ML22272A038
| ML22272A038 | |
| Person / Time | |
|---|---|
| Issue date: | 09/29/2022 |
| From: | Office of Nuclear Material Safety and Safeguards |
| To: | |
| Beall, Robert | |
| Shared Package | |
| ML22272A034 | List: |
| References | |
| 10 CFR Part 53, NRC-2019-0062, RIN 3150-AK31 | |
| Download: ML22272A038 (182) | |
Text
This draft Federal Register notice contains the latest draft proposed rule language that the NRC staff has publicly released to support interactions with the Advisory Committee on Reactor Safeguards (ACRS). This version is based on reviews by NRC staff and consideration of stakeholder input. The NRC staff expects to adopt further changes in the draft proposed rule language.
This language has not been subject to complete NRC management or legal review, and its contents should not be interpreted as official agency positions. The NRC staff plans to continue working on the draft proposed rule language provided in this document.
Please note that blue text indicates conforming changes to existing rule language in parts other than Part 53.
TABLE OF CONTENTS VIII. Section-by-Section Analysis 10 CFR part 1 - Statement of Organization and General Information Section 1.43 Office of Nuclear Reactor Regulation.
10 CFR Part 2 - Agency Rules of Practice and Procedure Section 2.1 Scope.
Section 2.4 Definitions.
10 CFR Part 2, Subpart A - Procedure for Issuance, Amendment, Transfer, or Renewal of a License, and Standard Design Approval Section 2.100 Scope of subpart.
Section 2.101 Filing of application.
Section 2.104 Notice of hearing.
Section 2.105 Notice of proposed action.
Section 2.106 Notice of issuance.
Section 2.109 Effect of timely renewal application.
Section 2.110 Filing and administrative action on submittals for standard design approval or early review of site suitability issues.
10 CFR Part 2, Subpart B - Procedure for Imposing Requirements by Order, or for Modification, Suspension, or Revocation of a License, or for Imposing Civil Penalties Section 2.202 Orders.
10 CFR Part 2, Subpart C - Rules of General Applicability: Hearing Requests, Petitions to Intervene, Availability of Documents, Selection of Specific Hearing Procedures, Presiding Officer Powers, and General Hearing Management for NRC Adjudicatory Hearings Section 2.309 Hearing requests, petitions to intervene, requirements for standing, and contentions.
Section 2.310 Selection of hearing procedures.
Section 2.329 Prehearing conference.
Section 2.339 Expedited decisionmaking procedure.
2 Section 2.340 Initial decision in certain contested proceedings; immediate effectiveness of initial decisions; issuance of authorizations, permits and licenses.
Section 2.341 Review of decisions and actions of a presiding officer.
10 CFR Part 2, Subpart D - Additional Procedures Applicable to Proceedings for the Issuance of Licenses to Construct and/or Operate Nuclear Power Plants of Identical Design at Multiple Sites Section 2.400 Scope of subpart.
Section 2.401 Notice of hearing on construction permit or combined license applications pursuant to appendix N of 10 CFR parts 50 or 52, or part 53.
Section 2.402 Separate hearings on separate issues; consolidation of proceedings.
Section 2.403 Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR part 50.
Section 2.404 Hearings on applications for operating licenses pursuant to appendix N of 10 CFR part 50.
Section 2.405 Initial decisions in consolidated hearings.
Section 2.406 Finality of decisions on separate issues.
10 CFR Part 2, Subpart E - Additional Procedures Applicable to Proceedings for the Issuance of Licenses to Manufacture Nuclear Power Reactors to be Operated at Sites Not Identified in the License Application and Related Licensing Proceedings Section 2.500 Scope of subpart.
Section 2.501 Notice of hearing on application under subpart F of 10 CFR part 52 for a license to manufacture nuclear power reactors.
10 CFR Part 2, Subpart F - Additional Procedures Applicable to Early Partial Decisions on Site Suitability Issues in Connection with an Application for a Construction Permit or Combined License to Construct Certain Utilization Facilities; and Advance Issuance of Limited Work Authorizations Section 2.643 Acceptance and docketing of application for limited work authorization.
Section 2.645 Notice of hearing.
Section 2.649 Partial decisions on limited work authorization.
10 CFR Part 2, Subpart H - Rulemaking Section 2.800 Scope and applicability.
Section 2.801 Initiation of rulemaking.
Section 2.813 Written communications.
10 CFR Part 2, Subpart K - Hybrid Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors Section 2.1103 Scope of subpart K.
10 CFR Part 2, Subpart L - Simplified Hearing Procedures for NRC Adjudications Section 2.1202 Authority and role of NRC staff.
3 10 CFR Part 2, Subpart M - Procedures for Hearings on License Transfer Applications Section 2.1301 Public notice of receipt of a license transfer application.
10 CFR Part 2, Subpart N - Expedited Proceedings with Oral Hearings Section 2.1403 Authority and role of the NRC staff.
10 CFR Part 2, Subpart O - Legislative Hearings Section 2.1500 Purpose and scope.
Section 2.1502 Commission decision to hold legislative hearing.
10 CFR Part 10 - Criteria and Procedures for Determining Eligibility for Access to Restricted Data or National Security Information or an Employment Clearance 10 CFR Part 10, Subpart A - General Provisions Section 10.1 Purpose.
Section 10.2 Scope.
10 CFR Part 11 - Criteria and Procedures for Determining Eligibility for Access to or Control Over Special Nuclear Material Section 11.7 Definitions.
10 CFR Part 19 - Notices, Instructions, and Reports to Workers: Inspection and Investigations Section 19.2 Scope.
Section 19.3 Definitions.
Section 19.11 Posting of notices to workers.
Section 19.14 Presence of representatives of licenses and regulated entities, and workers during inspections.
Section 19.20 Employee protection.
10 CFR Part 20 - Standards for Protection Against Radiation Section 20.1002 Scope.
Section 20.1003 Definitions.
10 CFR Part 20, Subpart B - Radiation Protection Programs Section 20.1101 Radiation protection programs.
10 CFR Part 20, Subpart E - Radiological Criteria for License Termination Section 20.1401 General provisions and scope.
Section 20.1403 Criteria for license termination under restricted conditions.
Section 20.1404 Alternate criteria for license termination.
Section 20.1406 Minimization of contamination.
10 CFR Part 20, Subpart F - Surveys and Monitoring Section 20.1501 General.
10 CFR Part 20, Subpart J - Precautionary Procedures Section 20.1905 Exemptions to labeling requirements.
10 CFR Part 20, Subpart K - Waste Disposal Section 20.2004 Treatment or disposal by incineration.
10 CFR Part 20, Subpart M - Reports
4 Section 20.2201 Reports of theft or loss of licensed material.
Section 20.2202 Notification of incidents.
Section 20.2203 Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits.
Section 20.2206 Reports of individual monitoring.
10 CFR Part 21 - Reporting of Defects and Noncompliance Section 21.2 Scope.
Section 21.3 Definitions.
Section 21.21 Notification of failure to comply or existence of a defect and its evaluation.
Section 21.51 Maintenance and inspection of records.
Section 21.61 Failure to notify.
10 CFR Part 25 - Access Authorization Section 25.5 Definitions.
Section 25.17 Approval for processing applicants for access authorization.
Section 25.35 Classified visits.
10 CFR 26, Fitness For Duty Programs 10 CFR Part 30 - Rules of General Applicability to Domestic Licensing of Byproduct Material Section 30.4 Definitions.
Section 30.50 Reporting requirements.
10 CFR Part 40 - Deomestic Licensing of Source Material Section 40.60 Reporting requirements.
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities 50.44 Combustible gas control for nuclear power reactors.
50.46 Acceptable criteria for emergency core cooling systems for light-water nuclear power reactors.
Section 50.47 Emergency plans.
Section 50.55a Codes and standards.
Section 50.60 Acceptance criteria for fracture prevention measures for light-water nuclear power reactors for normal operations.
Section 50.61 Fracture toughness requirements for protection against pressurized thermal shock events.
Section 50.62 Requirements for reduction of risk from anticipated transients without scram events for light-water-cooled nuclear power plants.
Section 50.63 Loss of all alternating current power.
Appendix A to 10 CFR part 50 Appendix G to 10 CFR part 50 Appendix H to 10 CFR part 50 Appendix J to 10 CFR part 50 Appendix S to 10 CFR part 50
5 10 CFR Part 51 - Environmental Protection Regulations for Domestic Licensing and Related Regualtory Functions 10 CFR Part 51, Subpart A - National Environmental Policy Act - Regulations Implementing Section 102(2)
Section 51.20 Criteria for and identification of licensing and regulatory actions requiring environmental impact statements.
Section 51.22 Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review.
Section 51.26 Requirement to publish notice of intent and conduct scoping process.
Section 51.30 Environmental assessment.
Section 51.31 Determinations based on environmental assessment.
Section 51.32 Finding of no significant impact.
Section 51.49 Environmental report-limited work authorization.
Section 51.50 Environmental report - construction permit, early site permit, or combined license stage.
Section 51.53 Postconstruction environmental reports.
Section 51.54 Environmental report - manufacturing license.
Section 51.55 Environmental report - standard design certification.
Section 51.58 Environmental report - number of copies; distribution.
Section 51.77 Distribution of draft environmental impact statement.
Section 51.92 Supplement to the final environmental impact statement.
Section 51.95 Postconstruction environmental impact statements.
Section 51.101 Limitations on actions.
Section 51.103 Record of decision - general.
Section 51.105 Public hearings in proceedings for issuance of construction permits or early site permits; limited work authorizations.
Section 51.107 Public hearings in proceedings for issuance of combined licenses; limited work authorizations.
Section 51.108 Public hearings on Commission findings that inspections, tests, analyses, and acceptance criteria of combined licenses are met.
10 CFR Part 53General Overview and Requirements Section 53.000 Purpose.
Section 53.010 Frameworks.
10 CFR part 53, subpart AGeneral Provisions Section 53.015 Scope.
Section 53.020 Definitions.
Section 53.024 Definitions specific to Framework A.
Section 53.028 Definitions specific to Framework B.
Section 53.040 Written communications.
Section 53.050 Deliberate misconduct.
Section 53.060 Employee protection.
6 Section 53.070 Completeness and accuracy of information.
Section 53.080 Specific exemptions.
Section 53.090 Standards for review.
Section 53.100 Jurisdictional limits.
Section 53.110 Attacks and destructive acts.
Section 53.115 Rights related to special nuclear material.
Section 53.117 License suspension and rights of recapture.
Section 53.120 Information collection requirements: OMB approval.
10 CFR Part 53, Subpart BTechnology-Inclusive Safety Requirements Section 53.200 Safety objectives.
Section 53.210 Safety criteria for design basis accidents.
Section 53.220 Safety criteria for licensing basis events other than design basis accidents.
Section 53.230 Safety functions.
Section 53.240 Licensing basis events.
Section 53.250 Defense in depth.
Section 53.260 Normal operations.
Section 53.270 Protection of plant workers.
10 CFR Part 53, Subpart CDesign and Analysis Requirements Section 53.400 Design features for licensing basis events.
Section 53.410 Functional design criteria for design-basis accidents.
Section 53.415 Protection against external hazards.
Section 53.420 Functional design criteria for licensing basis events other than design-basis accidents.
Section 53.425 Design features and functional design criteria for normal operations.
Section 53.430 Design features and functional design criteria for protection of plant workers.
Section 53.440 Design requirements.
Section 53.450 Analysis requirements.
Section 53.460 Safety categorization and special treatment.
Section 53.470 Maintaining analytical safety margins used to justify operational flexibilities.
Section 53.480 Earthquake engineering.
10 CFR Part 53, Subpart DSiting Requirements Section 53.500 General siting.
Section 53.510 External hazards.
Section 53.520 Site characteristics.
Section 53.530 Population-related considerations.
Section 53.540 Siting interfaces.
10 CFR Part 53, Subpart EConstruction and Manufacturing Requirements Section 53.600 Construction and manufacturing - scope and purpose.
7 Section 53.605 Reporting of defects and noncompliance.
Section 53.610 Construction.
Section 53.620 Manufacturing.
10 CFR Part 53, Subpart FRequirements for Operation Section 53.700 Operational objectives.
Section 53.710 Maintaining capabilities, availability, and reliability of structures, systems, and components.
Section 53.715 Maintenance, repair, and inspection programs.
Section 53.720 Response to seismic events.
Section 53.725 General staffing, training, personnel qualifications, and human factors requirements.
Section 53.726 Communications.
Section 53.727 Information collection requirements.
Section 53.728 Completeness and accuracy of information.
Section 53.730 Defining, fulfilling, and maintaining the role of personnel in ensuring safe operations.
Section 53.735 General exemptions.
Section 53.740 Facility licensee requirements - general.
Section 53.745 Operator license requirements.
Section 53.750 Violations.
Section 53.755 Criminal penalties.
Section 53.760 Operator licensing.
Section 53.765 Medical requirements.
Section 53.770 Incapacitation because of disability or illness.
Section 53.775 Applications for operator and senior operator licenses.
Section 53.780 Training, examination, and proficiency programs.
Section 53.785 Conditions of operator and senior operator licenses.
Section 53.790 Issuance, modification, and revocation of operator and senior operator licenses.
Section 53.795 Expiration and renewal of operator and senior operator licenses.
Section 53.800 Facility licensees that comply with §§ 53.800 through 53.820.
Section 53.805 Facility licensee requirements related to generally licensed reactor operators.
Section 53.810 Generally licensed reactor operators.
Section 53.815 Generally licensed reactor operator training, examination, and proficiency programs.
Section 53.820 Expiration.
Section 53.830 Training and qualification of commercial nuclear plant personnel.
Section 53.845 Programs.
Section 53.850 Radiation protection.
Section 53.855 Emergency preparedness.
8 Section 53.860 Security programs.
Section 53.865 Quality assurance.
Section 53.870 Integrity assessment programs.
Section 53.875 Fire protection.
Section 53.880 Inservice inspection/inservice testing.
Section 53.890 Facility safety program.
Section 53.910 Procedures and guidelines.
10 CFR Part 53, Subpart GDecommissioning Requirements Section 53.1000 Scope and purpose.
Section 53.1010 Financial assurance for decommissioning.
Section 53.1020 Cost estimates for decommissioning.
Section 53.1030 Annual adjustments to cost estimates for decommissioning.
Section 53.1040 Methods for providing financial assurance for decommissioning.
Section 53.1045 Limitations on the use of decommissioning trust funds.
Section 53.1050 NRC oversight.
Section 53.1060 Reporting and recordkeeping requirements.
Section 53.1070 Termination of license.
Section 53.1075 Program requirements during decommissioning.
Section 53.1080 Release of part of a commercial nuclear plant or site for unrestricted use.
10 CFR Part 53, Subpart HLicenses, Certifications, and Approvals Section 53.1100 Filling of application for licenses, certifications, or approvals; oath or affirmation.
Section 53.1101 Requirement for license.
Section 53.1103 Combining applications and licenses.
Section 53.1106 Elimination of repetition.
Section 53.1109 Contents of applications; general information.
Section 53.1112 Environmental conditions.
Section 53.1115 Agreement limiting access to classified information.
Section 53.1118 Ineligibility of certain applicants.
Section 53.1120 Exceptions and exemptions from licensing requirements.
Section 53.1121 Public inspection of applications.
Section 53.1124 Relationship between sections.
Section 53.1130 Limited work authorizations.
Section 53.1140 Early site permits.
Section 53.1143 Filing of applications.
Section 53.1144 Contents of applications for early site permits; general information.
Section 53.1146 Contents of applications for early site permits; technical information.
Section 53.1149 Review of applications.
Section 53.1155 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1158 Issuance of early site permit.
9 Section 53.1161 Extent of activities permitted.
Section 53.1164 Duration of permit.
Section 53.1167 Limited work authorization after issuance of early site permit.
Section 53.1170 Transfer of early site permit.
Section 53.1173 Application for renewal.
Section 53.1176 Criteria for renewal.
Section 53.1179 Duration of renewal.
Section 53.1182 Use of site for other purposes.
Section 53.1188 Finality of early site permit determinations.
Section 53.1200 Standard design approvals.
Section 53.1203 Filing of applications.
Section 53.1206 Contents of applications for standard design approvals; general information.
Section 53.1209 Contents of applications for standard design approvals; technical information.
Section 53.1210 Contents of applications for standard design approvals; other application content.
Section 53.1212 Standards for review of applications.
Section 53.1215 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1218 Staff approval of design.
Section 53.1221 Finality of standard design approvals; information requests.
Section 53.1230 Standard design certifications.
Section 53.1233 Filing of applications.
Section 53.1236 Contents of applications for standard design certifications; general information.
Section 53.1239 Contents of applications for standard design certifications; technical information.
