Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft report entitled, NUREG-1307, Revision 19, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.'' This report, which is revised periodically, explains the formula acceptable to the NRC for determining the minimum decommissioning fund requirements for nuclear power reactor licensees, as required by NRC regulations. Specifically, this report provides the adjustment factor and updates the values for the labor, energy, and waste burial escalation factors of the minimum formula.
Southern Nuclear Operating Company, Inc.,Vogtle Electric Generating Plant, Unit 4, Electrical Inspections, Tests, Analyses, and Acceptance Criteria Optimization
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the Tier 1 information in the plant-specific design control document (DCD) and is issuing License Amendment No. 187 to Combined License (COL) NPF-92. The COL was issued to Southern Nuclear Operating Company, Inc. (SNC); Georgia Power Company; Oglethorpe Power Corporation; MEAG Power SPVM, LLC; MEAG Power SPVJ, LLC; MEAG Power SPVP, LLC; and the City of Dalton, Georgia; for the Vogtle Electric Generating Plant (VEGP) Unit 4, located in Burke County, Georgia. SNC is the entity that is licensed to construct and operate VEGP Unit 4. The granting of the exemption allows the departure from 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.
Abilene Christian University
The U.S. Nuclear Regulatory Commission (NRC) staff accepts and dockets an application for a construction permit from Abilene Christian University (ACU) for a molten salt research reactor to be built in Abilene, Texas.
Information Collection: Specific Domestic Licenses To Manufacture or Transfer Certain Items Containing Byproduct 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, ``Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material.''
Information Collection: Scheduling Information for the Licensing of Accident Tolerant, Higher Burnup, and Increased Enrichment Fuels
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, ``Scheduling Information for the Licensing of Accident Tolerant, Higher Burnup, and Increased Enrichment Fuels.''
In the Matter of Zion Solutions, LLC and Exelon Generation Company, LLC Zion Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order to extend until November 26, 2023, the effectiveness of a November 26, 2019, order, which approved the direct transfer of Facility Operating License Nos. DPR-39 and DPR-48 for Zion Nuclear Power Station (ZNPS), Units 1 and 2, respectively, and the general license for the ZNPS independent spent fuel storage installation from the current holder, ZionSolutions, LLC, to Exelon Generation Company, LLC and amended the facility operating licenses for administrative purposes to reflect the transfer.
Information Collection: NRC Forms 542 and 542A, Uniform Low-Level Radioactive Waste Manifest Index and Regional Compact Tabulation and Continuation Page
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 Forms 542 and 542A, Uniform Low-Level Radioactive Waste Manifest Index and Regional Compact Tabulation and Continuation Page.''
Information Collection: NRC Form 313, Application for Materials License and NRC Forms 313A (RSO), 313A (AMP), 313A (ANP), 313A (AUD), 313A (AUT), and 313A (AUS)
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 313, ``Application for Materials License'' and NRC Forms 313A (RSO), 313A (AMP), 313A (ANP), 313A (AUD), 313A (AUT), and 313A (AUS).''
Information Collection: Regulatory Issue Summary 2009-06, Revision 1, Importance of Giving the NRC Advance Notice of Intent To Pursue License Renewal
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed information collection. The information collection is entitled, ``Regulatory Issue Summary 2009-06, Revision 1, Importance of Giving the NRC Advance Notice of Intent to Pursue License Renewal.''
Information Collection: NRC Form 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports
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 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/ BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports.''
Information Collection: NRC Forms 540 and 540A, Uniform Low-Level Radioactive Waste Manifest (Shipping Paper) and Continuation Page
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 Forms 540 and 540A, Uniform Low-Level Radioactive Waste Manifest (Shipping Paper) and Continuation Page.''
Information Collection: NRC Forms 541 and 541A, Uniform Low-Level Radioactive Waste Manifest Container and Waste Description and Continuation Page
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 Forms 541 and 541A, Uniform Low-Level Radioactive Waste Manifest Container and Waste Description and Continuation Page.''
