Nuclear Regulatory Commission 2021 – Federal Register Recent Federal Regulation Documents
Results 401 - 431 of 431
Alignment of Licensing Processes and Lessons Learned From New Reactor Licensing
The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on a regulatory basis to support a proposed rule that would amend the NRC's regulations for the licensing of new nuclear power reactors. The NRC's goals in amending these regulations would be to ensure consistency in new reactor licensing reviews, provide for an efficient new reactor licensing process, reduce the need for exemptions from existing regulations and license amendment requests, address other new reactor licensing issues deemed relevant by the NRC, and support the principles of good regulation, specifically openness, clarity, and reliability. The NRC plans to hold a public meeting to promote a full understanding of the rulemaking, discuss the regulatory basis, and facilitate public participation.
In the Matter of Tennessee Valley Authority Bellefonte Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has approved the Tennessee Valley Authority (TVA) requests to extend the latest construction completion dates for Bellefonte Nuclear Plant (BLN), Units 1 and 2, to October 1, 2021. TVA is the current construction permit (CP) holder for BLN, Units 1 and 2. The initial CPs for BLN were issued on December 24, 1974, authorizing TVA to construct BLN, Units 1 and 2, in Jackson County, AL.
Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Independent Spent Fuel Storage Installation; Consideration of Approval of Transfer of Licenses
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an indirect license transfer application filed by Arizona Public Service Company (APS) on December 2, 2020. The application seeks NRC approval of the indirect transfer of possession- only non-operating 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 (ISFSI) from Public Service Company of New Mexico (PNM) to Avangrid, Inc. (Avangrid), whereby PNM and its parent holding company would become indirect wholly owned subsidiaries of Avangrid. PNM currently owns a 10.2 percent tenant-in-common interest and holds possession-only rights in the NRC licenses. The proposed indirect license transfer would result from Avangrid acquiring PNM and its parent holding company as its subsidiaries, thereby owning 100 percent of the shares in PNM.
NextEra Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering an application for the subsequent renewal of Renewed Facility Operating License Nos. DPR-24 and DPR-27, which authorize NextEra Energy Point Beach, LLC (NextEra, the applicant) to operate Point Beach Nuclear Plant, Units 1 and 2 (Point Beach), respectively. The subsequent renewed operating licenses would authorize the applicant to operate Point Beach for an additional 20 years beyond the period specified in each of the current renewed operating licenses. The current renewed operating licenses for Point Beach expire as follows: Unit 1 on October 5, 2030, and Unit 2 on March 8, 2033.
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 2103, ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors.''
Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria
On December 8, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued a draft report for comment, NUREG-1757, Volume 2, Revision 2, ``Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria.'' The public comment period was originally scheduled to close on February 8, 2021. 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. Additionally, the NRC staff would like to announce that it will hold a public meeting on Monday, March 15, 2021, to discuss updates to the guidance document and provide members of the public an opportunity to comment on the draft guidance document. Details regarding the public meeting and agenda will be forthcoming on the NRC's public website https://www.nrc.gov/pmns/mtg.
Information Collection: Collection of Operator Simulator Training Data
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Collection of Operator Simulator Training Data.''
Information Collection: Domestic Licensing 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, ``Domestic Licensing of Special Nuclear Material.''
An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.177, ``An Approach for Plant- Specific, Risk-Informed Decisionmaking: Technical Specifications.'' Revision 2 of RG 1.177 includes guidance to develop risk-informed applications for technical specification (TS) changes that considers engineering issues and applies risk insights. It provides guidance acceptable to the staff for using risk information to evaluate changes to nuclear power plant TS completion times (CTs), surveillance frequencies (SFs) and to assess the impact of such proposed changes on the risk associated with plant operation. In addition, it supplements RG 1.174, Revision 3, ``An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,''.
Issuance of Multiple Exemptions in Response to COVID-19 Public Health Emergency
The U.S. Nuclear Regulatory Commission (NRC) issued 68 exemptions in response to requests from 26 licensees. The exemptions afford these licensees temporary or permanent relief from certain requirements under NRC regulations. The exemptions are in response to the licensees' requests for relief due to the coronavirus disease 2019 (COVID-19) public health emergency (PHE). The NRC is issuing a single notice to announce the issuance of the exemptions.