Section 53.1241 Contents of applications for standard design certifications; other application content.
Section 53.1242 Review of applications.
Section 53.1245 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1248 Issuance of standard design certification.
Section 53.1251 Duration of certification.
Section 53.1254 Application for renewal.
Section 53.1257 Criteria for renewal.
Section 53.1260 Duration of renewal.
Section 53.1263 Finality of standard design certifications.
Section 53.1270 Manufacturing licenses.
Section 53.1273 Filing of applications.
Section 53.1276 Contents of applications for manufacturing licenses; general information.
10 Section 53.1279 Contents of applications for manufacturing licenses; technical information.
Section 53.1282 Contents of applications for manufacturing licenses; other application content.
Section 53.1285 Review of applications.
Section 53.1286 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1287 Issuance of manufacturing license.
Section 53.1288 Finality of manufacturing licenses.
Section 53.1291 Duration of manufacturing licenses.
Section 53.1293 Transfer of manufacturing licenses.
Section 53.1295 Renewal of manufacturing licenses.
Section 53.1300 Construction permits.
Section 53.1306 Contents of applications for construction permits; general information.
Section 53.1309 Contents of applications for construction permits; technical information.
Section 53.1312 Contents of applications for construction permits; other application content.
Section 53.1315 Review of applications.
Section 53.1318 Finality of referenced NRC approvals, permits, and certifications.
Section 53.1324 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1327 Authorization to conduct limited work authorization activities.
Section 53.1330 Exemptions, departures, and variances.
Section 53.1333 Issuance of construction permits.
Section 53.1336 Finality of construction permits.
Section 53.1342 Duration of construction permit.
Section 53.1345 Transfer of construction permits.
Section 53.1348 Termination of construction permits.
Section 53.1360 Operating licenses.
Section 53.1366 Contents of applications for operating licenses; general information.
Section 53.1369 Contents of applications for operating licenses; technical information.
Section 53.1372 Contents of applications for operating licenses; other application content.
Section 53.1375 Review of applications.
Section 53.1381 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1384 Exemptions, departures, and variances.
Section 53.1387 Issuance of operating licenses.
Section 53.1390 Finality of operating licenses.
Section 53.1396 Duration of operating license.
Section 53.1399 Transfer of an operating license.
Section 53.1402 Application for renewal.
Section 53.1405 Continuation of an operating license.
Section 53.1410 Combined licenses.
11 Section 53.1413 Contents of applications for combined licenses; general information.
Section 53.1416 Contents of applications for combined licenses; technical information.
Section 53.1419 Contents of applications for combined licenses; other application content.
Section 53.1422 Review of applications.
Section 53.1425 Finality of referenced NRC approvals.
Section 53.1431 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.1434 Authorization to conduct limited work authorization activities.
Section 53.1437 Exemptions, departures, and variances.
Section 53.1440 Issuance of combined licenses.
Section 53.1443 Finality of combined licenses.
Section 53.1449 Inspection during construction.
Section 53.1452 Operation under a combined license.
Section 53.1455 Duration of a combined license.
Section 53.1456 Transfer of a combined license.
Section 53.1458 Application for renewal.
Section 53.1461 Continuation of combined license.
Section 53.1470 Standardization of commercial nuclear power plant designs: licenses to construct and operate nuclear power reactors of identical design at multiple sites.
Section 53.1480 Limited combined license supporting testing of manufactured reactor modules.
10 CFR Part 53, Subpart IMaintaining and Revising Licensing Basis Information Section 53.1500 Licensing basis information.
Section 53.1502 Specific terms and conditions of licenses.
Section 53.1505 Changes to licensing basis information requiring NRC approval.
Section 53.1510 Application for amendment of license.
Section 53.1515 Public notices; State consultation.
Section 53.1520 Issuance of amendment.
Section 53.1530 Revising design information within a manufacturing license.
Section 53.1535 Amendments during construction.
Section 53.1540 Updating licensing basis information and determining the need for NRC approval.
Section 53.1545 Updating Final Safety Analysis Reports.
Section 53.1550 Evaluating changes to facility as described in reports.
Section 53.1560 Updating program documents included in licensing basis information.
Section 53.1565 Evaluating changes to programs included in licensing basis information.
Section 53.1570 Transfer of licenses.
Section 53.1575 Termination of license.
Section 53.1580 Information requests.
Section 53.1585 Revocation, suspension, modification of licenses and approvals for cause.
12 Section 53.1590 Backfitting.
Section 53.1595 Renewal.
10 CFR Part 53, Subpart JReporting and Other Administrative Requirements Section 53.1600 General information.
Section 53.1610 Unfettered access for inspections.
Section 53.1620 Maintenance of records, making of reports.
Section 53.1630 Immediate notification requirements for operating commercial nuclear plants.
Section 53.1640 Licensee event report system.
Section 53.1645 Effluent reports.
Section 53.1650 Facility information and verification.
Section 53.1660 Financial requirements.
Section 53.1670 Financial qualifications.
Section 53.1680 Annual financial reports.
Section 53.1690 Licensees change of status; financial qualifications.
Section 53.1700 Creditor regulations.
Section 53.1710 Financial protection.
Section 53.1720 Insurance required to stabilize and decontaminate plant following an accident.
Section 53.1730 Financial protection requirements.
10 CFR Part 53, Subpart KQuality Assurance Criteria Section 53.1800 General provisions.
Section 53.1805 Organization.
Section 53.1810 Quality assurance program.
Section 53.1815 Design control.
Section 53.1820 Procurement document control.
Section 53.1825 Instructions, procedures, and drawings.
Section 53.1830 Document control.
Section 53.1835 Control of purchased material, equipment, and services.
Section 53.1840 Identification and control of materials, parts, and components.
Section 53.1845 Control of special processes.
Section 53.1850 Inspection.
Section 53.1855 Test control.
Section 53.1860 Control of measuring and test equipment.
Section 53.1865 Handling, storage, and shipping.
Section 53.1870 Inspections, test, and operating status.
Section 53.1875 Nonconforming materials, parts, or components.
Section 53.1880 Corrective action.
Section 53.1885 Quality assurance records.
Section 53.1890 Audits.
10 CFR Part 53, Subpart NSiting
13 Section 53.3505 Scope.
Section 53.3510 Definitions.
Section 53.3515 Factors to be considered when evaluating sites.
Section 53.3520 Non-seismic siting criteria.
Section 53.3525 Geologic and seismic siting.
10 CFR Part 53, Subpart OConstruction and Manufacturing Section 53.4100 Construction and manufacturing - scope and purpose.
Section 53.4105 Reporting of defects and noncompliance.
Section 53.4110 Construction.
Section 53.4120 Manufacturing.
10 CFR Part 53, Subpart POperations Section 53.4200 Operational objectives.
Section 53.4210 Maintenance, repair, and inspection programs.
Section 53.4213 Technical specifications.
Section 53.4215 Response to seismic events.
Section 53.4220 General staffing, training, personnel qualifications, and human factors requirements.
Section 53.4300 Programs.
Section 53.4310 Radiation protection.
Section 53.4320 Emergency preparedness.
Section 53.4330 Security programs.
Section 53.4340 Quality assurance.
Section 53.4350 Fire protection.
Section 53.4360 Inservice inspection and inservice testing.
Section 53.4380 Environmental qualification of electric equipment important to safety for nuclear power plants.
Section 53.4390 Procedures and guidelines.
Section 53.4400 Integrity assessment program.
Section 53.4410 Primary containment leakage rate testing program.
Section 53.4420 Mitigation of beyond-design basis events.
10 CFR Part 53, Subpart QDecommissioning Requirements Section 53.4600 Scope and purpose.
Section 53.4610 Financial assurance for decommissioning.
Section 53.4620 Cost estimates for decommissioning.
Section 53.4630 Annual adjustments to cost estimates for decommissioning.
Section 53.4640 Methods for providing financial assurance for decommissioning.
Section 53.4645 Limitations on the use of decommissioning trust funds.
Section 53.4650 NRC oversight.
Section 53.4660 Reporting and recordkeeping requirements.
Section 53.4670 Termination of license.
Section 53.4675 Program requirements during decommissioning.
14 Section 53.4680 Release of part of a commercial nuclear plant or site for unrestricted use.
10 CFR Part 53, Subpart RLicenses, Certifications, and Approvals Section 53.4700 Filling of application for licenses, certifications, or approvals; oath or affirmation.
Section 53.4701 Requirement for license.
Section 53.4703 Combining applications and licenses.
Section 53.4706 Elimination of repetition.
Section 53.4709 Contents of applications; general information.
Section 53.4712 Environmental conditions.
Section 53.4715 Agreement limiting access to classified information.
Section 53.4718 Ineligibility of certain applicants.
Section 53.4720 Exceptions and exemptions from licensing requirements.
Section 53.4721 Public inspection of applications.
Section 53.4724 Relationship between sections.
Section 53.4730 General technical requirements.
Section 53.4731 Risk-informed classification of structures, systems, and components.
Section 53.4733 Seismic design alternatives.
Section 53.4740 Limited work authorizations.
Section 53.4750 Early site permits.
Section 53.4753 Filing of applications.
Section 53.4754 Contents of applications for early site permits; general information.
Section 53.4756 Contents of applications for early site permits; technical information.
Section 53.4759 Review of applications.
Section 53.4765 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
Section 53.4768 Issuance of early site permit.
Section 53.4771 Extent of activities permitted.
Section 53.4774 Duration of permit.
Section 53.4777 Limited work authorization after issuance of early site permit.
Section 53.4780 Transfer of early site permit.
Section 53.4783 Application for renewal.
Section 53.4786 Criteria for renewal.
Section 53.4789 Duration of renewal.
Section 53.4792 Use of site for other purposes.
Section 53.4798 Finality of early site permit determinations.
Section 53.4800 Standard design approvals.
Section 53.4803 Filing of applications.
Section 53.4806 Contents of applications for standard design approvals; general information.
Section 53.4809 Contents of applications for standard design approvals; technical information.
15 Section 53.4812 Review of applications.
Section 53.4815 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.4818 Staff approval of design.
Section 53.4821 Finality of standard design approvals; information requests.
Section 53.4830 Standard design certifications.
Section 53.4833 Filing of applications.
Section 53.4836 Contents of applications for standard design certifications; general information.
Section 53.4839 Contents of applications for standard design certifications; technical information.
Section 53.4841 Contents of applications for standard design certifications; other application content.
Section 53.4842 Review of applications.
Section 53.4845 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.4848 Issuance of standard design certification.
Section 53.4851 Duration of certification.
Section 53.4854 Application for renewal.
Section 53.4857 Criteria for renewal.
Section 53.4860 Duration of renewal.
Section 53.4863 Finality of standard design certifications.
Section 53.4870 Manufacturing licenses.
Section 53.4873 Filing of applications.
Section 53.4876 Contents of applications for manufacturing licenses; general information.
Section 53.4879 Contents of applications for manufacturing licenses; technical information.
Section 53.4882 Contents of applications for manufacturing licenses; other application content.
Section 53.4885 Review of applications.
Section 53.4886 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.4887 Issuance of manufacturing license.
Section 53.4888 Finality of manufacturing licenses.
Section 53.4891 Duration of manufacturing licenses.
Section 53.4893 Transfer of manufacturing licenses.
Section 53.4895 Renewal of manufacturing licenses.
Section 53.4900 Construction permits.
Section 53.4906 Contents of applications for construction permits; general information.
Section 53.4909 Contents of applications for construction permits; technical information.
Section 53.4912 Contents of applications for construction permits; other application content.
Section 53.4915 Review of applications.
16 Section 53.4918 Finality of referenced NRC approvals, permits, and certifications.
Section 53.4924 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.4927 Authorization to conduct limited work authorization activities.
Section 53.4930 Exemptions, departures, and variances.
Section 53.4933 Issuance of construction permits.
Section 53.4936 Finality of construction permits.
Section 53.4942 Duration of construction permit.
Section 53.4945 Transfer of construction permits.
Section 53.4948 Termination of construction permits.
Section 53.4960 Operating licenses.
Section 53.4966 Contents of applications for operating licenses; general information.
Section 53.4969 Contents of applications for operating licenses; technical information.
Section 53.4972 Contents of applications for operating licenses; other application content.
Section 53.4975 Review of applications.
Section 53.4981 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.4984 Exemptions, departures, and variances.
Section 53.4987 Issuance of operating licenses.
Section 53.4990 Finality of operating licenses.
Section 53.4996 Duration of operating license.
Section 53.4999 Transfer of an operating license.
Section 53.5002 Application for renewal.
Section 53.5005 Continuation of an operating license.
Section 53.5010 Combined licenses.
Section 53.5013 Contents of applications for combined licenses; general information.
Section 53.5016 Contents of applications for combined licenses; technical information.
Section 53.5019 Contents of applications for combined licenses; other application content.
Section 53.5022 Review of applications.
Section 53.5025 Finality of referenced NRC approvals.
Section 53.5031 Referral to the Advisory Committee on Reactor Safeguards.
Section 53.5034 Authorization to conduct limited work authorization activities.
Section 53.5037 Exemptions, departures, and variances.
Section 53.5040 Issuance of combined licenses.
Section 53.5043 Finality of combined licenses.
Section 53.5049 Inspection during construction.
Section 53.5052 Operation under a combined license.
Section 53.5055 Duration of a combined license.
Section 53.5056 Transfer of a combined license.
Section 53.5058 Application for renewal.
Section 53.5061 Continuation of combined license.
17 Section 53.5070 Standardization of commercial nuclear power plant designs: licenses to construct and operate nuclear power reactors of identical design at multiple sites.
10 CFR Part 53, Subpart SMaintaining and Revising Licensing Basis Information Section 53.6000 Licensing basis information.
Section 53.6002 Specific terms and conditions of licenses.
Section 53.6005 Changes to licensing basis information requiring NRC approval.
Section 53.6010 Application for amendment of license.
Section 53.6015 Public notices; State consultation.
Section 53.6020 Issuance of amendment.
Section 53.6025 Revising information from a certified design.
Section 53.6030 Revising design information within a manufacturing license.
Section 53.6035 Amendments during construction.
Section 53.6040 Updating licensing basis information and determining the need for NRC approval.
Section 53.6045 Updating reports.
Section 53.6050 Evaluating changes to facility as described in reports.
Section 53.6052 Maintenance of risk evaluations.
Section 53.6054 Control of aircraft impact assessments.
Section 53.6060 Updating program documents included in licensing basis information.
Section 53.6065 Evaluating changes to programs included in licensing basis information.
Section 53.6070 Transfer of licenses.
Section 53.6075 Termination of license.
Section 53.6080 Information requests.
Section 53.6085 Revocation, suspension, modification of licenses and approvals for cause.
Section 53.6090 Backfitting.
Section 53.6095 Renewal.
10 CFR Part 53, Subpart TReporting and Other Administrative Requirements Section 53.6300 General Information.
Section 53.6310 Unfettered access for inspections.
Section 53.6320 Maintenance of records, making of reports.
Section 53.6330 Immediate notification requirements for operating commercial nuclear plants.
Section 53.6340 Licensee event report system.
Section 53.6345 Effluent reports.
Section 53.6350 Facility information and verification.
Section 53.6360 Financial requirements.
Section 53.6370 Financial qualifications.
Section 53.6380 Annual financial reports.
Section 53.6390 Licensees change of status; financial qualifications.
Section 53.6400 Creditor regulations.
18 Section 53.6410 Financial protection.
Section 53.6420 Insurance required to stabilize and decontaminate plant following an accident.
Section 53.6430 Financial protection requirements.
10 CFR Part 53, Subpart UQuality Assurance Criteria Section 53.6600 General provisions.
Section 53.6605 Organization.
Section 53.6610 Quality assurance program.
Section 53.6615 Design control.
Section 53.6620 Procurement document control.
Section 53.6625 Instructions, procedures, and drawings.
Section 53.6630 Document control.
Section 53.6635 Control of purchased material, equipment, and services.
Section 53.6640 Identification and control of materials, parts, and components.
Section 53.6645 Control of special processes.
Section 53.6650 Inspection.
Section 53.6655 Test control.
Section 53.6660 Control of measuring and test equipment.
Section 53.6665 Handling, storage, and shipping.
Section 53.6670 Inspections, test, and operating status.
Section 53.6675 Nonconforming materials, parts, or components.
Section 53.6680 Corrective action.
Section 53.6685 Quality assurance records.
Section 53.6690 Audits.
10 CFR Part 70 - Domestic Licensing of Special Nuclear Material 10 CFR Part 70, Subpart C - General Licenses Section 70.20a General license to possess special nuclear material for transport.
10 CFR Part 70, Subpart D - License Applications Section 70.22 Contents of applications.
10 CFR Part 70, Subpart E - Licenses Section 70.32 Conditions of licenses.
10 CFR Part 70, Subpart G - Special Nuclear Material Control Records, Reports, and Inspections Section 70.50 Reporting requirements.
