Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Information Collection: Solicitation of Non-Power Reactor Operator Licensing Examination Data
The Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Solicitation of Non-Power Reactor Operator Licensing Examination Data.''
Information Collection: Criteria and Procedures for Emergency Access to Non-Federal and Regional Low-Level Waste Disposal Facilities
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, ``Criteria and Procedures for Emergency Access to Non-Federal and Regional Low-Level Waste Disposal Facilities.''
Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures
The U.S. Nuclear Regulatory Commission (NRC) has issued Revision 1 to NUREG-1556, Volume 20, ``Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures.'' NUREG-1556, Volume 20 has been revised to include information on updated NRC materials policies and procedures, NRC's internal safety culture, security of radioactive materials, protection of sensitive information, and changes in regulatory policies and practices consistent with current regulations. This volume is intended for use by NRC staff and management.
United Nuclear Corporation Church Rock Project
On November 13, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued for public comment a draft Environmental Impact Statement (EIS) for United Nuclear Corporation's (UNC) license amendment request. The UNC is requesting authorization to amend its license (SUA-1475) to excavate approximately 1 million cubic yards (CY) of mine waste from the Northeast Church Rock Mine Site and dispose of it at the existing mill site in McKinley County, New Mexico. The comment period was originally scheduled to close on December 28, 2020. The NRC has decided to extend the public comment period to allow more time for members of the public to develop and submit their comments. The NRC plans to hold a public meeting in the future to promote full understanding of the contemplated action and facilitate public comment.
Order To Transport Logistics International Suspending Exports of Certain Source Material
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order to Transport Logistics International (TLI) suspending its authority to export certain source material to the United Kingdom (U.K.). This suspension is required due to the U.K.'s exit from the European Atomic Energy Community (EURATOM). Exports of EURATOM- obligated and Canadian-obligated source material to the U.K. are currently not authorized.
Order to ConverDyn Suspending Exports of Certain Source Material
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order to ConverDyn suspending its authority to export certain source material to the United Kingdom (U.K.). This suspension is required due to the U.K.'s exit from the European Atomic Energy Community (EURATOM). Exports of EURATOM-obligated and Canadian-obligated source material to the U.K. are currently not authorized.
Sigma-Aldrich Company; Fort Mims Site
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to NRC Materials License No. 24-16273-01, issued to Sigma-Aldrich Company (the licensee), for possession of byproduct material incident to radiological survey, storage of waste awaiting disposal, and decontamination and remediation of the Fort Mims Site. The proposed amendment is to revise the decommissioning plan and terminate the license for the licensee's Fort Mims Site in Maryland Heights, Missouri.
Alternatives to the Use of Credit Ratings
The U.S. Nuclear Regulatory Commission (NRC) is considering an amendment to its regulations that would alter financial assurance mechanisms approved by the NRC for the decommissioning of nuclear power plants and other nuclear facilities. Specifically, this action would amend provisions for parent company and self company guarantees that require bond ratings issued by credit rating agencies. This action would implement the provisions of the Dodd-Frank Wall Street Reform and Consumer Protection Act of 2010, which directed agencies to amend their regulations to remove any reference to or reliance on credit ratings. Applicants and licensees who are required to provide decommissioning financial assurance may be affected. The NRC is soliciting public comment on potential approaches for amending the regulations and invites stakeholders and interested persons to participate. The NRC plans to hold a public meeting during the comment period to facilitate stakeholder participation.
Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-2242, ``Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030.'' This guidance updates previous estimates of replacement energy costs for potential shutdowns of U.S. nuclear electricity-generating units.
Erik Erb-Minimum Day Off Requirement for Security Officers
The U.S. Nuclear Regulatory Commission (NRC) is announcing the withdrawal, without prejudice to a future filing, of a petition for rulemaking (PRM), PRM-26-6, ``Minimum Day Off Requirement for Security Officers,'' submitted to the NRC by Erik Erb and 91 co-signers (the petitioners) on August 17, 2010. The petitioners requested that the NRC amend its regulations to decrease the minimum days off requirement for security officers working 12-hour shifts from an average of 3 days per week to 2.5 or 2 days per week. The petitioner withdrew PRM-26-6 by email dated December 10, 2019.