Licensing Safety Analysis for Loss-of-Coolant Accidents
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Ralph O. Meyer dated August 1, 2022, requesting that the NRC revise its regulations regarding the licensing safety analysis for loss-of-coolant accidents. The petition was docketed by the NRC on October 11, 2022, and has been assigned Docket No. PRM-50-124. The NRC is examining the issues raised in PRM-50-124 to determine whether they should be considered in rulemaking. The NRC is requesting public comment on this petition at this time.
Perma-Fix Northwest Richland, Inc.
On October 17, 2022, the U.S. Nuclear Regulatory Commission (NRC) received an application to amend an export license (XW027/01), from Perma-Fix Northwest Richland, Inc. (PFNW), authorizing the export of low-level radioactive waste to Eckert and Ziegler Nuclitech GmbH located in Germany. The request seeks the NRC's approval to amend an existing license authorizing the export of radioactive waste to Germany. The NRC is providing notice of the opportunity to comment, request a hearing, and petition to intervene on PFNW's application.
Fitness for Duty Drug Testing Requirements
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations regarding fitness for duty (FFD) programs for certain NRC licensees and other entities to align the NRC's drug testing requirements more closely with the updates made to the U.S. Department of Health and Human Services' ``Mandatory Guidelines for Federal Workplace Drug Testing Programs'' in 2008 and as revised in 2017. This final rule also incorporates lessons learned from implementing the NRC's current FFD regulations. These changes enhance the ability of NRC licensees and other entities to identify individuals using illegal drugs, misusing legal drugs, or attempting to subvert the drug testing process. This final rule provides additional protections to individuals subject to drug testing and improves the clarity, organization, and flexibility of the NRC's FFD regulations. This final rule provides a new flexibility for the collection and drug testing of an oral fluid specimen as an alternative to the collection and testing of a urine specimen under direct observation conditions. The NRC also is issuing final implementation guidance for this final rule.
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 Radiation Oncologist Physician (Brachytherapy) on the Advisory Committee on the Medical Uses of Isotopes (ACMUI). Nominees should be currently practicing radiation oncologists.
National Institute of Standards and Technology; National Bureau of Standards Test Reactor
The U.S. Nuclear Regulatory Commission (NRC, the Commission) is considering issuance of an amendment to Renewed Facility Operating License No. TR-5, issued to the U.S. Department of Commerce, National Institute of Standards and Technology (NIST), for operation of the National Bureau of Standards test reactor (NBSR). The proposed amendment would revise the NBSR Safety Analysis Report (SAR) to allow reactor operation with the debris that remains in the reactor primary coolant system from the February 3, 2021, fuel damage event and after the subsequent cleaning operations. The proposed amendment would not authorize the restart of the NBSR.
Performance-Based Containment Leak Test Program
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1391, ``Performance- Based Containment Leak Test Program''. This DG is proposed Revision 1 to regulatory guide (RG) 1.163 of the same name. The proposed revision provides guidance on an acceptable performance-based leak-test program, leakage-rate test methods, procedures, and analyses that may be used to comply with NRC regulations.
Information Collection: Physical Protection of Category 1 and Category 2 Quantities of Radioactive 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, ``Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material.''
GE-Hitachi Nuclear Energy Americas, LLC; Morris Operation Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering a renewal for twenty years of special nuclear materials (SNM) License SNM-2500 for the possession, transfer, and storage of radioactive material at the Morris Operation independent spent fuel storage installation (ISFSI) in Grundy County, Illinois. The license is held by GE-Hitachi Nuclear Energy Americas, LLC, and, if renewed, would expire on May 31, 2042.
Holtec Decommissioning International, LLC, Indian Point Energy Center, Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request submitted by Holtec Decommissioning International, LLC (HDI), on behalf of Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC on March 24, 2022. This exemption would, if granted, permit HDI to load up to three MPC-32Ms, using Amendment No. 15 of the Holtec International Certificate of Compliance (CoC) No. 1014 for the HI-STORM 100 storage system, with either up to 32 fuel assemblies each containing either a Californium-252 (Cf-252) or an Antimony-Beryllium (Sb-Be) neutron source assemblies (NSA) with sufficient cooling time, or a combination of up to five Plutonium- Beryllium (Pu-Be) NSAs and up to all of the remaining basket locations with fuel assemblies each containing either a Cf-252 or an Sb-Be NSA with sufficient cooling time. Further, it would permit HDI to load the fuel assemblies containing either Cf-252 or Sb-Be NSAs in any location in the basket and the fuel assemblies containing Pu-Be NSAs such that one is located in the center of the basket and no more than one NSA is located in each of the four basket quadrants.