10 CFR Part 72 - Licesning Requirements for the Independent Storage of Spent Nuclear Fuel, High-level Radioactive Waste, and Reactor-Related Greater Than Class C Waste 10 CFR Part 72, Subpart A - General Provisions Section 72.3 Definitions.
10 CFR Part 72, Subpart B - License Application, Form, and Contents Section 72.30 Financial assurance and recordkeeping for decommissioning.
19 Section 72.32 Emergency plan.
10 CFR Part 72, Subpart C - Issuance and Conditions Of License Section 72.40 Issuance of license.
10 CFR Part 72, Subpart D - Records, Reports, Inspections, and Enforcement Section 72.75 Reporting requirements for specific events and conditions.
Section 72.184 Safeguards contingency plan.
10 CFR Part 72, Subpart K - General License for Storage of Spent Fuel at Power Reactor Sites Section 72.210 General license issued.
Section 72.212 Conditions of general license issued under § 72.210.
Section 72.218 Termination of licenses.
10 CFR Part 73 - Physical Protection of Plants and Materials 10 CFR Part 74 - Material Control and Accounting of Special Nuclear Material 10 CFR Part 74, Subpart C - Special Nuclear Material of Low Strategic Significance Section 74.31 Nuclear material control and accounting for special nuclear material of low strategic significance.
10 CFR Part 74, Subpart D - Special Nuclear Material of Moderate Strategic Significance Section 74.41 Nuclear material control and accounting for special nuclear material of moderate strategic significance.
10 CFR Part 74, Subpart E - Formula Quantities of Strategic Special Nuclear Material Section 74.51 Nuclear material control and accounting for strategic special nuclear material.
10 CFR Part 75 - Safeguards on Nuclear Material - Implementation of Safeguards Agreements Between the United States and the International Atomic Energy Agency Section 75.4 Definitions.
Part 95 - Facility Security Clearance and Safeguarding of National Security Information and Restricted Data Section 95.5 Definitions.
Section 95.39 External transmission of documents and material.
Part 140 - Financial Protection Requirements and Indemnitiy Agreements Part 140 Subpart A, General Provisions Section 140.2 Scope.
Part 140 Subpart B, Provisions Applicable Only to Applicants and Licenses Other Than Federal Agencies and Nonprofit Educational Institutions Section 140.10 Scope.
Section 140.11 Amounts of financial protection for certain reactors.
Section 140.12 Amount of financial protection required for other reactors.
Section 140.13 Amount of financial protection required of certain holders of construction permits and combined licenses under 10 CFR part 52.
20 Section 140.20 Indemnity agreements and liens.
Part 150 - Persons Not Exempt Section 150.15 Persons not exempt.
Part 170 - Fees for Facilities, Materials, Import and Export Licenses, and Other Regualtory Services Under the Atomic Energy Act of 1954, As Amended Section 170.3 Definitions.
Section 170.12 Payment of fees.
Section 170.21 Schedule of fees for production and utilization facilities, review of standard referenced design approvals, special projects, inspections, and import and export licenses.
Section 170.41 Failure by applicant or licensee to pay prescribed fees.
10 CFR part 171 - Annual Fees for Reactor Licenses and Fuel Cycle Licenses and Materials Licenses, Including Holders of Certificates of Compliance, Registrations, and Quality Assurance Program Approvals and Government Agencies Licensed by the NRC Section 171.3 Scope.
Section 171.5 Definitions.
Section 171.15 Annual fees: Non-power production or utilization licenses; reactor licenses and independent spent fuel storage licenses.
Section 171.17 Proration.
IX. Regulatory Flexibility Certification X. Regulatory Analysis XI. Backfitting and Issue Finality XII. Cumulative Effects of Regulation XIII. Plain Writing XIV. Environmental Assessment and Proposed Finding of No Significant Environmental Impact XV. Paperwork Reduction Act XVI. Criminal Penalties XVII. Voluntary Consensus Standards XVIII. Availability of Guidance XIX. Public Meeting XX. Availability of Documents VIII. Section-by-Section Analysis The following paragraphs describe the specific changes proposed by this rulemaking.
21 10 CFR part 1 - Statement of Organization and General Information Section 1.43 Office of Nuclear Reactor Regulation.
This proposed rule would update § 1.43(a)(2) to extend the authority of the Office of Nuclear Reactor Regulation to regulate source, byproduct, and special nuclear material at facilities licensed under part 53.
10 CFR part 2 - Agency Rules of Practice and Procedure Section 2.1 Scope.
This proposed rule would update § 2.1(e) to apply to standard design approvals under part 53 of this chapter.
Section 2.4 Definitions.
This proposed rule would revise § 2.4 to update the definition of contested proceeding to include NRC enforcement actions against applicants for a standard design certification under part 53. It would also update the definition of facility to encompass production facilities and utilization facilities as defined in § 53.02.
10 CFR part 2, subpart A - Procedure for Issuance, Amendment, Transfer, or Renewal of a License, and Standard Design Approval Section 2.100 Scope of subpart.
This proposed rule would revise § 2.100 to extend the scope of subpart A of part 2 to licenses and standard design approvals issued under §§ 53.1100 through 53.14, or
§§ 53.4700 through 53.5080 of this chapter.
22 Section 2.101 Filing of application.
This proposed rule would revise § 2.101 to be applicable to part 53 applicants in addition to part 50 and 52 applications by adding references to part 53 in paragraphs (a)(3)(i), (a)(5), (a)(9)(i), (a-1), and (c)(1).
Section 2.104 Notice of hearing.
This proposed rule would extend the hearing notice requirement in § 2.104 to applications concerning facilities covered under part 53. Footnote 1 to § 2.104 would be revised in a corresponding manner.
Section 2.105 Notice of proposed action.
This proposed rule would extend the requirement in § 2.104 to publish a notice of intended operation or a notice of proposed action, as applicable, to part 53 applicants in addition to part 50 and 52 applicants by adding corresponding references to part 53 on paragraphs (a)(4), (a)(10), (a)(12), (a)(13), and (b)(3).
Section 2.106 Notice of issuance.
This proposed rule would extend the issuance notice requirement in § 2.106 to applications concerning facilities covered under part 53.
Section 2.109 Effect of timely renewal application.
This proposed rule would update § 2.109 to add references to part 53 in paragraphs (b), (c), and (d) regarding the timing of license renewal applications.
23 Section 2.110 Filing and administrative action on submittals for standard design approval or early review of site suitability issues.
This proposed rule would revise § 2.110 to include references to part 53 in paragraphs (a)(1) and (b).
10 CFR part 2, subpart B - Procedure for Imposing Requirements by Order, or for Modification, Suspension, or Revocation of a License, or for Imposing Civil Penalties Section 2.202 Orders.
This proposed rule would update § 2.202 to add references to part 53 in paragraph (e) regarding the requirements to be followed for orders involving the modification of a license, COL, ESP, standard design certification rule, standard design approval, or manufacturing license.
10 CFR part 2, subpart C - Rules of General Applicability: Hearing Requests, Petitions to Intervene, Availability of Documents, Selection of Specific Hearing Procedures, Presiding Officer Powers, and General Hearing Management for NRC Adjudicatory Hearings Section 2.309 Hearing requests, petitions to intervene, requirements for standing, and contentions.
This proposed rule would update § 2.309 to include references to part 53 in paragraphs (a), (f)(1)(i), (f)(1)(vi), and (f)(1)(vii), (g), (h)(2), (i)(2), (j)(1), and (j)(2) regarding a request for hearing under §§ 53.1452 or 53.5052.
24 Section 2.310 Selection of hearing procedures.
This proposed rule would amend § 2.310 by revising paragraph (a), the introductory text for paragraph (h) and paragraphs (i) and (j) to incorporate references to part 53 regarding hearing procedures.
Section 2.329 Prehearing conference.
This proposed rule would revise § 2.329, paragraph (a) to extend the timing requirements for prehearing conferences involving CPs and licenses under part 53.
Section 2.339 Expedited decisionmaking procedure.
This proposed rule would revise § 2.339, paragraph (d) to include references to part 53 regarding expedited decisionmaking procedures.
Section 2.340 Initial decision in certain contested proceedings; immediate effectiveness of initial decisions; issuance of authorizations, permits and licenses.
This proposed rule would amend § 2.340 regarding initial decisions of a presiding officer in certain contested proceedings, the effective date of those decisions, and the issuance of authorizations, permits, and licenses, by incorporating references to part 53 in paragraphs (b), (c), (d), (f), (i), and (j).
Section 2.341 Review of decisions and actions of a presiding officer.
This proposed rule would amend § 2.341, paragraph (a)(1) with an updated reference to part 53 regarding the allowance of a period of interim operation.
25 10 CFR part 2, subpart D - Additional Procedures Applicable to Proceedings for the Issuance of Licenses to Construct and/or Operate Nuclear Power Plants of Identical Design at Multiple Sites Section 2.400 Scope of subpart.
This proposed rule would revise § 2.400 to extend the scope of subpart D to part 53 applicants for licenses to construct or operate nuclear power reactors of identical design at multiple sites.
Section 2.401 Notice of hearing on construction permit or combined license applications pursuant to appendix N of 10 CFR parts 50 or 52, or part 53.
This proposed rule would revise § 2.401 extend the hearing notice requirement in
§ 2.401 to applications concerning facilities covered under part 53.
Section 2.402 Separate hearings on separate issues; consolidation of proceedings.
This proposed rule would revise § 2.402 to apply provisions regarding separate hearings and the consolidation of proceedings to part 53 applicants.
Section 2.403 Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR part 50.
This proposed rule would revise § 2.403 to require the Commission to publish a notice of proposed action in the Federal Register after applications under part 53 are docketed.
26 Section 2.404 Hearings on applications for operating licenses pursuant to appendix N of 10 CFR part 50.
This proposed rule would amend § 2.404 to apply to applications for an operating license under part 53.
Section 2.405 Initial decisions in consolidated hearings.
This proposed rule would revise the fourth sentence of § 2.405 to be applicable to CPs, full-power operating licenses, and COLs under part 53.
Section 2.406 Finality of decisions on separate issues.
This proposed rule would update § 2.406 to be applicable to proceedings conducted pursuant to part 53.
10 CFR part 2, subpart E - Additional Procedures Applicable to Proceedings for the Issuance of Licenses to Manufacture Nuclear Power Reactors to be Operated at Sites Not Identified in the License Application and Related Licensing Proceedings Section 2.500 Scope of subpart.
This proposed rule would revise § 2.500 to extend the provisions of subpart E to applications for a license to manufacture nuclear power reactors under part 53.
Section 2.501 Notice of hearing on application under subpart F of 10 CFR part 52 for a license to manufacture nuclear power reactors.
This proposed rule would amend § 2.501 by extending its provisions to applications for a license to manufacture nuclear power reactors under part 53.
27 10 CFR part 2, subpart F - Additional Procedures Applicable to Early Partial Decisions on Site Suitability Issues in Connection with an Application for a Construction Permit or Combined License to Construct Certain Utilization Facilities; and Advance Issuance of Limited Work Authorizations Section 2.643 Acceptance and docketing of application for limited work authorization.
The proposed rule would revise § 2.643, paragraph (b) regarding the acceptance and docketing of an application for a CP for a utilization facility of the type specified in part 53.
Section 2.645 Notice of hearing.
The proposed rule would amend § 2.645, paragraph (a) to incorporate a reference to part 53.
Section 2.649 Partial decisions on limited work authorization.
The proposed rule would revise the third sentence of § 2.649 to extend its provisions to limited work authorizations issued under part 53.
10 CFR part 2, subpart H - Rulemaking Section 2.800 Scope and applicability.
This proposed rule would update § 2.800 by revising paragraph (c) and (d) to incorporate references to part 53 regarding the scope and applicability of the rulemaking procedures contained in this subpart.
28 Section 2.801 Initiation of rulemaking.
This proposed rule would update § 2.801 to include a reference to part 53.
Section 2.813 Written communications.
This proposed rule would update § 2.813, paragraph (a) to apply general requirements for correspondence with the Commission to communications concerning part 53, in addition to parts 50, 52, and 100.
10 CFR part 2, subpart K - Hybrid Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors Section 2.1103 Scope of subpart K.
The proposed rule would revise the first sentence of § 2.1103 to extend the provisions of subpart K to licenses under part 53 to expand the spent fuel capacity at the site of a civilian nuclear power plant.
10 CFR part 2, subpart L - Simplified Hearing Procedures for NRC Adjudications Section 2.1202 Authority and role of NRC staff.
This proposed rule would revise § 2.1202 by updating paragraphs (a)(1), (a)(2),
(a)(3), and (a)(6) to include references to part 53.
10 CFR part 2, subpart M - Procedures for Hearings on License Transfer Applications Section 2.1301 Public notice of receipt of a license transfer application.
This proposed rule would revise § 2.1301, paragraph (b) to include a corresponding reference to license transfers under part 53 in addition to parts 50 and 52.
29 10 CFR part 2, subpart N - Expedited Proceedings with Oral Hearings Section 2.1403 Authority and role of the NRC staff.
This proposed role would update § 2.1403, paragraph (a)(3) to specify that significant hazards consideration has the same meaning as defined in part 53.
10 CFR part 2, subpart O - Legislative Hearings Section 2.1500 Purpose and scope.
This proposed rule would update § 2.1500, paragraph (a) to extend the scope of subpart O to design certification rulemaking hearings under part 53.
Section 2.1502 Commission decision to hold legislative hearing.
This proposed rule would revise § 2.1502, paragraphs (a) and (b)(1) to incorporate references to part 53 regarding the Commissions decision to hold a design certification rulemaking.
10 CFR part 10 - Criteria and Procedures for Determining Eligibility for Access to Restricted Data or National Security Information or an Employment Clearance 10 CFR Part 10, subpart A - General Provisions Section 10.1 Purpose.
This proposed rule would update § 10.1, paragraph (a)(3) to include a reference to part 53.
30 Section 10.2 Scope.
This proposed rule would update § 10.2, paragraph (b) to extend the scope of subpart A to applicants and holders of licenses, certificates, and standard design approvals under part 53 in addition to part 52.
10 CFR part 11 - Criteria and Procedures for Determining Eligibility for Access to or Control Over Special Nuclear Material Section 11.7 Definitions.
This proposed rule would update § 11.7 such that terms defined in part 53 of this chapter have the same meaning when used in part 11.
10 CFR part 19 - Notices, Instructions, and Reports to Workers: Inspection and Investigations Section 19.2 Scope.
This proposed rule would update § 19.2, paragraphs (a)(1)-(4) to include references to part 53.
Section 19.3 Definitions.
This proposed rule would revise § 19.3 to update the definitions of license and regulated entities to incorporate references to part 53.
31 Section 19.11 Posting of notices to workers.
This proposed rule would revise § 19.11, paragraphs (a), (b), and (e)(1) to be applicable to applicants and holders of licenses, permits, standard design approvals, and standard design certifications under part 53 in addition to part 52.
Section 19.14 Presence of representatives of licenses and regulated entities, and workers during inspections.
This proposed rule would revise § 19.14, paragraph (a) to apply to applicants and holders of a license, standard design approval, ESP, or standard design certification under part 53 in addition to part 52.
Section 19.20 Employee protection.
This proposed rule would update § 19.20 to include a reference to protected activities under part 53.
10 CFR part 20 - Standards for Protection Against Radiation Section 20.1002 Scope.
This proposed rule would revise the first sentence of § 20.1002 to extend the scope of part 20 to apply to persons licensed by the Commission to receive, use, transfer, or dispose of byproduct, source, or special nuclear material or to operate a production or utilization facility under part 53.
32 Section 20.1003 Definitions.
This proposed rule would revise § 20.1003 to update the definition of license to include those issued under part 53.
10 CFR part 20, subpart B - Radiation Protection Programs Section 20.1101 Radiation protection programs.
This proposed rule would revise § 20.1101 to exclude licensees subject to
§§ 53.260(b) or 53.4730(a)(3) from the requirements of paragraph (d).
10 CFR part 20, subpart E - Radiological Criteria for License Termination Section 20.1401 General provisions and scope.
This proposed rule would update § 20.1401 to extend the scope of subpart E to apply to the decommissioning of facilities licensed under part 53 and the release of part of a facility or site for unrestricted use in accordance with §§ 53.1000 through 53.1080, or §§ 53.4600 through 53.4680.
Section 20.1403 Criteria for license termination under restricted conditions.
The proposed rule would revise § 20.1403, paragraph (d) to include decommissioning plans under part 53.
Section 20.1404 Alternate criteria for license termination.
