptable to the NRC staff, to meet the regulatory requirements for sumps and suppression pools that provide water sources for emergency core cooling, containment heat removal, or containment atmosphere cleanup systems. It also provides guidelines for evaluating the adequacy and the availability of the sump or suppression pool for long-term recirculation cooling following a loss-of-coolant-accident, and the use of containment accident pressure in determining the net positive suction head for the emergency core cooling and containment heat removal pumps. This proposed revision guidance applies to both the pressurized-water reactor (PWR) and boiling-water reactor (BWR) types of light-water reactors.
Access to the Decommissioning Trust Fund for the Disposal of Large Components
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking, dated February 22, 2019, submitted by Gerard P. Van Noordennen on behalf of EnergySolutions, LLC (the petitioner). The petition was docketed by the NRC on March 20, 2019, and was assigned Docket No. PRM-50-119. The petition requested that the NRC revise its regulations to allow access to the decommissioning trust fund for the removal of major radioactive components before the permanent cessation of operations and revise the definition of Decommissioning. The NRC is denying the petition because the petitioner does not raise a significant safety or security concern, and this subject area is adequately covered by existing regulations. The NRC's current regulations and oversight activities continue to provide for the reasonable assurance of adequate protection of public health and safety.
Information Collection: Exemptions and Continued Regulatory Authority in Agreement States and in Offshore Waters Under Section 274
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Exemptions and Continued Regulatory Authority in Agreement States and in Offshore Waters under Section 274.''
Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1393, ``Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations.'' This proposed DG describes methods that are acceptable to the NRC staff to use for assessing, monitoring, and mitigating aging effects on electrical equipment used in nuclear power generating stations.
Vogtle Electric Generating Plant, Unit 4; Hearing Opportunity Associated With Inspections, Tests, Analyses, and Acceptance Criteria
By letter dated January 18, 2022, Southern Nuclear Operating Company (SNC) informed the U.S. Nuclear Regulatory Commission (NRC) that its scheduled date for initial loading of fuel into the reactor for Vogtle Electric Generating Plant (VEGP) Unit 4 is September 2, 2022. The Atomic Energy Act of 1954, as amended (AEA), and NRC regulations provide the public with an opportunity to request a hearing regarding the licensee's conformance with the acceptance criteria in the combined license (COL) for the facility. This document announces the public's opportunity to request a hearing and includes orders imposing procedures for the hearing process.
Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register on January 25, 2022, regarding an incorrect name of the attorney for the licensee referenced in the License Amendment Request table as ``Steven Hamrick, Managing AttorneyNuclear, Florida Power and Light Company, P.O. Box 14000, Juno Beach, FL 33408-0420'' to read ``Rick Giannantonio, General Counsel, Energy Harbor Nuclear Corp., Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308.''
In the Matter of Holtec Decommissioning International, LLC; Oyster Creek Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Holtec Decommissioning International, LLC (HDI) to memorialize the agreement reached during an alternative dispute resolution mediation session held on October 14, 2021. This Order will resolve any issues identified during an NRC inspection and investigation related to a (now-former) training superintendent at Oyster Creek Nuclear Generating Station (Oyster Creek), who was also responsible for performing armorer duties, and who deliberately failed to perform firearms maintenance activities and falsified records related to those activities. The Order includes a number of significant actions HDI has agreed to take that are expected to improve HDI's security performance at Oyster Creek and other sites in its fleet. The Confirmatory Order is effective upon issuance.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4 Inspections, Tests, Analyses, and Acceptance Criteria
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that specified inspections, tests, and analyses have been successfully completed, and that specified acceptance criteria are met for the Vogtle Electric Generating Plant (VEGP), Units 3 and 4.
NextEra Energy Duane Arnold, LLC; Duane Arnold Energy Center Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is publishing this notice regarding the issuance of an Environmental Assessment (EA) and Finding of No Significant Impact (FONSI) for its review and potential approval of an exemption to NextEra Energy Duane Arnold, LLC (NEDA) for the Duane Arnold Energy Center (DAEC) Independent Spent Fuel Storage Installation (ISFSI). The exemption would allow a failed fuel can (FFC) and its contents at DAEC to exceed the limits specified in Table 1-1t in Appendix B, Technical Specifications, of NRC Certificate of Compliance (CoC) No. 1004, Renewed Amendment No. 17.
Information Collection: Operators' Licenses
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Operators' Licenses.''
Information Collection: NRC Form 398, “Personal Qualification Statement-Licensee”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, NRC Form 398, ``Personal Qualification StatementLicensee.''
Information Collection: NRC Form 396, “Certification of Medical Examination by Facility Licensee”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, NRC Form 396, ``Certification of Medical Examination by Facility Licensee.''
In the Matter of Arizona Public Service Company; El Paso Electric Company; Palo Verde Nuclear Generating Station, Units 1, 2, and 3 and Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order approving the application dated March 18, 2021, filed by El Paso Electric Company (EPE). The application sought NRC consent to the indirect transfer of control of EPE's interests in Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74 for Palo Verde Nuclear Generating Station (Palo Verde), Units 1, 2, and 3, respectively, and the general license for the Palo Verde Independent Spent Fuel Storage Installation (together, the facility). No physical changes or operational changes to the facility were proposed in the application.
Unified Agenda of Federal Regulatory and Deregulatory Actions
We are publishing our semiannual regulatory agenda (the Agenda) in accordance with Public Law 96-354, ``The Regulatory Flexibility Act,'' and Executive Order 12866, ``Regulatory Planning and Review.'' The NRC's Agenda is a compilation of all rulemaking activities on which we have recently completed action or have proposed or are considering action. We have completed 7 rulemaking activities since our complete Agenda was issued online at the Office of Management and Budget's website at https://www.reginfo.gov on June 11, 2021. This issuance of our Agenda contains 37 active and 17 long-term rulemaking activities: 3 are Economically Significant; 16 represent Other Significant agency priorities; 38 are Substantive, Nonsignificant rulemaking activities; and 4 are Administrative rulemaking activities. In addition, 4 rulemaking activities impact small entities. We are requesting comment on the rulemaking activities as identified in this Agenda. The NRC's last Agenda was issued for public comment on July 30, 2021.
Sigma-Aldrich Company, Fort Mims Site
The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of the Sigma-Aldrich Company, Fort Mims Site, Materials License No. 24-16273-01, located in Maryland Heights, MO.
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