Tennessee Valley Authority Bellefonte, Units 1 and 2 Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering extending the completion dates for Construction Permit Nos. CPPR-122 and CPPR-123, issued to the Tennessee Valley Authority (TVA) for Bellefonte Nuclear Plant, Units 1 and 2 (BLN), located on the west shore of the Guntersville Reservoir at Tennessee River Mile (RM) 392 in Jackson County, Alabama. The NRC prepared this environmental assessment (EA) documenting the environmental review and finding of no significant impact (FONSI) for this proposed action.
Updated Aging Management Criteria for Reactor Vessel Internal Components for Pressurized-Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) SLR-ISG-2021-01-PWRVI, ``Updated Aging Management Criteria for Reactor Vessel Internal Components for Pressurized-Water Reactors.'' This ISG updates the aging management criteria for pressurized-water reactor (PWR) vessel internals components in the NRC's subsequent license renewal (SLR) guidance documents. Specifically, the ISG revises guidance contained in NUREG- 2191, ``Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report,'' and NUREG-2192, ``Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants.'' This ISG is intended to facilitate preparation of SLR applications by clarifying existing guidance for aging management and adding new guidance, which also will facilitate the NRC staff's review of SLR applications.
Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1303, ``Application and Testing of Safety-Related Diesel Generators in Nuclear Power.'' This draft guide is proposed revision 5 of Regularity Guide (RG) 1.9. DG- 1303 provides updated guidance that the staff of the NRC considers acceptable to demonstrate compliance with the NRC regulations for safety-related alternating current (AC) power supplies intended for use as onsite emergency power sources in nuclear power plants. This revision of RG 1.9 would endorse, with supplements and clarifications, Institute of Electrical and Electronics Engineers (IEEE) Std 387-2017, ``IEEE Standard for Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations'' and IEEE Std 2420-2019, ``IEEE Standard for Combustion Turbine Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations.'' This guidance would help ensure that the standby emergency power supplies are qualified, have sufficient capacity, and have the necessary reliability and availability for design-basis events.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM UMAX Canister Storage System, Certificate of Compliance No. 1040, Amendment No. 4
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of January 25, 2021, for the direct final rule that was published in the Federal Register on November 9, 2020. This direct final rule amended the Holtec International HI-STORM UMAX Canister Storage System listing in the ``List of approved spent fuel storage casks'' to include Amendment No. 4 to Certificate of Compliance No. 1040. Amendment No. 4 revises the certificate of compliance to update the technical specifications for radiation protection regarding the dose rate limit for the vertical ventilated module lid, update the technical specifications for the vent blockage limiting condition for operation, and add a Type 1 version of multi-purpose canister MPC-37.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Unit 3; Unit 3 Auxiliary Building Wall 11 Seismic Gap Requirements
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information in Tier 1 of the plant-specific design control document (DCD) and is issuing License Amendment No. 182 to Combined License (COL) NPF-91. The COL is for construction and operation of the Vogtle Electric Generating Plant (VEGP) Unit 3, located in Burke County, Georgia. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.
Indiana Michigan Power Company; Donald C. Cook Nuclear Plant, Unit No. 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 74, issued to Indiana Michigan Power Company (I&M), for operation of the Donald C. Cook Nuclear Plant, Unit No. 2 (CNP-2). The proposed amendment would revise the CNP-2 technical specifications (TSs) to allow a one-time change to permit the current integrated leak rate test interval of 15 years to be extended by approximately 18 months to no later than the plant startup after the fall 2022 refueling outage.
Fire Protection Program for Nuclear Power Plants During Decommissioning
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.191, ``Fire Protection Program for Nuclear Power Plants During Decommissioning.'' Revision 1 of RG 1.191 addresses new information identified since Revision 0 of this guide was issued. The guidance in Revision 0 of the RG does not include guidance for plants that have transitioned to the National Fire Protection Association (NFPA) Standard 805, ``Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,'' 2001 Edition.