The proposed rule would update § 20.1404, paragraph (a)(4) to include a reference to part 53 regarding alternate criteria for license termination.
33 Section 20.1406 Minimization of contamination.
This proposed rule would revise § 20.1406, paragraphs (a) and (b) to include references to applicants for licenses, standard design certifications, and standard design approvals under part 53 in addition to part 52.
10 CFR part 20, subpart F - Surveys and Monitoring Section 20.1501 General.
This proposed rule would revise § 20.1501 regarding the requirement for retention of records from surveys describing the location and amount of subsurface residual radioactivity at a site to include a reference to the retention requirements under part 53.
10 CFR part 20, subpart J - Precautionary Procedures Section 20.1905 Exemptions to labeling requirements.
This proposed rule would revise § 20.1905 to apply to facilities licensed under part 53 in addition to parts 50 and 52 regarding exemptions to labeling requirements.
10 CFR part 20, subpart K - Waste Disposal Section 20.2004 Treatment or disposal by incineration.
This proposed rule would revise § 20.2004, paragraph (b)(1) to include references to part 53 regarding the treatment or disposal of waste oil by incineration.
34 10 CFR part 20, subpart M - Reports Section 20.2201 Reports of theft or loss of licensed material.
This proposed rule would update § 20.2201 to include references to part 53 in paragraphs (a)(2)(i), (b)(2)(i) and (c) regarding requirements for reports of theft or loss of licensed material.
Section 20.2202 Notification of incidents.
This proposed rule would revise § 20.2202, paragraph (d)(1) to add a reference to part 53 regarding reports to the NRC Operations Center.
Section 20.2203 Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits.
This proposed rule would update § 20.2203, paragraph (c) to refer to procedures under part 53 for reporting occurrences of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits.
Section 20.2206 Reports of individual monitoring.
This proposed rule would update § 20.2206, paragraph (a)(1) to include a reference to part 53.
10 CFR part 21 - Reporting of Defects and Noncompliance
35 Section 21.2 Scope.
This proposed rule would update § 21.2, paragraphs (a)(2)-(4) and paragraph (c) to include references to part 53 regarding the scope and applicability of part 21 requirements.
Section 21.3 Definitions.
This proposed rule would revise § 21.3 to update the definitions of basic component, commercial grade item, critical characteristics, dedicating entity, dedication, defect, and substantial safety hazard with references to part 53.
Section 21.21 Notification of failure to comply or existence of a defect and its evaluation.
This proposed rule would amend § 21.21, incorporating references to part 53, to update the requirements for notifying the Commission of a failure to comply or defect in paragraphs (a)(3), (a)(3)(i), and (d)(1)(i)-(ii).
Section 21.51 Maintenance and inspection of records.
This proposed rule would revise § 21.51, paragraphs (a)(4)-(5) to apply to applicants for standard design certification and applicants or holders of a standard design approval under part 53, in addition to part 52, regarding the retention of records.
Section 21.61 Failure to notify.
This proposed rule would update § 21.61, paragraph (b) to include references to part 53 licensees and applicants regarding failure to provide the notice required in
§ 21.21.
36 10 CFR part 25 - Access Authorization Section 25.5 Definitions.
This proposed rule would update the definition of license in § 25.5 to include those issued under part 53.
Section 25.17 Approval for processing applicants for access authorization.
This proposed rule would revise § 25.17, paragraph (a) to add a reference to part 53 regarding AAs for individuals who need access to classified information in connection with activities under part 53.
Section 25.35 Classified visits.
This proposed rule would update § 25.35, paragraph (a) to apply the requirements for classified visits to licensees, certificate holders, and applicants under part 53 in addition to part 52.
10 CFR part 26, Fitness For Duty Programs Part 26 placeholder.
10 CFR part 30 - Rules of General Applicability to Domestic Licensing of Byproduct Material
37 Section 30.4 Definitions.
This proposed rule would update the definition of utilization facility in § 30.4 to include utilization facilities defined in the regulations under part 53 in addition to part 50.
Section 30.50 Reporting requirements.
This proposed rule would revise § 30.50 to include references to part 53 in addition to part 50.
10 CFR part 40 - Deomestic Licensing of Source Material Section 40.60 Reporting requirements.
This proposed rule would revise § 40.60, paragraph (c)(3) to include references to part 53 in addition to part 50 regarding reporting requirements.
10 CFR part 50, Domestic Licensing of Production and Utilization Facilities Section 50.44 Combustible gas control for nuclear power reactors.
This proposed rule would amend § 50.44, paragraphs (c) and (d) to incorporate the appropriate references to Framework B of part 53.
Section 50.46 Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.
This proposed rule would amend § 50.46, paragraphs (a)(1) and (a)(3)(i)-(iii) to incorporate the appropriate references to Framework B of part 53.
Section 50.47 Emergency plans.
This proposed rule would amend § 50.47 by revising paragraph (a)(1)(ii) to apply to COLs under part 53 and adding paragraphs (a)(1)(v) and (a)(1)(vi) regarding
38 proposed emergency plans under part 53 in connection with an application for an ESP under part 53.
Section 50.55a Codes and standards.
This proposed rule would amend § 50.55a, paragraphs (b)(1),
(b)(2)(xxi)(B)(3), (b)(3)(iii), (b)(4), (c), (d), (d)(1), (e), (e)(1), (f), (f)(3), (f)(3)(iii)(B),
(f)(23)(iv)(B), (f)(4)(i), (g),(g)(2)(ii),(g)(3)(ii), (g)(4)(i), (g)(4)(v), and (h)(3) to incorporate the appropriate references to boiling or pressurized water-cooled commercial nuclear plants under Framework B of part 53.
Section 50.60 Acceptance criteria for fracture prevention measures for light water nuclear power reactors for normal operation.
This proposed rule would amend § 50.60, paragraphs (a) and (b) to incorporate the appropriate references to Framework B of part 53.
Section 50.61 Fracture toughness requirements for protection against pressurized thermal shock events.
This proposed rule would update § 50.61(b) to extend the requirements of this section to pressurized-water nuclear power reactors with a license or permit issued under Framework B of this part.
Section 50.62 Requirements for reduction of risk from anticipated transients without scram events for light-water-cooled nuclear power plants.
This proposed rule would revise § 50.62, paragraphs (a), (b), (c)(4), (c)(6),
and (d) to include the appropriate references to Framework B of this part.
Section 50.63 Loss of all alternating current power.
39 This proposed rule would revise § 50.63 to update this section with the appropriate references to Framework B of this part.
Appendix A to 10 CFR part 50 This proposed rule would revise appendix A to 10 CFR part 50 by revising the Introduction and Criterion 19 to incorporate the appropriate references to Framework B of this part.
Appendix G to 10 CFR part 50 This proposed rule would update appendix G to part 50 with a reference to part 53.
Appendix H to 10 CFR part 50 This proposed rule would update appendix H to part 50 with references to
§ 53.040 where appropriate.
Appendix J to 10 CFR part 50 This proposed rule would revise appendix J to part 50 by adding references to Framework B of this part where appropriate.
Appendix S to 10 CFR part 50 This proposed rule would revise appendix S to part 50 by updating the introduction and definitions to include references to part 53.
40 10 CFR part 51 - Environmental Protection Regulations for Domestic Licensing and Related Regualtory Functions 10 CFR part 51, subpart A - National Environmental Policy Act - Regulations Implementing Section 102(2)
Section 51.20 Criteria for and identification of licensing and regulatory actions requiring environmental impact statements.
This proposed rule would amend § 51.20, paragraphs (b)(1)-(2) to require an environmental impact statement following the issuance of a CP or ESP under part 53, or the issuance to renewal of a full power or design capacity license to operate a nuclear power reactor, testing facility, or fuel reprocessing plant under part 53.
Section 51.22 Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review.
This proposed rule would amend § 51.22 to include corresponding references to part 53 in paragraphs (c)(3), (c)(9), (c)(12), (c)(17), (c)(22)-(23).
Section 51.26 Requirement to publish notice of intent and conduct scoping process.
This proposed rule would revise § 51.26, paragraph (d) to add a reference to part
- 53.
41 Section 51.30 Environmental assessment.
This proposed rule would revise the introductory text to paragraph (a) and revise paragraphs (d) and (e) of § 51.30 to incorporate the appropriate references to part 53 regarding environmental assessments.
Section 51.31 Determinations based on environmental assessment.
This proposed rule would revise § 51.31, paragraph (a) to include a reference to part 53.
Section 51.32 Finding of no significant impact.
This proposed rule would revise § 51.32, paragraphs (b)(1) and (3), finding there is no significant environmental impact associated with the issuance of standard design certifications and manufacturing licenses under part 53.
Section 51.49 Environmental report-limited work authorization.
This proposed rule would amend § 51.50, paragraphs (a), (b)(4), and the introductory text of paragraph (c) to require applicants for an ESP under part 53 requesting a limited work authorization to include the environmental report required by
§ 51.50(b).
Section 51.50 Environmental report - construction permit, early site permit, or combined license stage.
This proposed rule would revise § 51.50, paragraphs (a), (b)(4), and the introductory text for paragraph (c) to incorporate the appropriate references to part 53.
42 Section 51.53 Postconstruction environmental reports.
This proposed rule would revise § 51.53 to include the appropriate references to part 53 in paragraph (d) regarding a license termination plan or decommissioning plan and related requirements for postconstruction environmental reports.
Section 51.54 Environmental report - manufacturing license.
This proposed rule would update § 51.54, paragraph (a) to require applicants for manufacturing licenses under part 53 to submit an environmental report with the application.
Section 51.55 Environmental report - standard design certification.
This proposed rule would update § 51.55, paragraph (a) to require applicants for a standard design certification under part 53 to submit an environmental report with the application.
Section 51.58 Environmental report - number of copies; distribution.
This proposed rule would revise § 51.58, paragraph (b) to incorporate the appropriate references to part 53.
Section 51.77 Distribution of draft environmental impact statement.
This proposed rule would revise the introductory text for paragraph (a) of § 51.77 to add a reference to part 53.
43 Section 51.92 Supplement to the final environmental impact statement.
This proposed rule would revise § 51.92, paragraph (b) to apply to COL applications referencing an ESP under part 53.
Section 51.95 Postconstruction environmental impact statements.
This proposed rule would revise the introductory text for paragraph (c) to § 51.95 to include a reference to part 53 regarding the Commissions obligations to prepare an environmental impact statement following the renewal of an operating or COL for a nuclear plant under 53.
Section 51.101 Limitations on actions.
This proposed rule would revise § 51.101, paragraph (a)(2) to include the corresponding references to part 53 where appropriate.
Section 51.103 Record of decision - general.
This proposed rule would update § 51.103, paragraph (a)(6) to apply to the issuance of a limited work authorization in connection with a CP or COL under part 53.
Section 51.105 Public hearings in proceedings for issuance of construction permits or early site permits; limited work authorizations.
This proposed rule would update § 51.105, paragraph (c)(1) to include the appropriate reference to limited work authorizations under part 53 for CPs or ESPs.
44 Section 51.107 Public hearings in proceedings for issuance of combined licenses; limited work authorizations.
This proposed rule would amend § 51.107 by revising the introductory text for paragraphs (a) and (b) and updating paragraph (d)(1) to include the appropriate corresponding references to part 53.
Section 51.108 Public hearings on Commission findings that inspections, tests, analyses, and acceptance criteria of combined licenses are met.
This proposed rule would amend § 51.108 to incorporate the appropriate references to part 53.
10 CFR part 53General Overview and Requirements Section 53.000 Purpose.
This proposed rule would add § 53.000, which would state the purpose of part 53, which is to establish a risk-informed, technology-inclusive regulatory scheme that enables part 53 licensees to choose between two distinct regulatory frameworks.
Section 53.010 Frameworks.
This proposed rule would add § 53.010, which would provide an overview of the two distinct frameworks under which part 53 applicants may seek a license, certificate, or permit.
45 10 CFR part 53, subpart AGeneral Provisions This proposed rule would add subpart A, General Provisions, to establish a set of general provisions that would apply to all applicants and licensees under part 53.
Section 53.015 Scope.
This proposed rule would add § 53.015, which would extend the provisions of subpart A to all applicants and licensees under part 53.
Section 53.020 Definitions.
This proposed rule would add § 53.020, which would define terms common to Frameworks A and B of part 53.
Section 53.024 Definitions specific to Framework A.
This proposed rule would add § 53.024, which would define terms that would be applicable to Framework A.
Section 53.028 Definitions specific to Framework B.
This proposed rule would add § 53.028, which would define terms that would be applicable to Framework B.
Section 53.040 Written communications.
This proposed rule would add § 53.040, which would govern how applicants and licensees submit written communications, including applications and other required submittals, to the NRC.
46 Section 53.050 Deliberate misconduct.
This proposed rule would add § 53.050, which would prohibit licensees, applicants, contractors and subcontractors from deliberately violating NRC rules, regulations, or orders, or the terms, conditions, and limitations of a part 53 license. This proposed rule would also prohibit deliberate submissions of incomplete or inaccurate information. Violations would be subject to enforcement actions under subpart B of part
- 2.
Section 53.060 Employee protection.
This proposed rule would add § 53.060, which would prohibit applicants and licensees from discriminating against employees for engaging in the protected activities listed in this section and provide remedial procedures for employees who believe they are the subjects of discrimination.
Section 53.070 Completeness and accuracy of information.
This proposed rule would add § 53.070, which would require licensees and applicants under part 53 to maintain complete and accurate information in accordance with all applicable laws, Commission regulations, and the terms and conditions of their license. This proposed rule would also require licensees to notify the Commission within two days of identifying information with material implications for public health and safety or common defense and security.
Section 53.080 Specific exemptions.
47 This proposed rule would add § 53.080, which would establish the special circumstances under which the Commission could grant exemptions to part 53 licensees and the Commissions criteria for making such a determination.
Section 53.090 Standards for review.
This proposed rule would add § 53.090 to establish the standards that the Commission would take into account when determining whether to issue a permit or license under part 53.
Section 53.100 Jurisdictional limits.
This proposed rule would add § 53.100, which would provide that permits, licenses, standard design approvals, and standard design certifications are solely issued for activities within the jurisdiction of the United States.
Section 53.110 Attacks and destructive acts.
This proposed rule would add § 53.110, which would exempt licensees or applicants under part 53 from providing design features to protect against attacks or destructive acts directed at the facility by United States adversaries.
Section 53.115 Rights related to special nuclear material.
This proposed rule would add § 53.115, which would establish provisions regarding the rights to special nuclear material under a part 53 license.
Section 53.117 License suspension and rights of recapture.
48 This proposed rule would add § 53.117, which would provide that the Commission may suspend licenses and recapture material or control of a facility in a state of war or national emergency declared by Congress.
Section 53.120 Information collection requirements: OMB approval.
This proposed rule would add § 53.120, which would establish requirements for information collection requirements and Office of Budget and Management approval.
10 CFR part 53, subpart BTechnology-Inclusive Safety Requirements This proposed rule would add subpart B, Technology-Inclusive Safety Requirements, to establish a set of technology-inclusive performance standards that would be used throughout Framework A within part 53 to determine appropriate regulatory controls for SSCs, human actions, and programs.
Section 53.200 Safety objectives.
This proposed rule would add § 53.200 to establish the overall safety objectives of minimizing the possibility of an immediate threat to public health and safety and ensuring additional measures are taken as may be appropriate when considering potential risks to public health and safety in the design, construction, operation, and decommissioning of commercial nuclear plants within Framework A of this part.
Section 53.210 Safety criteria for design basis accidents.
This proposed rule would add § 53.210 to set a dose value to ensure that plants are designed to limit the publics radiation exposure in the event of a design basis accident.
49 Section 53.220 Safety criteria for licensing basis events other than design basis accidents.
This proposed rule would add § 53.220 to require plants to implement a combination of design features and programmatic controls to minimize risks to the public in the event of a licensing basis event other than a design basis accident.
Section 53.230 Safety functions.
This proposed rule would add § 53.230, which specifies that limiting the release of radioactive materials from the facility is the primary safety function of a commercial nuclear plant, and that additional safety functions must be defined to support the retention of radioactive materials during licensing basis events.
Section 53.240 Licensing basis events.
This proposed rule would add § 53.240 to require commercial nuclear plants to conduct an analysis of licensing basis events to confirm that design features and programmatic controls satisfy the safety criteria under §§ 53.210 and 53.220, or alternatively, under § 53.470.
Section 53.250 Defense in depth.
This proposed rule would add § 53.250 to establish a performance-based, defense-in-depth approach to address uncertainties about the effectiveness and reliability of plant SSCs, personnel, and programmatic controls.
50 Section 53.260 Normal operations.
This proposed rule would add § 53.260, requiring plants to be designed to ensure that the publics exposure to doses of radiation is ALARA, and not to exceed the limits provided in subpart D to part 20, during normal plant operation.