Operational Leakage
The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Issue Summary (RIS) 2022-02, ``Operational Leakage.'' This RIS clarifies the NRC staff's position on the NRC requirements for evaluation, control, and treatment of operational leakage in systems required to be operable by plant technical specifications (TS). This RIS is intended for all holders of operating licenses and combined licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel. This RIS emphasizes that operational leakage must be addressed in the same manner as leakage detected during an American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code, Section XI, pressure test. That is, when operational leakage is found in a system that is within the scope of ASME BPV Code, Section XI, and is required to be operable by plant TS, the component must be evaluated by the licensee for operability. Structural integrity determinations must be conducted in accordance with the applicable provisions of the original construction code, the ASME BPVC, Section XI, or otherwise addressed through authorized methods.
Notice of Intent To Conduct Scoping Process and Prepare Supplement To Draft Environmental Impact Statement Virginia Electric and Power Company North Anna Power, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has received Environmental Report, Supplement 1, from Virginia Electric and Power Company (Dominion, the applicant), dated September 28, 2022, related to Dominion's application for subsequent license renewal (SLR) of Renewed Facility Operating License Nos. NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2 (North Anna). The NRC staff will prepare a supplement to its draft supplemental environmental impact statement (DSEIS) for North Anna subsequent license renewal, i.e., NUREG-1437, Supplement 7, Second Renewal, ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 7, Second Renewal, Regarding Subsequent License Renewal for North Anna Power Station Units 1 and 2, Draft Report'' (August 2021). The subsequent renewed operating licenses would authorize the applicant to operate North Anna for an additional 20 years beyond the period specified in each of the current renewed licenses. The current renewed operating licenses for North Anna Units 1 and 2 expire on April 1, 2038, and August 21, 2040, respectively. The NRC will conduct a limited scoping process to gather information necessary to prepare a supplement to its DSEIS to evaluate the environmental impacts of SLR of the operating licenses for North Anna. The NRC is seeking public comment on the proper scope of the site- specific environmental impact statement (EIS) supplement to be prepared for this action.
Miscellaneous Corrections
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous corrections. These changes include correcting typographical errors, removing obsolete language, inserting missing language, and updating the telephone number for the NRC's Region IV office.
Safety Review of Light-Water Power Reactor Construction Permit Applications
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) ``Safety Review of Light-Water Power Reactor Construction Permit Applications'' to clarify existing guidance and to assist the NRC staff in determining whether an application to construct a light-water power reactor (LWR) facility meets the minimum requirements to issue a construction permit (CP). The NRC anticipates the submission of power reactor CP applications in the next few years based on preapplication engagement initiated by several prospective applicants. This guidance is applicable to all applicants for a CP for a light-water power reactor but not to non-LWR applicants or those following the Advanced Reactor Content of Application Project (ARCAP) guidance to the extent the guidance is issued as final and is relevant to the application from a technical and regulatory perspective.
SHINE Medical Technologies, LLC; SHINE Medical Isotope Production Facility
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) regarding the SHINE Medical Technologies, LLC (SHINE, the licensee) request to amend Construction Permit No. CPMIF-001 for the SHINE Medical Isotope Production Facility (SHINE facility) in Rock County, Wisconsin. The amendment request seeks, in part, NRC approval to extend the latest date for completion of the construction of the SHINE facility from December 31, 2022, to December 31, 2025.
Reporting Requirements for Nonemergency Events at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is requesting comment on a regulatory basis to support a rulemaking that would amend its regulations for nonemergency event notifications. The NRC is evaluating the current requirements and guidance for immediate notification of nonemergency events for operating nuclear power reactors and assessing whether the requirements present an unnecessary reporting burden. The regulatory basis contains an analysis of whether reporting requirements can be reduced or eliminated when they do not have a commensurate safety benefit.