Information Collection: Material Control and Accounting of Special Nuclear Material
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Material Control and Accounting of Special Nuclear Material.''
Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants
The Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1361, ``Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants.'' This draft guide is proposed revision 2 of regulatory guide (RG) 1.89 of the same name. The proposed revision describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for environmental qualification (EQ) of certain electric equipment important to safety for nuclear power plants. The previous revision of RG 1.89 was issued in June 1984 and endorsed the use of Institute of Electrical and Electronic Engineers (IEEE) Standard (Std.) 323-1974. This proposed revision incorporates additional information regarding the dual logo International Electrotechnical Commission (IEC)/IEEE Std. 60780-323, ``Nuclear FacilitiesElectrical Equipment Important to SafetyQualification,'' Edition 1, 2016-02.
Portland General Electric Company; Trojan Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by Portland General Electric Company (PGE) for amendment of Materials License No. SNM-2509 which authorizes PGE to receive, possess, store, and transfer spent nuclear fuel and associated radioactive materials. The amendment sought to revise the description in the safety analysis report of the licensee's evaluation of explosion accident events.
Transfer of Very Low-Level Waste To Exempt Persons for Disposal
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing a proposed interpretation of its low-level radioactive waste disposal regulations that would permit licensees to dispose of waste by transfer to persons who hold specific exemptions for the purpose of disposal by burial. The proposal is being withdrawn based on the NRC staff's assessment that the proposed changes may not benefit the regulatory framework for the disposal of low-level radioactive waste.
Large Break Loss-of-Coolant Accident Redefinition
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking dated February 6, 2002, submitted by Anthony R. Pietrangelo on behalf of the Nuclear Energy Institute, due to the discontinuation of the associated rulemaking.
Fitness-for-Duty Program
The U.S. Nuclear Regulatory Commission (NRC) is denying two petitions for rulemaking related to the fitness-for-duty program that were docketed as PRM-26-3, ``Professional Reactor Operator Society Fitness-for-Duty Programs,'' and PRM-26-5, ``Nuclear Energy Institute Fitness-for-Duty Programs,'' due to the discontinuation of the associated rulemaking.
Westinghouse Electric Company, LLC; Columbia Fuel Fabrication Facility; and US Ecology, Inc.; Idaho Resource Conservation and Recovery Act Subtitle C Hazardous Disposal Facility Located Near Grand View, Idaho
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption and associated license amendment related to a request from Westinghouse Electric Company, LLC (WEC) from NRC regulations with respect to a request for alternate disposal and exemption for specified low-activity radioactive waste from the Columbia Fuel Fabrication Facility (CFFF) in Hopkins, South Carolina for waste containing byproduct material and special nuclear material (SNM) under License Number SNM- 1107. Additionally, the NRC is taking the related action of approving exemptions to US Ecology, Inc. (USEI) from the applicable licensing requirements to allow USEI to receive and possess the material from CFFF without an NRC license. The USEI disposal facility, located near Grand View, Idaho, is a Subtitle C Resource Conservation and Recovery Act (RCRA) hazardous waste disposal facility permitted by the State of Idaho to receive low-level radioactive waste and is not licensed by the NRC. Approval of the alternate disposal request from WEC, the exemptions and license amendment requested by WEC and associated exemptions for USEI would allow WEC to transfer the specific waste from CFFF for disposal at USEI.
Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping
The U.S. Nuclear Regulatory Commission (NRC) is re-issuing for public comment draft regulatory guide (DG), DG-1288 (Revision 1), ``Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping.'' This proposed guide is Revision 2 of regulatory guide (RG) 1.178, ``An Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping.'' It incorporates information to be consistent with the terminology and defense-in-depth philosophy provided in RG 1.174, ``An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,'' as well as to endorse the American Society of Mechanical Engineers (ASME) Code Case N-716-1, ``Alternative Classification and Examination Requirements, Section XI, Division 1.''
Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-3055, ``Implementation of Aging Management Requirements for Spent Fuel Storage Renewals.'' This DG is a proposed new regulatory guide that would describes an approach that is acceptable to the staff of the NRC to meet the regulatory requirements for spent fuel storage renewals. It addresses requirements for the renewal of specific licenses for independent spent fuel storage installations (ISFSI) and certificates of compliance (CoC) for spent fuel storage cask designs pursuant to NRC requirements.
Updated Record of Decision for Powertech (USA) Inc.; Dewey-Burdock In Situ Uranium Recovery Facility
The U.S. Nuclear Regulatory Commission (NRC) staff has issued an updated Record of Decision (ROD) related to the license for Powertech (USA) Inc. (Powertech), Dewey-Burdock in situ uranium recovery (ISR) facility in Custer and Fall River Counties, South Dakota. Powertech's request for a source and byproduct materials license to construct and operate the Dewey-Burdock ISR facility was contested through the NRC's adjudicatory process. On October 8, 2020, the Commission denied a petition for review of the Atomic Safety and Licensing Board Panel's (ASLBP) Final Initial Decision issued on December 12, 2019, and two interlocutory orders, thus terminating the adjudicatory proceeding. The ROD has been updated to account for the ASLBP's decision and the Commission's ruling.
Information Collection: Reactor Site Criteria
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, ``Reactor Site Criteria.''
Information Collection: Licenses and Radiation Safety Requirements for Irradiators
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, ``Licenses and Radiation Safety Requirements for Irradiators.''
Advanced Manufacturing Technologies Subtask 2A
The U.S. Nuclear Regulatory Commission (NRC) published a draft document entitled ``Implementation of Quality Assurance Criteria and 10 CFR 50.59 for Nuclear Power Plant Components Produced Using Advanced Manufacturing Technologies'' for public comments in the Federal Register on November 30, 2020. The document addresses the application of quality assurance (QA) criteria and NRC's requirements in its regulations regarding, ``Changes, tests and experiments,'' to the implementation of Advanced Manufacturing Technologies (AMT)-fabricated components in U.S. nuclear power plants. This notice withdraws the November 30, 2020, notice in its entirety and reissues the notice to include additional explanatory information, extend the comment period to 60 days, and correct the Agencywide Documents Access and Management System (ADAMS) accession number for the draft document.
Westinghouse Electric Company, LLC; Columbia Fuel Fabrication Facility; and US Ecology, Inc.; Idaho Resource Conservation and Recovery Act Subtitle C Hazardous Disposal Facility Located Near Grand View, Idaho
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) related to a request for alternate disposal, exemptions, and associated license amendment for the disposition of waste containing byproduct material and special nuclear material (SNM) from the Westinghouse Electric Company, LLC's (WEC) Columbia Fuel Fabrication Facility (CFFF) in Hopkins, South Carolina, under License Number SNM- 1107. Additionally, the NRC is considering the related action of approving exemptions to US Ecology, Inc. (USEI) from the NRC licensing requirements to allow USEI to receive and dispose the material from CFFF without an NRC license. The USEI disposal facility, located near Grand View, Idaho, is a Subtitle C Resource Conservation and Recovery Act (RCRA) hazardous waste disposal facility permitted by the State of Idaho to receive low-level radioactive waste and is not licensed. Approval of the alternate disposal request from WEC and the exemptions requested by WEC and USEI would allow WEC to transfer the specific waste from CFFF for disposal at USEI.
Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria
The Nuclear Regulatory Commission (NRC) is issuing a draft report for comment, NUREG-1757, Volume 2, Revision 2, ``Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria.'' NUREG-1757 has been revised to address lessons learned and experience gained from review of license termination plans, decommissioning plans, and final status surveys for licensees undergoing license termination since the last revision to the document in September 2006. This NUREG is intended for use by applicants, licensees, and the NRC staff.