Section 53.270 Protection of plant workers.
This proposed rule would add § 53.270 to require that plants use a combination of design features and programmatic controls to ensure that occupational exposure to doses of radiation is ALARA, and not to exceed the limits provided in subpart C to part
- 20.
10 CFR part 53, subpart CDesign and Analysis Requirements This proposed rule would add subpart C, Design and Analysis Requirements, which requires the implementation of certain design features and the performance of risk assessments and analyses to demonstrate compliance with the safety criteria and safety functions in subpart B.
Section 53.400 Design features for licensing basis events.
This proposed rule would add § 53.400, which would require design features that satisfy the safety criteria defined in §§53.210 and 53.220 or § 53.470 and fulfill the safety functions identified in § 53.230 during licensing basis events.
Section 53.410 Functional design criteria for design-basis accidents.
This proposed rule would add § 53.410, which would stipulate that functional design criteria must be defined for each design feature required by § 53.400 to
51 demonstrate compliance with the safety criteria defined in § 53.210 for design basis accidents.
Section 53.415 Protection against external hazards.
This proposed rule would add § 53.415, which would require safety-related systems, structures, and components to be designed to withstand the effects of natural phenomena and human-related hazards while performing the intended safety functions.
Section 53.420 Functional design criteria for licensing basis events other than design-basis accidents.
This proposed rule would add § 53.420, which would require functional design criteria to be defined for each design feature required by § 53.400 to demonstrate compliance with the safety criteria defined in § 53.220 for licensing basis events other than design basis accidents.
Section 53.425 Design features and functional design criteria for normal operations.
The proposed rule would add § 53.425, which would require commercial nuclear plants to implement design features and define functional design criteria sufficient to demonstrate compliance with §§ 53.260(a) and 53.260(b) and conduct monitoring to ensure the publics exposure to radiation does not exceed the limits established in
§§ 53.260(a) and 53.260(b).
52 Section 53.430 Design features and functional design criteria for protection of plant workers.
The proposed rule would add § 53.430, which would require commercial nuclear plants to implement design features and define functional design criteria sufficient to demonstrate compliance with §§ 53.270(a) and 53.270(b) and conduct monitoring to ensure the occupational exposure to radiation does not exceed the limits established in
§§ 53.270(a) and 53.270(b).
Section 53.440 Design requirements.
The proposed rule would add § 53.440, which would establish various design feature requirements, including for protection against fires and explosions, criticality accidents, and the impact of a large commercial aircraft.
Section 53.450 Analysis requirements.
The proposed rule would add § 53.450, which would require commercial nuclear plants to perform probabilistic risk assessments in combination with other analytical methods to identify and assess risks and determine compliance with the safety criteria in subpart B. In addition, § 53.450 would require analysis of design basis accidents and other analyses to assess the adequacy of protections against fire, aircraft impact, and the release of effluents.
Section 53.460 Safety categorization and special treatment.
The proposed rule would add § 53.460 to address the safety classification of SSCs and determine appropriate special treatments.
53 Section 53.470 Maintaining analytical safety margins used to justify operational flexibilities.
The proposed rule would add § 53.470 to permit applicants and licensees to implement more restrictive criteria than that defined in §§ 53.220 and 53.450(e) to support operational flexibilities.
Section 53.480 Earthquake engineering.
The proposed rule would add § 53.480 to provide overall seismic design considerations in light of the safety criteria in subpart B and siting requirements in subpart D.
10 CFR part 53, subpart DSiting Requirements The proposed rule would add subpart D, Siting, which would address requirements associated with the siting of commercial nuclear facilities, including considerations of external hazards and potential adverse impacts on the surrounding population.
Section 53.500 General siting.
The proposed rule would add § 53.500, which would require a siting assessment for each commercial nuclear plant to ensure that design features and programmatic controls are sufficient to address licensing basis events and mitigate potential adverse impacts of the plant on the surrounding environs.
Section 53.510 External hazards.
54 The proposed rule would add § 53.510, which would require site-specific assessments, including an evaluation of geological and seismic siting factors, to identify and characterize the external hazard level for a range of natural and manmade hazards.
Section 53.520 Site characteristics.
The proposed rule would add § 53.520, which would require the design and analyses conducted under subpart C to consider how site characteristics may contribute to licensing basis events.
Section 53.530 Population-related considerations.
The proposed rule would add § 53.530, which would establish requirements related the facilitys exclusion area, low population zone, and population center distance.
Section 53.540 Siting interfaces.
The proposed rule would add § 53.540, which would require that external hazards and site characteristics must be accounted for in the design features, programmatic controls, and supporting analyses used to demonstrate compliance with the safety criteria in §§ 53.210 and 53.220.
10 CFR part 53, subpart EConstruction and Manufacturing Requirements The proposed rule would add subpart E, Construction and Manufacturing Requirements, which would establish requirements for the construction of an advanced nuclear plant.
55 Section 53.600 Construction and manufacturing - scope and purpose.
The proposed rule would add § 53.600, which would apply to construction and manufacturing activities authorized by a CP, COL, Manufacturing License (ML), or Limited Work Authorization (LWA) issued under this part.
Section 53.605 Reporting of defects and noncompliance.
The proposed rule would add § 53.605, which stipulates that each CP, ML, and COL is subject to procedures, notification requirements, records retention required under this section with respect to reporting of defects and noncompliance.
Section 53.610 Construction.
The proposed rule adds § 53.610 to address the management and control of the construction of a commercial nuclear plant, including specific requirements for manufacturing activities, control of radioactive materials, fuel loading, and transportation, acceptance, and installation of a manufactured reactor.
Section 53.620 Manufacturing.
This proposed rule would add § 53.620, which would ensure that the holders of a manufacturing license under Framework A of this part develop plans, programs, and organizational units to manage and control manufacturing activities.
10 CFR part 53, subpart FRequirements for Operation This proposed rule would add subpart F, Requirements for Operation, which would establish regulatory requirements to ensure that the safety criteria in subpart B
56 are satisfied whenever a commercial nuclear plant licensed under Framework A is operational. This includes periods of normal operation and unplanned events.
Section 53.700 Operational objectives.
This proposed rule would add § 53.700, which would establish general operational objectives to ensure that licensees under Framework A have implemented and maintained the structures, systems, and controls (SSCs) necessary to demonstrate compliance with the safety functions identified in subpart B for addressing normal operations and responding to licensing basis events.
Section 53.710 Maintaining capabilities, availability, and reliability of structures, systems, and components.
This proposed rule would add § 53.710, which would require licensees under Framework A to demonstrate compliance with the safety criteria in subpart B by establishing technical specifications for all safety-related (SR) SSCs and developing documents and procedures for all non-safety related but safety significant (NSRSS)
SSCs.
Section 53.715 Maintenance, repair, and inspection programs.
This proposed rule would add § 53.715, which would require licensees to develop, implement, and maintain programs to assess and manage any risks posed by maintenance activities and to evaluate the efficacy of performance, condition monitoring, and maintenance activities to ensure compliance with the safety criteria of subpart B.
57 Section 53.720 Response to seismic events.
This proposed rule would add § 53.730, which would establish requirements for licensees to respond to a seismic event during the operating phase of the life cycle of a commercial nuclear plant.
Section 53.725 General staffing, training, personnel qualifications, and human factors requirements.
This proposed rule would add § 53.725 that would provide an overview of the staffing, training, personnel qualifications, and human factors requirements established in §§ 53.725 to 53.830 and would provide definitions for certain terms used within those sections.
Section 53.726 Communications.
This proposed rule would add § 53.726 that would contain communications requirements applicable to sections §§ 53.725 to 53.830.
Section 53.727 Information collection requirements.
This proposed rule would add § 53.727 that would contain information collection requirements and OMB clearance information.
Section 53.728 Completeness and accuracy of information.
This proposed rule would add § 53.728 that would require submitted information to be complete and accurate in all material respects.
58 Section 53.730 Defining, fulfilling, and maintaining the role of personnel in ensuring safe operations.
This proposed rule would add § 53.730, which would establish technical requirements for applicants or holders of operating licenses or COLs within the areas of human factors engineering, human-system interface design, concept of operations, functional requirements analysis, function allocation, operating experience, procedures, staffing, operator training, operator examinations, and operator proficiency.
Section 53.735 General exemptions.
This proposed rule would add § 53.735, which would establish general exemptions for licensed operators.
Section 53.740 Facility licensee requirements - general.
This proposed rule would add § 53.740, which would establish requirements for facility licensees regarding various aspects of facility operations.
Section 53.745 Operator license requirements.
This proposed rule would add § 53.745 that would require individuals to be licensed to perform certain functions.
Section 53.750 Violations.
This proposed rule would add § 53.750, which would address violations of United States laws, any rule, regulation, or order issued by the NRC pursuant to its authority under the Atomic Energy Act of 1954, as amended, or any term, condition, or limitation of a license issued under part 53.
59 Section 53.755 Criminal penalties.
This proposed rule would add § 53.755, which would address provisions for criminal sanctions.
Section 53.760 Operator licensing.
This proposed rule would add § 53.760, which would address the applicability of the requirements of §§ 53.760 though 53.795 for specifically licensed operators and senior operators.
Section 53.765 Medical requirements.
This proposed rule would add § 53.765, which would establish medical requirements for specifically licensed operators and senior operators.
Section 53.770 Incapacitation because of disability or illness.
This proposed rule would add § 53.770, which would establish requirements to address permanent medical conditions for specifically licensed operators and senior operators.
Section 53.775 Applications for operator and senior operator licenses.
This proposed rule would add § 53.775, which would establish the application process and requirements for individuals applying for specific operator and senior operator licenses.
60 Section 53.780 Training, examination, and proficiency programs.
This proposed rule would add § 53.780, which would contain the requirements associated with specifically licensed operator and senior operator initial training, initial examinations, requalification training, requalification examinations, examination integrity, simulation facilities, waivers, and proficiency.
Section 53.785 Conditions of operator and senior operator licenses.
This proposed rule would add § 53.785, which would establish conditions for specific operator and senior operator licenses.
Section 53.790 Issuance, modification, and revocation of operator and senior operator licenses.
This proposed rule would add § 53.790, which would contain requirements associated with the issuance, modification, or revocation of specific operator and senior operator licenses.
Section 53.795 Expiration and renewal of operator and senior operator licenses.
This proposed rule would add § 53.795 that would contain requirements associated with the expiration and renewal of specific operator and senior operator licenses.
Section 53.800 Facility licensees that comply with §§ 53.800 through 53.820.
This proposed rule would add § 53.800 that would establish the technical criteria by which commercial nuclear plants under Framework A or B are determined to be of the
61 self-reliant mitigation class of facilities that would be staffed by generally licensed reactor operators in lieu of specifically licensed operators and senior operators.
Section 53.805 Facility licensee requirements related to generally licensed reactor operators.
This proposed rule would add § 53.805 that would establish requirements that apply to the facility licensee at those facilities staffed by generally licensed reactor operators.
Section 53.810 Generally licensed reactor operators.
This proposed rule would add § 53.810, which would describe the general license for generally licensed reactor operators.
Section 53.815 Generally licensed reactor operator training, examination, and proficiency programs.
This proposed rule would add § 53.815 that would contain the requirements for generally licensed reactor operator initial training, initial examinations, continuing training, requalification examinations, examination integrity, simulation facilities, waivers, and proficiency.
Section 53.820 Expiration.
This proposed rule would add new § 53.820 that would address the expiration of the general license for generally licensed reactor operators.
62 Section 53.830 Training and qualification of commercial nuclear plant personnel.
This proposed rule would add § 53.830 that would address training and qualification requirements for supervisors, technicians, and other appropriate operating personnel at commercial nuclear plants.
Section 53.845 Programs.
This proposed rule would add § 53.845, which would require licensees to establish programs that include, but are not limited to, radiation protection, emergency preparedness, security, quality assurance, integrity assessment, fire protection, inservice inspection and testing, and facility safety, to ensure that the safety criteria and functions in subpart B are maintained during normal operations and licensing basis events.
Section 53.850 Radiation protection.
This proposed rule would add § 53.850, which would require licensees under Framework A to implement and maintain programs and processes to limit and monitor radioactive plant effluents and limit the exposure of plant personnel and the public.
Section 53.855 Emergency preparedness.
This proposed rule would add § 53.855, which would require licensees under Framework A to develop, implement, and maintain an emergency response plan for radiological emergencies.
63 Section 53.860 Security programs.
This proposed rule would add § 53.860, which would require licensees under Framework A to develop, implement, and maintain programs for physical security, fitness for duty, AA, cybersecurity, and information security.
Section 53.865 Quality assurance.
This proposed rule would add § 53.865, which would require licensees under Framework A to establish a quality assurance program that includes a written manual to ensure activities are conducted in accordance with codes and standards found acceptable by the NRC.
Section 53.870 Integrity assessment programs.
This proposed rule would add § 53.870, which would require licensees under Framework A to establish an integrity assessment program to ensure that the plant continues to fulfill safety criteria and functional design criteria as it ages.
Section 53.875 Fire protection.
This proposed rule would add § 53.875, which would require licensees under Framework A to establish a fire protection plan and describe the necessary elements that the plan must incorporate.
Section 53.880 Inservice inspection/inservice testing.
This proposed rule would add § 53,880, which would establish requirements for licensees regarding the development and implementation of a program for In-Service Inspection and In-Service Testing.
64 Section 53.890 Facility safety program.
This proposed rule would add § 53.890, which would require licensees under Framework A to establish a risk-informed, performance-based facility safety program.
Section 53.910 Procedures and guidelines.
This proposed rule would require licensees under Framework A to develop, maintain, and implement procedures and guidelines that address normal plant operations and responses to unplanned events.
10 CFR part 53, subpart GDecommissioning Requirements This proposed rule would add subpart G, Decommissioning Requirements, to establish decommissioning requirements for applicants for or holders of an Operating License (OL) or Combined Operating License (COL) under Framework A of 10 CFR part 53.
Section 53.1000 Scope and purpose.
This proposed rule would add § 53.1000 that would establish the scope of the decommissioning requirements for applicants and licensees under Framework A of part 53 and describe the contents of subpart G of part 53.
Section 53.1010 Financial assurance for decommissioning.
This proposed rule would add § 53.1010 that would establish the requirement that applicants for an OL or COL under Framework A of part 53 provide reasonable assurance that funds will be available for the decommissioning process. This section
65 would describe the requirements associated with the required plan and an associated decommissioning report that ensures and documents that adequate funding for decommissioning will be available.
Section 53.1020 Cost estimates for decommissioning.
This proposed rule would add § 53.1020 that would require site-specific cost estimates for decommissioning and establish the aspects that must be included in the estimate.
Section 53.1030 Annual adjustments to cost estimates for decommissioning.
This proposed rule would add § 53.1030 that would require that holders of an OL or COL under Framework A of part 53 annually adjust their cost estimate for decommissioning to account for escalation in labor, energy, and waste burial costs. This section would allow licensees to elect either a site-specific adjustment factor or a generic adjustment factor.
Section 53.1040 Methods for providing financial assurance for decommissioning.
This proposed rule would add § 53.1040 that would establish suitable methods that holders of an OL or COL under Framework A of part 53 may use to provide financial assurance for decommissioning to the NRC.
Section 53.1045 Limitations on the use of decommissioning trust funds.
This proposed rule would add § 53.1045 that would establish requirements for decommissioning trust funds under Framework A of this part, including criteria for using decommissioning trust funds and required terms.
66 Section 53.1050 NRC oversight.
This proposed rule would add § 53.1050 that would outline the steps the NRC may take to ensure adequate accumulation of decommissioning funds.
Section 53.1060 Reporting and recordkeeping requirements.
This proposed rule would add § 53.1060 that would contain reporting and recordkeeping requirements related to decommissioning for each holder of an OL or COL under Framework A of part 53. This section would outline requirements for documents such as: certification of decommissioning funding, decommissioning cost estimates and copies of financial instruments, licensee records of information important to safe and effective decommissioning, PSDARs, financial assurance reports, and reports on the status of funding for managing irradiated fuel.
Section 53.1070 Termination of license.
This proposed rule would add § 53.1070 that would establish procedures for decommissioning and license termination applicable to licensees under Framework A of this part that have determined to permanently cease operations.
Section 53.1075 Program requirements during decommissioning.
This proposed rule would add § 53.1075, which would require licensees under Framework A of this part to establish and maintain a decommissioning fire protection program to prevent, detect, and control fires, and ensure that the risk of fire induced radiological hazards are minimized through the various stages of facility decommissioning.
67 Section 53.1080 Release of part of a commercial nuclear plant or site for unrestricted use.
This proposed rule would add § 53.1080 that would establish licensee procedures for requesting and NRC procedures for approving partial release of a commercial nuclear plant or site for unrestricted use prior to receiving approval of a license termination plan from the Commission under Framework A of this part.