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
The U.S. Nuclear Regulatory Commission (NRC) will convene a meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on December 5-6, 2022. A sample of agenda items to be discussed during the public session includes: an overview of Y-90 medical events; overview of the review of Lu-177-PSMA for the treatment of adult patients with prostate cancer; review of pre-rulemaking documents for the rulemaking to establish requirements for Rb-82 generators and emerging medical technologies; and overview of the status of rulemaking for regulations for decommissioning financial assurance for sealed and unsealed radioactive materials. The agenda is subject to change. The current agenda and any updates will be available on the ACMUI's Meetings and Related Documents web page at https://www.nrc.gov/reading- rm/doc-collections/acmui/meetings/2022.html or by emailing Ms. Gupta Sarma at the contact information below. Purpose: Discuss issues related to 10 CFR part 35, Medical Use of Byproduct Material. Date and Time for Open Sessions: December 5, 2022, from 8:30 a.m. to 4:30 p.m. EST, December 6, 2022, from 10:00 a.m. to 12:00 p.m. EST. Date and Time for Closed Session: December 6, 2022, from 1:30 p.m. to 3:30 p.m. EST. This session will be closed to conduct the ACMUI's required annual training. Address for Public Meeting: U.S. Nuclear Regulatory Commission, One White Flint North Building, Commissioner's Hearing Room, 11555 Rockville Pike, Rockville, Maryland 20852.
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 Salem Nuclear Generating Station, Unit 2; Vogtle Electric Generating Plant, Units 1 and 2; and Surry Power Station, 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 by persons who file a hearing request or petition for leave to intervene.
Susquehanna Steam Electric Station, Units 1 and 2 and Associated Independent Spent Fuel Storage Installation; Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments
The U.S. Nuclear Regulatory Commission (NRC, the Commission) received and is considering approval of an application filed by Susquehanna Nuclear, LLC (Susquehanna Nuclear) on September 29, 2022, as supplemented by letter dated October 28, 2022. The application seeks NRC approval of the indirect transfer of Renewed Facility Operating License Nos. NPF-14 and NPF-22 for Susquehanna Steam Electric Station (Susquehanna), Units 1 and 2, respectively, and the general license for the Susquehanna independent spent fuel storage installation (ISFSI) as a result of the restructuring of Talen Energy Corporation, an indirect parent of Susquehanna Nuclear, as a reorganized company yet to be named (referred to as ``Reorganized Talen''). The NRC is also considering amending the renewed facility operating licenses for administrative purposes to reflect the proposed transfer. The application and supplement contain sensitive unclassified non-safeguards information (SUNSI).
Advance Tribal Notification of Certain Radioactive Material Shipments
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process the issue raised in a petition for rulemaking (PRM), PRM-37-2, submitted by Richard Arnold and Ron Johnson, on behalf of the Tribal Radioactive Materials Transportation Committee, dated December 4, 2020. The petitioner requests that the NRC amend its regulations to include advance Tribal notification of certain radioactive material shipments.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 10 to Certificate of Compliance No. 1031. Amendment No. 10 revises the certificate of compliance by adding a new metal storage overpack.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel regulations by revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 10 to Certificate of Compliance No. 1031. Amendment No. 10 revises the certificate of compliance by adding a new metal storage overpack.
Holtec International HI-STORE Consolidated Interim Storage Facility Project
The U.S. Nuclear Regulatory Commission (NRC) is issuing Supplement 1 to a final Environmental Impact Statement (FEIS), NUREG- 2237, ``Environmental Impact Statement for the Holtec International's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico.'' Supplement 1 to NUREG- 2237 updates the responses to public comments by adding responses to certain comments that were inadvertently not included in the FEIS. Supplement 1 does not include any changes to impact analysis or determinations. Holtec International (Holtec) has requested a license to construct and operate a consolidated interim storage facility (CISF) for spent nuclear fuel (SNF) and Greater-Than-Class C (GTCC) waste, along with a small quantity of mixed oxide (MOX) fuel. The proposed CISF would be located in southeast New Mexico at a site located approximately halfway between the cities of Carlsbad and Hobbs. The proposed action is the issuance of an NRC license authorizing a CISF to store up to 8,680 metric tons of uranium (MTUs) [9,568 short tons] of SNF in 500 canisters for a license period of 40 years.