Proposed Evaluation Policy Statement
The U.S. Nuclear Regulatory Commission (NRC) is requesting public comment on this proposed Evaluation Policy Statement that presents the standards that will govern the NRC's planning, conduct, and use of program evaluations. The policy statement is intended to provide agency personnel and stakeholders with a clear understanding of the expectations related to the NRC's evaluation standards that include rigor, relevance and utility, transparency, collaboration, independence and objectivity, and ethics.
In the Matter of Arizona Public Service Company; Palo Verde Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) issued a Confirmatory Order to Arizona Public Service Company (APS) on November 17, 2020. The purpose of the Confirmatory Order was to document commitments made as part of a settlement agreement between the NRC and APS to address the licensee's failure to: Perform a written evaluation for a change to the NAC MAGNASTOR spent fuel dry cask storage system and obtain a license amendment for a change in methodology for performing tip-over calculations, and (2) adequately analyze the consequences of a hypothetical MAGNASTOR CC5 spent fuel cask tip-over accident on the independent spent fuel storage installation pad located at APS' Palo Verde Nuclear Generating Station.
Licensee Actions to Address Nonconservative Technical Specifications
The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Guide (RG) 1.239, ``Licensee Actions to Address Nonconservative Technical Specifications.'' This RG endorses the guidance in NEI 15-03, Revision 3, ``Licensee Actions to Address Nonconservative Technical Specifications,'' as a method acceptable to the NRC staff for licensee actions to address nonconservative technical specifications.
Advisory Committee on Reactor Safeguards Charter Renewal
The Advisory Committee on Reactor Safeguards (ACRS) was established by the Atomic Energy Act (AEA) of 1954, as amended. Its purpose is to provide advice to the Commission with regard to the hazards of proposed or existing reactor facilities, to review each application for a construction permit or operating license for certain facilities specified in the AEA, and such other duties as the Commission may request.
Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued exemptions in response to a request from Exelon Generation Company, LLC (Exelon, the licensee) regarding certain emergency planning (EP) requirements. The exemptions eliminate the requirements to maintain an offsite radiological emergency preparedness plan and reduce the scope of onsite EP activities at the Three Mile Island Nuclear Station, Units 1 and 2 (TMI), based on the reduced risks of accidents that could result in an offsite radiological release at a decommissioning nuclear power reactor.
NRC Enforcement Policy
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a proposed policy statement titled NRC Enforcement Policy (the Policy). The NRC is soliciting comments from interested parties, including public interest groups, States, members of the public, and the regulated industry (i.e., reactor, fuel cycle, and material licensees, vendors, and contractors) to assist the NRC in revising its policy.
Dry Storage and Transportation of High Burnup Spent Nuclear Fuel
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 2224, ``Dry Storage and Transportation of High Burnup Spent Nuclear Fuel.'' The NUREG provides technical background information applicable to high burnup spent nuclear fuel (HBU SNF), provides an engineering assessment of recent NRC-sponsored mechanical testing of HBU SNF, and presents example approaches for licensing and certification of HBU SNF in transportation and dry storage.
Operator Licensing Examination Standards for Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-1021, Revision 12, ``Operator Licensing Examination Standards for Power Reactors.'' NUREG-1021 establishes the policies, procedures, and guidance for the development, administration, and grading of written examinations and operating tests used for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities. It also provides procedures and guidance for maintaining operators' licenses and for the NRC to conduct requalification examinations when necessary. The draft NUREG streamlines the examination standards by organizing them in topic-based sections for ease of use, clarifies existing instructions, and introduces new instructions.
Information Collection: Voluntary Reporting of Planned New Reactor Applications
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, ``Voluntary Reporting of Planned New Reactor Applications.''