10 CFR part 53, subpart HLicenses, Certifications, and Approvals Section 53.1100 Filling of application for licenses, certifications, or approvals; oath or affirmation.
This proposed rule would add § 53.1100, which would establish requirements for applicants seeking a standard design approval, standard design certification, license, or permit under Framework A to submit and amend an application.
Section 53.1101 Requirement for license.
This proposed rule would add § 53.1101, which would prohibit any use of a utilization facility except as authorized by a license issued by the Nuclear Regulatory Commission.
Section 53.1103 Combining applications and licenses.
This proposed rule would add § 53.1103, which would permit applicants seeking multiple licenses under Framework A to submit a single application, and the Commission to issue a single license for activities that would otherwise be licensed separately.
68 Section 53.1106 Elimination of repetition.
This proposed rule would add § 53.1106, which would allow applicants under Framework A to reference information contained in previous documents filed with the Commission so long as those references are clear and specific.
Section 53.1109 Contents of applications; general information.
This proposed rule would add § 53.1109, which would establish the general content to be included in applications made under Framework A of this part, including but not limited to the identifying information of the applicant and the radiological emergency response plans of government entities within the plume exposure pathway emergency planning zone.
Section 53.1112 Environmental conditions.
This proposed rule would add § 53.1112, which would allow the Commission to attach conditions to CPs, ESPs, and licenses issued under Framework A to address environmental issues during construction, operation, or decommissioning. These conditions may be derived from the information contained in the environmental report submitted as part of the application for a permit or license.
Section 53.1115 Agreement limiting access to classified information.
This proposed rule would add § 53.1115, which would require applicants to agree in writing, prior to receiving a license or standard design approval under Framework A, to restrict individuals with access to plant facilities from possessing Restricted Data or classified National Security Information until they have received the appropriate AA.
69 Section 53.1118 Ineligibility of certain applicants.
This proposed rule would add § 53.1118, which would prevent citizens, nationals, or agents of a foreign country, or corporations owned, controlled, or dominated by a foreign entity from applying for or obtaining a license under Framework A.
Section 53.1120 Exceptions and exemptions from licensing requirements.
This proposed rule would add § 53.1120, which would establish the activities that are exempt from licensing requirements.
Section 53.1121 Public inspection of applications.
This proposed rule would add § 53.1121, which would allow applicant submissions to be made publicly available in accordance with part 2.
Section 53.1124 Relationship between sections.
This proposed rule would add § 53.1124, which would outline the relationship between limited work authorizations, ESPs, standard design approvals, standard design certifications, manufacturing licenses, CPs, operating licenses, and COLs under Framework A.
Section 53.1130 Limited work authorizations.
This proposed rule would add § 53.1130, which would establish requirements for requesting a limited work authorization and grounds for the Commission to issue a limited work authorization. It would also contain details about the effect of a limited work authorization and the implementation of a redress plan.
70 Section 53.1140 Early site permits.
This proposed rule would add § 53.1140, which would provide an overview of the requirements regarding applications for and the issuance of ESPs under Framework A.
Section 53.1143 Filing of applications.
This proposed rule would add § 53.1143, which would enable an applicant under Framework A to apply for an ESP, regardless of whether they have filed an application for a CP or COL for that site.
Section 53.1144 Contents of applications for early site permits; general information.
This proposed rule would add § 53.1144, which would require applications for ESPs to include the information required by § 53.1109(a) through (d) and (j).
Section 53.1146 Contents of applications for early site permits; technical information.
This proposed rule would add § 53.1146, which would require applicants for ESPs to submit technical information, including but not limited to a Site Safety Analysis Report and emergency plans.
Section 53.1149 Review of applications.
This proposed rule would add § 53.1149, which would establish standards for review of applications for ESPs under Framework A, including requirements for the Commission to prepare an environmental impact statement and assess the adequacy of protective actions in the event of a radiological emergency. It would also require the
71 administrative review of applications and hearings to follow the procedural requirements of part 2.
Section 53.1155 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1115, which would require the ACRS to review safety-related content in the application for an ESP under Framework A.
Section 53.1158 Issuance of early site permit.
This proposed rule would add § 53.1158, which would establish the conditions under which the Commission may issue an ESP under Framework A, as well as the information, terms, and conditions to be included in the permit.
Section 53.1161 Extent of activities permitted.
This proposed rule would add § 53.1161, which would require that a valid ESP only be used for the purpose of site redress, unless the site is referenced in an application for a CP or COL under Framework A.
Section 53.1164 Duration of permit.
This proposed rule would add § 53.1164, which would govern the conditions under which an ESP remains valid following the date of issuance.
Section 53.1167 Limited work authorization after issuance of early site permit.
This proposed rule would add § 53.1167, which would permit the holder of an ESP to request a limited work authorization under § 53.1146(c).
72 Section 53.1170 Transfer of early site permit.
This proposed rule would add § 53.1170, which would govern the transfer of an ESP in accordance with § 53.1570.
Section 53.1173 Application for renewal.
This proposed rule would add § 53.1173, which would establish the conditions and procedures for renewing an ESP under Framework A.
Section 53.1176 Criteria for renewal.
This proposed rule would add § 53.1176, which would establish the criteria that the Commission may use to grant a renewal of an ESP under Framework A.
Section 53.1179 Duration of renewal.
This proposed rule would add § 53.1179, which would govern the duration of a renewed ESP under Framework A.
Section 53.1182 Use of site for other purposes.
This proposed rule would add § 53.1182, which would govern acceptable uses of the site for purposes other than those described in the permit.
Section 53.1188 Finality of early site permit determinations.
This proposed rule would add § 53.1188, which would address the finality of ESP determinations under Framework A.
73 Section 53.1200 Standard design approvals.
This proposed rule would add § 53.1200, which would provide an overview of the procedures for filing an application for a standard design approval under Framework A, the process of review by NRC staff, and referral to the ACRS of standard designs.
Section 53.1203 Filing of applications.
This proposed rule would add § 53.1203, which would enable applicants to submit a final design for the entire facility, or major portions, to the NRC staff for review.
Section 53.1206 Contents of applications for standard design approvals; general information This proposed rule would add § 53.1206, which would require applications for a standard design approval under Framework A to contain the information required by
§ 53.1109(a) through (c) and (j).
Section 53.1209 Contents of applications for standard design approvals; technical information.
This proposed rule would add § 53.1209, which would require the inclusion of certain technical information, including a Final Safety Analysis Report, site parameters, and design information, when an applicant seeks review of a major portion of a standard design.
74 Section 53.1210 Contents of applications for standard design approvals; other application content.
This proposed rule would add § 53.1210, which would require applications for standard design approvals under Framework A to include a description of the availability controls used to satisfy the safety criteria of § 53.220, actions taken to protect Safeguards Information against unauthorized disclosure, evidence that safety questions associated with SSCs have been resolved, and a description of how design features fulfill design criteria.
Section 53.1212 Standards for review of applications.
This proposed rule would add § 53.1212, which would require applications for standard design approval to be reviewed for compliance with the standards in parts 20, 53, and 73.
Section 53.1215 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1215, which would require the ACRS to report on any portions of the application for a standard design approval under Framework A concerning safety.
Section 53.1218 Staff approval of design.
This proposed rule would add § 53.1218, which would require the Nuclear Regulatory Commission to make a determination on the acceptability of the design, publish its decision in the Federal Register, and issue a report analyzing the design that is available at http://nrc.gov. Additionally, the rule would establish the conditions under which a design approval under Framework A remains valid.
75 Section 53.1221 Finality of standard design approvals; information requests.
This proposed rule would add § 53.1221, which would require NRC staff and the ACRS to rely upon an approved design in their review of any standard design certification or individual facility license application under Framework A that references the standard design approval. The proposed rule would also govern requirements for issuing information requests.
Section 53.1230 Standard design certifications.
This proposed rule would add § 53.1230, which would provide an overview of the requirements and procedures that govern the issuance of standard design certifications under Framework A.
Section 53.1233 Filing of applications.
This proposed rule would add § 53.1233, which would enable an application for design certification to be filed, regardless of whether an application for a CP, COL, or manufacturing license has been filed, provided it complies with the filing requirements in
§ 53.040 and §§ 2.811 through 2.819.
Section 53.1236 Contents of applications for standard design certifications; general information.
This proposed rule would add § 53.1236, which would require an application for a standard design certification under Framework A to contain all of the information required by § 53.1109(a) through (c) and (j).
76 Section 53.1239 Contents of applications for standard design certifications; technical information.
This proposed rule would add § 53.1239, which would require applicants for a standard design certification under Framework A to submit a Final Safety Analysis Report that includes technical design information at a level of detail sufficient to enable the Commission to make a safety determination.
Section 53.1241 Contents of applications for standard design certifications; other application content.
This proposed rule would add § 53.1241, which would require applications for standard design certifications under Framework A to include an environmental report, as well as a description of the availability controls used to satisfy the safety criteria of
§ 53.220, actions taken to protect Safeguards Information against unauthorized disclosure, evidence that safety questions associated with SSCs have been resolved, and a description of how design features fulfill design criteria.
Section 53.1242 Review of applications.
This proposed rule would add § 53.1242, which would require applications for standard design certifications to be reviewed for compliance with the standards in parts 2, 51, 73, and Framework A of this part. It would also establish procedural requirements for reviewing applications and holding hearings in accordance with subpart H of part 2.
77 Section 53.1245 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1245, which would require the ACRS to report on any portions of the application for a standard design approval under Framework A concerning safety.
Section 53.1248 Issuance of standard design certification.
This proposed rule would add § 53.1248, which would establish the conditions under which the Commission may issue a design certification rule that specifies the site parameters, design characteristics, and any additional terms and conditions of the design certification rule.
Section 53.1251 Duration of certification.
This proposed rule would add § 53.1251, which would set the conditions under which a standard design certification remains valid.
Section 53.1254 Application for renewal.
This proposed rule would add § 53.1254, which would establish the conditions and procedures for an application to renew a standard design certification under Framework A.
Section 53.1257 Criteria for renewal.
This proposed rule would add § 53.1257, which would enable the Commission to issue a rule granting the renewal of a standard design certification under Framework A, impose additional requirements, and grant amendment requests.
78 Section 53.1260 Duration of renewal.
This proposed rule would add § 53.1260, which would provide that a renewal of a standard design certification under Framework A is valid for not less than 10 years, nor more than 15 years.
Section 53.1263 Finality of standard design certifications.
This proposed rule would add § 53.1263, which would establish limited conditions under which the Commission may initiate a rulemaking to modify, rescind, or impose new requirements on a standard design certification rule under Framework A. It would also address requests for an exemption from elements of the certification information, and require that applicants for a CP, COL, or manufacturing license that references a design certification rule, make engineering documents available for audit.
Section 53.1270 Manufacturing licenses.
This proposed rule would add § 53.1270, which would provide an overview of the requirements and procedures for applying for and issuing a manufacturing license under Framework A of this part.
Section 53.1273 Filing of applications.
This proposed rule would add § 53.1273, which would establish the requirements to apply for a manufacturing license under Framework A.
79 Section 53.1276 Contents of applications for manufacturing licenses; general information.
This proposed rule would add § 53.1276, which would require applicants for a manufacturing license under Framework A to include the information contained in
§ 53.1109(a) through (e) and (j).
Section 53.1279 Contents of applications for manufacturing licenses; technical information.
This proposed rule would add § 53.1279, which would require an applicant for a manufacturing license under Framework A to include certain technical information in a Final Safety Analysis Report, including but not limited to information about site parameters, design information, manufacturing information, and information related to the deployment of a completed manufactured reactor or manufactured reactor module.
Section 53.1282 Contents of applications for manufacturing licenses; other application content.
This proposed rule would add § 53.1282, which would require applicants for a manufacturing license under Framework A to include in their application inspections, tests, analyses, and acceptance criteria (ITAAC), an environmental report, a description of actions taken to protect Safeguards Information against unauthorized disclosure, and a description of how design features fulfill design criteria.
Section 53.1285 Review of applications.
This proposed rule would add § 53.1285, which would require applications for manufacturing licenses under Framework A to be reviewed for compliance with
80 applicable standards and establish procedural requirements for reviewing applicants and holding hearings in accordance with part 2.
Section 53.1286 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1286, which would require the ACRS to report on any portions of the application for a manufacturing license under Framework A concerning safety.
Section 53.1287 Issuance of manufacturing license.
This proposed rule would add § 53.1287, which would establish the conditions under which the Commission may issue a manufacturing license under Framework A.
Section 53.1288 Finality of manufacturing licenses.
This proposed rule would add § 53.1288, which would address the limited circumstances in which the Commission may modify, rescind, or impose new requirements following the issuance of a manufacturing license under Framework A. It would also address requests for a departure from the specifications of the license.
Section 53.1291 Duration of manufacturing licenses.
This proposed rule would add § 53.1291, which would govern the expiration of a manufacturing license.
81 Section 53.1293 Transfer of manufacturing licenses.
This proposed rule would add § 53.1293, which would provide that a manufacturing license under Framework A may be transferred in accordance with
§ 53.1570.
Section 53.1295 Renewal of manufacturing licenses.
This proposed rule would add § 53.1295, which would establish the procedures for applicants to apply for and the Commission to grant a renewal of a manufacturing license under Framework A.
Section 53.1300 Construction permits.
This proposed rule would add § 53.1300, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to grant a CP under Framework A.
Section 53.1306 Contents of applications for construction permits; general information.
This proposed rule would add § 53.1306, which would require applicants for a CP under Framework A to submit the general information required by § 53.1109, as well as financial information.
Section 53.1309 Contents of applications for construction permits; technical information.
This proposed rule would add § 53.1309, which would require applicants for a CP under Framework A to submit a Preliminary Safety Analysis Report (PSAR) and a
82 description of actions taken to protect Safeguards Information from unauthorized disclosure.
Section 53.1312 Contents of applications for construction permits; other application content.
This proposed rule would add § 53.1312, which would require applicants for a CP under Framework A to submit an environmental report and to provide additional details in the PSAR if the application references an ESP, standard design approval, or standard design certification.
Section 53.1315 Review of applications.
This proposed rule would add § 53.1315, which would require applications for CPs under Framework A to be reviewed for compliance with applicable standards and establish procedural requirements for reviewing applications and holding hearings in accordance with part 2.
Section 53.1318 Finality of referenced NRC approvals, permits, and certifications.
This proposed rule would add § 53.1318, which would address the finality of ESPs, standard design approvals, and standard design certifications referenced in the CP application.
Section 53.1324 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1324, which would require the ACRS to report on any portions of the application for a CP under Framework A concerning safety based on applicable standards in parts 20, 51, 53, 70, and 140.
83 Section 53.1327 Authorization to conduct limited work authorization activities.
This proposed rule would add § 53.1327, which would govern authorization to conduct limited work authorization activities.
Section 53.1330 Exemptions, departures, and variances.
This proposed rule would add § 53.1330, which would govern requests for and the issuance of exemptions from the Commissions regulations, and exemptions, departures, and variances from NRC approvals, permits, and certifications.
Section 53.1333 Issuance of construction permits.
This proposed rule would add § 53.1333, which would establish the conditions under which the Commission may issue CPs and accompanying terms and conditions under Framework A.
Section 53.1336 Finality of construction permits.
This proposed rule would add § 53.1336, which would address the finality of CPs.
Section 53.1342 Duration of construction permit.
This proposed rule would add § 53.1342, which would establish requirements for the expiration of a CP.
84 Section 53.1345 Transfer of construction permits.
This proposed rule would add § 53.1345, which would govern the transfer of CPs under Framework A in accordance with § 53.1345.
Section 53.1348 Termination of construction permits.
This proposed rule would add § 53.1348, which would require the holder of a permit under Framework A to provide written certification to the Commission within 30 of permanently ceasing construction.
Section 53.1360 Operating licenses.
This proposed rule would add § 53.1360, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to issue an operating license under Framework A.
Section 53.1366 Contents of applications for operating licenses; general information.
This proposed rule would add § 53.1366, which would require an application for an operating license under Framework A to include the information required by
§ 53.1109 as well as financial information.
Section 53.1369 Contents of applications for operating licenses; technical information.
This proposed rule would add § 53.1369, which would require an application for an operating license under Framework A to include certain technical information in a
85 Final Safety Analysis report at a level of detail sufficient for the Commission to reach a final conclusion on all safety matters.
Section 53.1372 Contents of applications for operating licenses; other application content.
This proposed rule would add § 53.1372, which would require an application for an operating license under Framework A to include an environmental report and a description of availability controls.
Section 53.1375 Review of applications.