Information Collection: NRC Form 483, “Registration Certificate-In Vitro Testing with Byproduct Material Under General License”
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, NRC Form 483, ``Registration CertificateIn Vitro Testing with Byproduct Material Under General License.''
Holtec Decommissioning International, LLC
The U.S. Nuclear Regulatory Commission (NRC) issued two exemptions in response to requests from Holtec Decommissioning International, LLC. The exemptions afford the licensee temporary relief from a certain requirement under NRC regulations. The exemptions are in response to the licensee's requests for relief due to the coronavirus disease 2019 (COVID-19) public health emergency (PHE). The NRC is issuing a single notice to announce the issuance of the exemptions.
Tennessee Valley Authority, Watts Bar Nuclear Plant, Unit 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. NPF-96, issued to Tennessee Valley Authority (TVA), for operation of the Watts Bar Nuclear Plant (Watts Bar or WBN), Unit 2. The proposed amendment would revise the Watts Bar Updated Final Safety Analysis Report (UFSAR) to apply alternate eddy current probabilities of detection (POD) to indications of axial outer diameter stress corrosion cracking (ODSCC) at tube support plates (TSPs) in the Watts Bar, Unit 2, steam generators for the beginning-of-cycle (BOC) voltage distribution in support of the Watts Bar, Unit 2, operational assessment. The proposed POD values will only be used until the Watts Bar, Unit 2, steam generators are replaced. For this amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because this amendment request contains sensitive unclassified non- safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Information Collection: Public Records
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, ``Public Records.'' NRC updated one form integral to the agency's Freedom of Information Act (FOIA) process, NRC Form 507, ``Freedom of InformationPrivacy Act Record Request Form.''
Information Collection: Voluntary Reporting of Performance Indicators
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 Performance Indicators.''
Information Collection: Voluntary Reporting of Planned New Reactor Applications; Withdrawal
On December 29, 2020, the U.S. Nuclear Regulatory Commission (NRC) inadvertently issued an information collection titled, ``Voluntary Reporting of Planned New Reactor Applications'' in the Federal Register. The information collection is being withdrawn because it duplicates a document previously published in the Federal Register on December 1, 2020.
Calculated Maximum Fuel Element Cladding Temperature
The U.S. Nuclear Regulatory Commission (NRC) is denying two related petitions for rulemaking (PRMs), PRM-50-93 and PRM-50-95, submitted by Mark Edward Leyse. The petitioner requested that the NRC amend its regulations for the domestic licensing of production and utilization facilities. The petitioner asserted that data from multirod (assembly) severe fuel damage experiments indicate that specific aspects of the NRC's regulations on emergency core cooling systems acceptance criteria and evaluation models are not conservative and that additional regulations are necessary. The NRC is denying these petitions because existing NRC regulations provide reasonable assurance of adequate protection of public health and safety. The petitioner did not present sufficient new information or arguments to support the requested changes.
Information Collection: NRC Form 446, “Request for Approval of Official Foreign Travel by Non-Government Personnel”
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a proposed collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, NRC Form 446, ``Request for Approval of Official Foreign Travel by Non-Government Personnel.''
Licensing Support Network Advisory Review Panel
The Licensing Support System Advisory Review Panel was established by the Nuclear Regulatory Commission (NRC) as a Federal Advisory Committee in 1989. Its purpose was to provide advice on the fundamental issues of design and development of an electronic information management system to be used to store and retrieve documents relating to the licensing of a geologic repository for the disposal of high-level radioactive waste, and on the operation and maintenance of the system. This electronic information management system was known as the Licensing Support System.
Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste
The Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1377, ``Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste.'' This DG is proposed revision 3 of Regulatory Guide (RG) 1.21 of the same name. The proposed revision describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for; (1) measuring, evaluating, and reporting plant related radioactivity in effluents and solid radioactive waste shipments from NRC licensed facilities, and (2) assessing and reporting the public dose to demonstrate compliance with NRC regulations.
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