Waste Control Specialists LLC
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) in support of the NRC's consideration of a request from Waste Control Specialists LLC (WCS) to continue to store transuranic waste that originated from the Los Alamos National Laboratory (LANL) without an NRC license under the terms of a 2014 order. The 2014 order exempted WCS from the NRC's regulations concerning special nuclear material (SNM). The current action is in response to a request by WCS dated August 24, 2020, to extend the possession time to temporarily store certain waste at specific locations at the WCS Site until December 23, 2022.
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 October 16, 2020, to November 12, 2020. The last notice was published on November 3, 2020.
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 three amendment requests. The amendment requests are for Waterford Steam Electric Station, Unit 3; Hope Creek Generating Station; and Sequoyah Nuclear Plant, Units 1 and 2. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration (NSHC). Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
In the Matter of Entergy Nuclear Operations, Inc.; Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Indian Point 3, LLC; Holtec International and Holtec Decommissioning International, LLC; Indian Point Nuclear Generating Unit Nos 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order approving the transfer of Provisional Operating License No. DPR-5 for Indian Point Nuclear Generating Station, Unit No. 1 (IP1); Renewed Facility Operating License Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3, respectively, (collectively, with IP1, the Indian Point Energy Center (IPEC)); and the general license for the IPEC independent spent fuel storage installation to Holtec International (Holtec) subsidiaries. The Holtec subsidiaries would be known as Holtec Indian Point 2, LLC (Holtec IP2) and Holtec Indian Point 3, LLC (Holtec IP3). The Order also approves the transfer of operating authority from the currently licensed operator, Entergy Nuclear Operations, Inc. (ENOI), to Holtec Decommissioning International, LLC (HDI). The NRC is also issuing conforming amendments for the facility operating licenses for administrative purposes to reflect the transfer of the licenses from ENOI to HDI and the planned name change for Entergy Nuclear Indian Point 2, LLC and Entergy Nuclear Indian Point 3, LLC to Holtec IP2 and Holtec IP3, respectively.
Physical Protection Programs at Nuclear Power Reactors Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.76, ``Physical Protection Programs at Nuclear Power Reactors (SGI),'' as a final RG. The NRC has revised RG 5.76 to provide licensees guidance on the implementation of the ``Reasonable Assurance of Protection Time'' concept. This RG (Revision 1) clarifies issues that have been identified through interactions with stakeholders and inspection activities since the original publication of the guide.
Advanced Manufacturing Technologies Subtask 2A
The U.S. Nuclear Regulatory Commission (NRC) is issuing a document for public comments as required by Subtask 2A of the Advanced Manufacturing Technologies (AMT) Action Plan, Revision 1. The document addresses the application of quality assurance (QA) criteria and NRC's requirements in its regulations regarding, ``Changes, Tests and Experiments,'' to the implementation of AMT-fabricated components in U.S. nuclear power plants.
Environmental Assessments and Findings of No Significant Impacts of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans
The U.S. Nuclear Regulatory Commission (NRC) is publishing this notice regarding the issuance of a Final Environmental Assessment (EA) and a Finding of No Significant Impacts (FONSI) for its review and approval of the initial and updated decommissioning funding plans submitted by independent spent fuel storage installation (ISFSI) licensees for the ISFSIs listed in the ``Discussion'' section of this document.
Holtec Decommissioning International, LLC;
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a February 12, 2020, request from Holtec Decommissioning International, LLC (HDI). The exemption permits HDI to make withdrawals from the Indian Point Nuclear Generating Station, Unit Nos. 1, 2, and 3 (referred to individually as IP1, IP2, and IP3, respectively, and collectively as the Indian Point Energy Center or IPEC) Decommissioning Trust Funds (DTFs) for spent fuel management and site restoration activities for IP1, IP2, and IP3 without prior notification to the NRC. This exemption is effective upon issuance, but only applies to HDI upon the consummation of the transfers of the licenses for IP1, IP2, and IP3 to Holtec International (Holtec) subsidiaries Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC and the transfer of the operating authority under the licenses to HDI.
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