This proposed rule would add § 53.1375, which would establish the standards and procedures for reviewing applications and holding hearings on operating licenses under Framework A.
Section 53.1381 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1381, which would require the ACRS to report on any portions of the application for a CP under Framework A concerning safety based on applicable standards in parts 20, 26, 51, 53, 73, and 140.
Section 53.1384 Exemptions, departures, and variances.
This proposed rule would add § 53.1384, which would govern requests for and the issuance of exemptions from the Commissions regulations, and exemptions, departures, and variances from NRC approvals, permits, and certifications.
86 Section 53.1387 Issuance of operating licenses.
This proposed rule would add § 53.1387, which would establish the conditions under which the Commission may issue operating licenses and accompanying conditions and limitations, including technical specifications, under Framework A.
Section 53.1390 Finality of operating licenses.
This proposed rule would add § 53.1390, which would prevent the Commission from modifying, adding, or deleting any terms or conditions of the operating license, except in accordance with § 53.1390.
Section 53.1396 Duration of operating license.
This proposed rule would add § 53.1396, which would provide that an operating license under Framework A may be valid for up to 40 years.
Section 53.1399 Transfer of an operating license.
This proposed rule would add § 53.1399, which would provide that an operating license under Framework A may be transferred in accordance with § 53.1570.
Section 53.1402 Application for renewal.
This proposed rule would add § 53.1402, which would provide that an application for a renewed operating license under Framework A must be filed in accordance with
§ 53.1595.
87 Section 53.1405 Continuation of an operating license.
This proposed rule would add § 53.1405, which would govern the continuing obligations of the holder of an operating license under Framework A following the permanent cessation of operations.
Section 53.1410 Combined licenses.
This proposed rule would add § 53.1410, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to issue a COL under Framework A.
Section 53.1413 Contents of applications for combined licenses; general information.
This proposed rule would add § 53.1413, which would require an application for an COL under Framework A to include the information required by § 53.1109 as well as financial information.
Section 53.1416 Contents of applications for combined licenses; technical information.
This proposed rule would add § 53.1416, which would require applicants for a COL under Framework A to submit a Final Safety Analysis Report with a level of technical information sufficient to reach a final conclusion on all safety matters.
88 Section 53.1419 Contents of applications for combined licenses; other application content.
This proposed rule would add § 53.1419, which would require applicants for a COL under Framework A to submit an environmental report, a description of availability controls, and the inspections, tests, analyses and acceptance criteria that the licensee must perform.
Section 53.1422 Review of applications.
This proposed rule would add § 53.1422, which would require applications for COLs under Framework A to be reviewed for compliance with applicable standards and establish procedural requirements for reviewing applicants and holding hearings in accordance with part 2.
Section 53.1425 Finality of referenced NRC approvals.
This proposed rule would add § 53.1425 which would address the finality of ESPs, standard design certification rules, standard design approvals, or manufacturing licenses referenced in the application for a COL under Framework A.
Section 53.1431 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.1431, which would require the ACRS to report on any portions of the application for a COL under Framework A concerning safety based on applicable standards in parts 20, 51, 53, 73, and 140.
89 Section 53.1434 Authorization to conduct limited work authorization activities.
This proposed rule would add § 53.1434, which would address authorization to conduct limited work authorization activities.
Section 53.1437 Exemptions, departures, and variances.
This proposed rule would add § 53.1437, which would govern the conditions in which the Commission may grant an exemption for one or more of its regulations, or an exemption, variance, or departure from a permit, design approval, or license.
Section 53.1440 Issuance of combined licenses.
This proposed rule would add § 53.1440, which would establish the conditions under which the Commission may issue COLs and accompanying conditions and limitations, including technical specifications, under Framework A.
Section 53.1443 Finality of combined licenses.
This proposed rule would add § 53.1443, which would govern permissible modifications or amendments that the Commission may make to a COL, as well as permissible changes that a licensee may make to facilities and procedures as described in the FSAR.
Section 53.1449 Inspection during construction.
This proposed rule would add § 53.1449, which would establish requirements related to inspections, tests, and analyses for the holder of a COL under Framework A.
90 Section 53.1452 Operation under a combined license.
This proposed rule would add § 53.1452, which would establish requirements describing the notifications, hearings, and findings to be made prior to commencing facility operations.
Section 53.1455 Duration of a combined license.
This proposed rule would add § 53.1455, which would govern the validity of a COL under Framework A.
Section 53.1456 Transfer of a combined license.
This proposed rule would add § 53.1456, which would permit the transfer of a COL under Framework A in accordance with § 53.1570.
Section 53.1458 Application for renewal.
This proposed rule would add § 53.1458, which would provide that an application for renewal of a COL must be filed in accordance with § 53.1595.
Section 53.1461 Continuation of combined license.
This proposed rule would add § 53.1461, which would govern the continuing obligations of the holder of a COL under Framework A following the permanent cessation of operations.
91 Section 53.1470 Standardization of commercial nuclear power plant designs:
licenses to construct and operate nuclear power reactors of identical design at multiple sites.
This proposed rule would add § 53.1470, which would govern the requirements and procedures for filing and issuing applications for a CP, operating license, or COL under Framework A in which the applicant seeks approval of the same design for multiple sites.
Section 53.1480 Limited combined license supporting testing of manufactured reactor modules.
[under development]
10 CFR part 53, subpart IMaintaining and Revising Licensing Basis Information This proposed rule would add subpart I, License Maintenance, which would address the maintenance of licensing basis information for Framework A.
Section 53.1500 Licensing basis information.
This proposed rule would add § 53.1500, describing the purpose of subpart I, which would be to provide the requirements for the maintenance of licensing basis information for commercial nuclear plants licensed under Framework A.
Section 53.1502 Specific terms and conditions of licenses.
This proposed rule would add § 53.1502, which would outline the specific terms and conditions for obtaining a license under Framework A. Specifically, licensees would
92 be subject to terms and conditions that are equivalent to §§ 50.54(h), 50.54(aa), and 50.54(dd).
Section 53.1505 Changes to licensing basis information requiring NRC approval.
This proposed rule would add § 53.1505, which would provide an overview of the process for licensees to request, and the Commission to issue, amendments to licensing basis information under Framework A.
Section 53.1510 Application for amendment of license.
This proposed rule would add § 53.1510, which would require licensees under Framework A of this part to file an application to request an amendment to the license.
Applicants must assess how their requested changes would impact the safety criteria and analysis requirements in subparts B and C, whether the amendment involves no significant hazards consideration using the standards in § 53.1520, and consider potential impacts on environmental factors.
Section 53.1515 Public notices; State consultation.
This proposed rule would add § 53.1515, which would outline the Commissions procedures for issuing a Federal Register notice and consulting with the State in which the commercial nuclear facility is located in connection with its consideration of applications for an amendment to an OL or COL under Framework A of this part. This section would be equivalent to § 50.91.
Section 53.1520 Issuance of amendment.
93 This proposed rule would add § 53.1520, which would outline criteria for the Commission to consider in issuing license amendments under Framework A. It would continue to use the criteria in § 50.92 to determine whether a proposed amendment involves no significant hazards consideration.
Section 53.1525 Revising information from a certified design.
This proposed rule would add § 53.1525, which would address the requirements for applicants to request, and the Commission to grant, an exemption to a design certification rule under Framework A.
Section 53.1530 Revising design information within a manufacturing license.
This proposed rule would add § 53.1530, which would require manufacturing licensees to request an amendment under §§ 53.1510 and 53.1520 to make changes to the design of a manufactured reactor or manufactured reactor module. It would also outline the requirements for holders of a COL under Framework A to request amendments for changes to the design information of a manufactured reactor.
Section 53.1535 Amendments during construction.
This proposed rule would add § 53.1535, which would outline the process for licensees under Framework A to request amendments to CPs or limited work authorizations during construction.
94 Section 53.1540 Updating licensing basis information and determining the need for NRC approval.
This proposed rule would add § 53.1540, which would provide an overview of the regulations in subpart I for holders of an OL or COL under Framework A to modify licensing basis information, circumstances in which NRC approval would be required, and definitions relevant to §§ 53.1545 through 53.1565.
Section 53.1545 Updating Final Safety Analysis Reports.
This proposed rule would add § 53.1545, which would require licensees under Framework A to regularly update Final Safety Analysis Reports (FSARs) in accordance with the requirements of this section to reflect changes to licensing basis information.
Section 53.1550 Evaluating changes to facility as described in Final Safety Analysis Reports.
This proposed rule would add § 53.1550, which would require licensees under Framework A to follow the guidelines outlined in this section in determining whether the changes to licensing basis information described in the updated Final Safety Analysis Report require them to obtain a license amendment.
Section 53.1560 Updating program documents included in licensing basis information.
This proposed rule would add § 53.1560, which would require the holders of an OL or COL under Framework A to regularly update the program documents that they submitted in their application for a license in accordance with the requirements of this section.
95 Section 53.1565 Evaluating changes to programs included in licensing basis information.
This proposed rule would add § 53.1565, which would enable licensees under Framework A to make changes to the facility, procedures, or organization, or address changes to site environs as described in program documents without NRC approval if these changes satisfy the generic criteria outlined in this section.
Section 53.1570 Transfer of licenses.
This proposed rule would add § 53.1570, which would outline the requirements for an application for transfer of a license issued under Framework A of this part. These requirements are equivalent to § 50.80.
Section 53.1575 Termination of license.
This proposed rule would add § 53.1575, which would outline the process for terminating an OL or COL issued under Framework A. These requirements are equivalent to those in § 50.82.
Section 53.1580 Information requests.
This proposed rule would add § 53.1580, which would parallel the requirements of § 50.54(f) regarding the process and circumstances under which the NRC may send information requests to the various types of licensees within Framework A.
96 Section 53.1585 Revocation, suspension, modification of licenses and approvals for cause.
This proposed rule would add § 53.1585, which would provide equivalent requirements to § 50.100 regarding grounds for the revocation, suspension, or modification of a license or standard design approval issued under Framework A.
Section 53.1590 Backfitting.
This proposed rule would add § 53.1590, which would define backfitting and introduce requirements for licensees under Framework A to undertake backfitting analyses and, when necessary, to backfit a facility to bring it into compliance with a license or the rules or orders of the Commission.
Section 53.1595 Renewal.
This proposed rule would add § 53.1595, which would provide for the renewal of a license under Framework A upon expiration.
10 CFR part 53, subpart JReporting and Other Administrative Requirements This proposed rule would add subpart J, Reporting and Other Administrative Requirements, to establish various reporting and other administrative requirements for licensees under Framework A of this part.
Section 53.1600 General information.
This proposed rule would add § 53.1600, which would require applicants and licensees under Framework A to provide NRC inspectors with unfettered access to sites
97 and facilities, maintain records and make reports, demonstrate compliance with financial qualification and reporting requirements, and maintain required financial protection for accidents.
Section 53.1610 Unfettered access for inspections.
This proposed rule would add § 53.1610 which would require applicants and licensees under part 53 to provide unfettered access to NRC inspectors, including access to records, premises, activities, and licensed materials, in addition to office space to accommodate temporary or resident inspectors.
Section 53.1620 Maintenance of records, making of reports.
This proposed rule would add § 53.1620 which would require part 53 licensees to retain all records and make reports as required by the conditions of the license or by the regulations in Framework A.
Section 53.1630 Immediate notification requirements for operating commercial nuclear plants.
This proposed rule would add § 53.1630 which would impose immediate notification requirements on part 53 licensees following the declaration of an emergency class or the discovery of certain non-emergency events.
Section 53.1640 Licensee event report system.
This proposed rule would add § 53.1640 which would require any commercial plant licensee holding an operating license under Framework A of this part to submit a Licensee Event Report in accordance with the specifications outlined in this section.
98 Section 53.1645 Effluent reports.
The proposed rule would add § 53.1645 which would require periodic (generally annual) reports to the Commission of the quantity of radionuclides released to unrestricted areas in liquid and gaseous effluents.
Section 53.1650 Facility information and verification.
The proposed rule would add § 53.1650 which would include a reporting requirement for applicants and holders of a CP or license under part 53 to support safeguards agreements between the United States and the International Atomic Energy Agency.
Section 53.1660 Financial requirements.
This proposed rule would add § 53.1660 which would introduce requirements and procedures related to financial qualifications and reporting requirements.
Section 53.1670 Financial qualifications.
This proposed rule would add § 53.1670 which would require an applicant for a CP, operating license, or COL under this part to must demonstrate possession or ability to obtain funds necessary for the activities for which the permit or license is sought.
Section 53.1680 Annual financial reports.
This proposed rule would add § 53.1680 which would require licensees and holders of a CP under part 53 to submit annual financial reports to the Commission, with
99 exceptions for those that submit financial forms to the Securities and Exchange Commission or the Federal Energy Regulatory Commission.
Section 53.1690 Licensees change of status; financial qualifications.
This proposed rule would add § 53.1690 which would require electric utility licensees that hold an operating or COL for a commercial nuclear plant under part 53 to provide the Nuclear Regulatory Commission with the financial qualifications information outlined in this section within seventy-five days of ceasing to be an electric utility.
Section 53.1700 Creditor regulations.
This proposed rule would add § 53.1700 which would establish regulations with respect to the creditors of any facility under Framework A of this part.
Section 53.1710 Financial protection.
This proposed rule would add § 53.1710 which would establish requirements for licenses under part 53 to obtain and maintain insurance to cover the costs of an accident.
Section 53.1720 Insurance Required to Stabilize and Decontaminate Plant Following an Accident.
This proposed rule would add § 53.1720 which would require commercial nuclear plant licensees under Framework A of this part to obtain insurance sufficient to cover the costs of stabilizing and decontaminating the plant in the event of an accident.
100 Section 53.1730 Financial protection requirements.
This proposed rule would add § 53.1730 which would require commercial nuclear plant licensees under part 53 to satisfy the provisions of 10 CFR part 53, subpart KQuality Assurance Criteria This proposed rule would add subpart K, Quality Assurance Criteria, that would establish quality assurance requirements for applicants for or holders of an OL or COL under part 53 applicable to the design, manufacture, construction, and operation of safety-related SSCs.
Section 53.1800 General provisions.
This proposed rule would add § 53.1800 that would define the applicability of subpart K of part 53.
Section 53.1805 Organization.
This proposed rule would add § 53.1805 that would establish requirements for establishing and executing a quality assurance program.
Section 53.1810 Quality assurance program.
This proposed rule would add § 53.1810 that would detail requirements for an applicants quality assurance programs, including requirements for documentation, scope, review, indoctrination and training, and management of the program.
101 Section 53.1815 Design control.
This proposed rule would add § 53.1815 that would detail required design control measures for applicants.
Section 53.1820 Procurement document control.
This proposed rule would add § 53.1820 that would establish requirements for procurement document control related to quality assurance.
Section 53.1825 Instructions, procedures, and drawings.
This proposed rule would add § 53.1825 that would establish requirements for documenting activities affecting quality.
Section 53.1830 Document control.
This proposed rule would add § 53.1830 that would require that applicants establish measures to control the issuance of documents that govern activities affecting quality.
Section 53.1835 Control of purchased material, equipment, and services.
This proposed rule would add § 53.1835 that would establish requirements for ensuring that purchased material, equipment, and services conform to procurement documents.
102 Section 53.1840 Identification and control of materials, parts, and components.
This proposed rule would add § 53.1840 that would establish requirements for measures to identify and control materials, parts, and components including partially fabricated assemblies.
Section 53.1845 Control of special processes.
This proposed rule would add § 53.1845 that would establish requirements for special processes, such as welding, heat treating, and nondestructive testing.
Section 53.1850 Inspection.
This proposed rule would add § 53.1850 that would establish requirements for inspection of activities affecting quality.
Section 53.1855 Test control.
This proposed rule would add § 53.1855 that would establish requirements for a test program for demonstrating SSCs will perform satisfactorily in service.
Section 53.1860 Control of measuring and test equipment.
This proposed rule would add § 53.1860 that would require that measures are established to ensure that measuring or testing devices are properly controlled, calibrated, and adjusted to maintain accuracy within necessary limits.
Section 53.1865 Handling, storage, and shipping.
This proposed rule would add § 53.1865 that would establish requirements for handling, storage, shipping, and cleaning and preservation of materials and equipment.
103 Section 53.1870 Inspections, test, and operating status.
This proposed rule would add § 53.1870 that would establish requirements for indicating inspection and test status of individual items and for including operating status of SSCs of a commercial nuclear power plant or manufactured reactor module.
Section 53.1875 Nonconforming materials, parts, or components.
This proposed rule would add § 53.1875 that would establish requirements for measures to control materials, parts, or components which do not conform to requirements.
Section 53.1880 Corrective action.
This proposed rule would add § 53.1880 that would establish requirements for corrective action of conditions adverse to quality.