TMI-2 Solutions, LLC; Three Mile Island Station, Unit No. 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing partial exemptions, with a conforming amendment, from several of the record keeping requirements in its regulations in response to a request from TMI-2 Solutions, LLC. Specifically, the licensee requested partial exemptions for certain NRC regulations which require certain records to be retained for the period specified by the appropriate regulation, license condition, or technical specifications (TS), or until termination of the license if not otherwise specified. In response to the licensee's requests, the NRC also issued a conforming amendment that revised the license to reflect the specific exemptions and associated changes in the TS.
Entergy Operations, Inc.; Arkansas Nuclear One; Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 51, issued to Entergy Operations, Inc., for operation of Arkansas Nuclear One, Unit 1 (ANO-1). The proposed amendment would revise the dose equivalent Iodine (I)-131 and the reactor coolant system (RCS) primary activity limits required by ANO-1 Technical Specification (TS) 3.4.12, ``RCS Specific Activity,'' and the primary-to-secondary leak rate limit provided in TS 3.4.13, ``RCS Operational LEAKAGE.'' 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.
Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.250, ``Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants.'' RG 1.250 provides guidance that the staff of the NRC considers acceptable to meet, in part, regulatory requirements for the dedication of commercial-grade digital instrumentation and control items (I&C) for use in nuclear power plant safety applications.
Acceptability of ASME Code, Section XI, Division 2, ‘Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.246, ``Acceptability of ASME Code, Section XI, Division 2, `Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors.'' This RG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section XI, ``Rules for Inservice Inspection of Nuclear Power Plant Components,'' Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis.
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.
Holtec Decommissioning International, LLC; Indian Point Energy Center; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering an exemption request from Holtec Decommissioning International, LLC (HDI) for the Indian Point Energy Center Independent Spent Fuel Storage Installation. This exemption would, if granted, allow HDI to load up to three MPC-32Ms, using Amendment No. 15 for Certificate of Compliance (CoC) No. 1014 for the HI-STORM 100 storage system, with either up to thirty-two fuel assemblies having either Californium (Cf-252) or Antimony-Beryllium (Sb-Be) neutron source assemblies (NSAs) with sufficient cooling time, or a combination of up to five fuel assemblies having primary Plutonium Beryllium (Pu-Be) NSAs and the remaining basket locations with fuel assemblies having either Cf-252 or Sb-Be NSAs with sufficient cooling time. As discussed further, the proposed exemption would permit HDI to load the fuel assemblies having either Cf-252 or Sb-Be NSAs in any location in the basket and the fuel assemblies having Pu-Be NSAs such that one is located in the center of the basket and one is located in each of the four basket quadrants. The NRC prepared an environmental assessment (EA) and concluded that the proposed action would have no significant environmental impact. Accordingly, the NRC staff is issuing a finding of no significant impact (FONSI) associated with the proposed exemption.
Union Electric Company, dba Ameren Missouri, Callaway Plant; Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is granting exemptions from certain portions of the acceptance criteria for emergency core cooling, and the general design criteria for emergency core cooling, containment heat removal, and atmosphere cleanup to allow the use of a risk-informed analysis to evaluate the effects of debris in containment following a loss-of-coolant accident for the Callaway Plant, Unit No. 1 (Callaway) located in Callaway County, Missouri. The exemptions are in response to a request dated March 31, 2021, from Union Electric Company, doing business as Ameren Missouri (the licensee) related to the licensee's proposed approach to resolve a generic safety concern for pressurized water reactors associated with potential clogging of emergency core cooling and containment spray system strainers during certain design basis events.
Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has received an application for the renewal of Facility Operating License Nos. NPF-87 and NPF-89, which authorize Vistra Operations Company LLC (VOC or the applicant) to operate Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The renewed licenses would authorize the applicant to operate CPNPP for an additional 20 years beyond the period specified in each of the current licenses. The current operating licenses for CPNPP expire as follows: Unit 1 on February 8, 2030, and Unit 2 on February 2, 2033.
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