Section 53.1885 Quality assurance records.
This proposed rule would add § 53.1885 that would establish requirements for records of activities affecting quality.
Section 53.1890 Audits.
This proposed rule would add § 53.1890 that would establish requirements for auditing of the quality assurance program.
104 10 CFR part 53, subpart NSiting Section 53.3505 Scope.
This proposed rule would add § 53.3505, which would apply the siting requirements of this subpart to applicants seeking a permit or license under Framework B of this part.
Section 53.3510 Definitions.
This proposed rule would add § 53.3510, which would define terms relevant to this subpart.
Section 53.3515 Factors to be considered when evaluating sites.
This proposed rule would add § 53.3515, which would require the Commission to consider certain factors, including population density, the nature and proximity of man-related hazards, and the physical characteristics of the site, when determining the suitability of a site for a commercial nuclear plant licensed under Framework B of this part.
Section 53.3520 Non-seismic siting criteria.
This proposed rule would add § 53.3520, which would require applicants to demonstrate that the proposed site fulfills certain criteria to ensure that the commercial power reactor poses little threat to the public or the environment.
Section 53.3525 Geologic and seismic siting criteria.
105 This proposed rule would add § 53.3525, which would establish geologic and seismic siting criteria for the Commission to evaluate in considering whether the proposed site and the design bases minimize the risk to the health and safety of the public.
10 CFR part 53, subpart OConstruction and Manufacturing The proposed rule adds subpart O, Construction and Manufacturing Requirements, which would establish requirements for the construction of an advanced nuclear plant under Framework B of the proposed rule.
Section 53.4100 Construction and manufacturing - scope and purpose.
The proposed rule would add § 53.4100, which would apply to construction and manufacturing activities authorized by a CP, COL, Manufacturing License (ML), or Limited Work Authorization (LWA) issued under Framework B of this part.
Section 53.4105 Reporting of defects and noncompliance.
The proposed rule would add § 53.4105, which would stipulate that each CP, ML, and COL is subject to procedures, notification requirements, records retention required under this section with respect to reporting of defects and noncompliance.
Section 53.4110 Construction.
The proposed rule would add § 53.4110 to address the management and control of the construction of a commercial nuclear plant, including specific requirements for manufacturing activities, control of radioactive materials, fuel loading, and transportation, acceptance, and installation of a manufactured reactor.
106 Section 53.4120 Manufacturing.
This proposed rule would add § 53.4120, which would ensure compliance with the requirements of a manufacturing license issued under Framework B of this part through the development of plans, programs, and organizational units to manage and control manufacturing activities.
10 CFR part 53, subpart POperations This proposed rule would add subpart P, Operations, which would require licensees under Framework B to develop and implement certain programs to maintain the safety and reliability of commercial nuclear plant functions.
Section 53.4200 Operational objectives.
This proposed rule would add § 53.4200, which would require each holder of an operating license or COL under Framework B of this part to ensure that the proper controls are in place to ensure that structures, systems, and components, as well as plant personnel, have the capability to maintain plant safety during normal operations and design basis events.
Section 53.4210 Maintenance, repair, and inspection programs.
This proposed rule would add § 53.4210, which would establish performance monitoring and maintenance requirements to ensure that structures, systems, and components operate as intended, in accordance with licensee-established performance goals that account for safety and industry-wide operating experience.
107 Section 53.4213 Technical specifications.
This proposed rule would add § 53.4213, which would establish technical specifications including, but not limited to: (1) safety limits, limiting safety system settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, (5) administrative controls, (6) decommissioning, (7) initial notification, and (8) written reports.
Section 53.4215 Response to seismic events.
This proposed rule would add § 53.4215, which would require a licensee to shut down the commercial nuclear plant if a vibratory ground motion exceeds the Operating Basis Earthquake Ground Motion until the licensee can demonstrate that no functional damage has occurred.
Section 53.4220 General staffing, training, personnel qualifications, and human factors requirements.
This proposed rule would add § 53.4220, which would apply the rules of
§§ 53.725 through 53.830 to Framework B of this part.
Section 53.4300 Programs.
This proposed rule would add § 53.4300, which would require licensees to implement the programs described in the following sections of this subpart to maintain plant safety during normal operations and design basis events.
108 Section 53.4310 Radiation protection.
This proposed rule would add § 53.4310, which would require licensees under Framework B to implement a Radiation Protection Program to control radioactive effluents and keep public exposure as low as is reasonably achievable.
Section 53.4320 Emergency preparedness.
This proposed rule would add § 53.4320, which would apply the rules in § 53.855 to Framework B.
Section 53.4330 Security programs.
This proposed rule would add § 53.4330, which would require licensees under Framework B to implement programs for physical protection, fitness for duty, AA, cybersecurity, and information security that demonstrates compliance with the requirements of this section.
Section 53.4340 Quality assurance.
This proposed rule would add § 53.4340, which would require licensees under Framework B to develop, implement, and maintain a quality assurance program (QAP),
including a written QAP manual, in accordance with subpart U.
Section 53.4350 Fire protection.
This proposed rule would add § 53.4350, which would require licensees under Framework B to develop and implement a fire protection program that demonstrate compliance with the requirements of this section.
109 Section 53.4360 Inservice inspection and inservice testing.
This proposed rule would add § 53.4360, which would require licensees to demonstrate compliance with the inservice inspection and inservice testing specifications under § 50.55a for boiling or pressurized water-cooled commercial nuclear plants and § 53.880 for non-light-water-cooled commercial nuclear plants.
Section 53.4380 Environmental qualification of electric equipment important to safety for nuclear power plants.
This proposed rule would add § 53.4380, which would require licensees under Framework B to maintain a list of electric equipment important to safety and ensure that it demonstrate compliance with the safety requirements of this section.
Section 53.4390 Procedures and guidelines.
This proposed rule would add § 53.4390, which would require licensees under Framework B to develop, implement, and maintain a set of procedures, guidelines, and supporting activities to support normal operations and response to unplanned events.
Section 53.4400 Integrity assessment program.
This proposed rule would add § 53.4400, which would require licensees under Framework B to establish an integrity assessment program to ensure that certain structures, systems, and components continue to operate as intended.
110 Section 53.4410 Primary containment leakage rate testing program.
This proposed rule would add § 53.4410, which would apply the requirements of appendix J to CFR part 50 to primary reactor containments for water-cooled commercial nuclear plants.
Section 53.4420 Mitigation of beyond-design-basis events.
This proposed rule would add § 53.4420, which would require certain licensees under Framework B to develop, implement, and maintain mitigation strategies for beyond-design basis external events and extensive damage mitigation guidelines in accordance with the requirements of this section.
10 CFR part 53, subpart QDecommissioning Requirements This proposed rule would add subpart Q, Decommissioning Requirements, to establish decommissioning requirements for applicants for or holders of an Operating License (OL) or Combined Operating License (COL) under Framework B of 10CFRpart53.
Section 53.4600 Scope and purpose.
This proposed rule would add § 53.4600 that would establish the scope of the decommissioning requirements for applicants and licensees under Framework B of part 53 and describe the contents of subpart Q of part 53.
Section 53.4610 Financial assurance for decommissioning.
This proposed rule would add § 53.4610 that would establish the need for financial assurance for decommissioning and require that applicants for an OL or COL
111 under Framework B of 10CFRpart53 prepare a plan and an associated decommissioning report that ensures and documents that adequate funding for decommissioning will be available.
Section 53.4620 Cost estimates for decommissioning.
This proposed rule would add § 53.4620 that would require site-specific cost estimates for decommissioning and establish the aspects that must be included in the estimate.
Section 53.4630 Annual adjustments to cost estimates for decommissioning.
This proposed rule would add § 53.4630 that would require that holders of an OL or COL under Framework B of part 53 annually adjust their cost estimate for decommissioning to account for escalation in labor, energy, and waste burial costs. This section would allow licensees to elect either a site-specific adjustment factor or a generic adjustment factor.
Section 53.4640 Methods for providing financial assurance for decommissioning.
This proposed rule would add § 53.1040 that would establish suitable methods that holders of an OL or COL under Framework B of part 53 may use to provide financial assurance for decommissioning to the NRC.
Section 53.4645 Limitations on the use of decommissioning trust funds.
This proposed rule would add § 53.4645 that would establish requirements for decommissioning trust funds under Framework B of this part, including criteria for using decommissioning trust funds and required terms.
112 Section 53.4650 NRC oversight.
This proposed rule would add § 53.4650 that would outline the steps the NRC may take to ensure adequate accumulation of decommissioning funds.
Section 53.4660 Reporting and recordkeeping requirements.
This proposed rule would add § 53.4660 that would contain reporting and recordkeeping requirements related to decommissioning for each holder of an OL or COL under Framework B of 10CFRpart53. This section would outline requirements for documents such as: certification of decommissioning funding, decommissioning cost estimates and copies of financial instruments, licensee records of information important to safe and effective decommissioning, PSDARs, financial assurance reports, and reports on the status of funding for managing irradiated fuel.
Section 53.4670 Termination of license.
This proposed rule would add § 53.1070 that would establish procedures for decommissioning and license termination applicable to licensees under Framework B of this part that have determined to permanently cease operations.
Section 53.4675 Program requirements during decommissioning.
This proposed rule would add § 53.4675, which would require licensees under Framework B of this part to establish and maintain a decommissioning fire protection program to prevent, detect, and control fires, and ensure that the risk of fire induced radiological hazards are minimized through the various stages of facility decommissioning.
113 Section 53.4680 Release of part of a commercial nuclear plant or site for unrestricted use.
This proposed rule would add § 53.1080 that would establish licensee procedures for requesting and NRC procedures for approving partial release of a commercial nuclear plant or site for unrestricted use prior to receiving approval of a license termination plan from the Commission under Framework B of this part.
10 CFR part 53, subpart RLicenses, Certifications, and Approvals Section 53.4700 Filling of application for licenses, certifications, or approvals; oath or affirmation.
This proposed rule would add § 53.4700, which would establish requirements for applicants seeking a standard design approval, standard design certification, license, or permit under Framework B to submit and amend an application.
Section 53.4701 Requirement for license.
This proposed rule would add § 53.4701, which would prohibit any use of a utilization facility except as authorized by a license issued by the Nuclear Regulatory Commission.
Section 53.4703 Combining applications and licenses.
This proposed rule would add § 53.4703, which would permit applicants seeking multiple licenses under Framework B to submit a single application, and the Commission to issue a single license for activities that would otherwise be licensed separately.
114 Section 53.4706 Elimination of repetition.
This proposed rule would add § 53.4706, which would allow applicants under Framework B to reference information contained in previous documents filed with the Commission so long as those references are clear and specific.
Section 53.4709 Contents of applications; general information.
This proposed rule would add § 53.4709, which would establish the general content to be included in applications made under Framework B of this part, including but not limited to the identifying information of the applicant and the radiological emergency response plans of government entities within the plume exposure pathway emergency planning zone.
Section 53.4712 Environmental conditions.
This proposed rule would add § 53.4712, which would allow the Commission to attach conditions to CPs, ESPs, and licenses issued under Framework B to address environmental issues during construction, operation, or decommissioning. These conditions may be derived from the information contained in the environmental report submitted as part of the application for a permit or license.
Section 53.4715 Agreement limiting access to classified information.
This proposed rule would add § 53.4715, which would require applicants to agree in writing, prior to receiving a license or standard design approval under Framework B, to restrict individuals with access to plant facilities from possessing Restricted Data or classified National Security Information until they have received the appropriate AA.
115 Section 53.4718 Ineligibility of certain applicants.
This proposed rule would add § 53.4718, which would prevent citizens, nationals, or agents of a foreign country, or corporations owned, controlled, or dominated by a foreign entity from applying for or obtaining a license under Framework B.
Section 53.4720 Exceptions and exemptions from licensing requirements.
This proposed rule would add § 53.4720, which would establish the activities that are exempt from licensing requirements.
Section 53.4721 Public inspection of applications.
This proposed rule would add § 53.4721, which would allow applicant submissions to be made publicly available in accordance with part 2.
Section 53.4724 Relationship between sections.
This proposed rule would add § 53.4724, which would outline the relationship between limited work authorizations, ESPs, standard design approvals, standard design certifications, manufacturing licenses, CPs, operating licenses, and COLs under Framework B.
Section 53.4730 General technical requirements.
This proposed rule would add § 53.4730, which would outline the general technical information to be included in the Safety Analysis Report in an application for a CP, operating license, ESP, COL, standard design approval, standard design certification, or manufacturing license under Framework B.
116 Section 53.4731 Risk-informed classification of structures, systems, and components.
This proposed rule would add § 53.4731, which would define four levels of Risk-Informed Safety Class (RISC) SSCs, and describe alternative requirements for the SSCs of a commercial nuclear plant.
Section 53.4733 Seismic design alternatives.
This proposed rule would add § 53.4733, which would define relevant terms and outline an alternative set of seismic design requirements that can be met in place of the requirements in appendix S to part 50.
Section 53.4740 Limited work authorizations.
This proposed rule would add § 53.4740, which would establish requirements for requesting a limited work authorization and grounds for the Commission to issue a limited work authorization. It would also contain details about the effect of a limited work authorization and the implementation of a redress plan.
Section 53.4750 Early site permits.
This proposed rule would add § 53.4750, which would provide an overview of the requirements regarding applications for and the issuance of ESPs under Framework B.
Section 53.4753 Filing of applications.
This proposed rule would add § 53.4753, which would enable an applicant under Framework B to apply for an ESP, regardless of whether they have filed an application for a CP or COL for that site.
117 Section 53.4754 Contents of applications for early site permits; general information.
This proposed rule would add § 53.4754, which would require applications for ESPs to include the information required by § 53.4709(a) through (d) and (j).
Section 53.4756 Contents of applications for early site permits; technical information.
This proposed rule would add § 53.4756, which would require applicants for ESPs to submit technical information, including but not limited to a Site Safety Analysis Report and emergency plans.
Section 53.4759 Review of applications.
This proposed rule would add § 53.4759, which would establish standards for review of applications for ESPs under Framework B, including requirements for the Commission to prepare an environmental impact statement and assess the adequacy of protective actions in the event of a radiological emergency. It would also require the administrative review of applications and hearings to follow the procedural requirements of part 2.
Section 53.4765 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
This proposed rule would add § 53.4765, which would require the ACRS to review safety-related content in the application for an ESP under Framework B.
118 Section 53.4768 Issuance of early site permit.
This proposed rule would add § 53.4758, which would establish the conditions under which the Commission may issue an ESP under Framework B, as well as the information, terms, and conditions to be included in the permit.
Section 53.4771 Extent of activities permitted.
This proposed rule would add § 53.4771, which would require that a valid ESP only be used for the purpose of site redress, unless the site is referenced in an application for a CP or COL under Framework B.
Section 53.4774 Duration of permit.
This proposed rule would add § 53.4774, which would govern the conditions under which an ESP remains valid following the date of issuance.
Section 53.4777 Limited work authorization after issuance of early site permit.
This proposed rule would add § 53.4777, which would permit the holder of an ESP to request a limited work authorization under § 53.4756(c).
Section 53.4780 Transfer of early site permit.
This proposed rule would add § 53.4780, which would govern the transfer of an ESP in accordance with § 53.6070.
Section 53.4783 Application for renewal.
119 This proposed rule would add § 53.4783, which would establish the conditions and procedures for renewing an ESP under Framework B.
Section 53.4786 Criteria for renewal.
This proposed rule would add § 53.4786, which would establish the criteria that the Commission may use to grant a renewal of an ESP under Framework B.
Section 53.4789 Duration of renewal.
This proposed rule would add § 53.4789, which would govern the duration of a renewed ESP under Framework B.
Section 53.4792 Use of site for other purposes.
This proposed rule would add § 53.4792, which would govern acceptable uses of the site for purposes other than those described in the permit.
Section 53.4798 Finality of early site permit determinations.
This proposed rule would add § 53.4798, which would address the finality of ESP determinations under Framework B.
Section 53.4800 Standard design approvals.
This proposed rule would add § 53.4800, which would provide an overview of the procedures for filing an application for a standard design approval under Framework B, the process of review by NRC staff, and referral to the ACRS of standard designs.
Section 53.4803 Filing of applications.
120 This proposed rule would add § 53.4803, which would enable applicants to submit a final design for the entire facility, or major portions, to the NRC staff for review.
Section 53.4806 Contents of applications for standard design approvals; general information This proposed rule would add § 53.4806, which would require applications for a standard design approval under Framework B to contain the information required by
§ 53.4709(a) through (c) and (j).
Section 53.4809 Contents of applications for standard design approvals; technical information.
This proposed rule would add § 53.4809, which would require the inclusion of certain technical information, including a Final Safety Analysis Report, site parameters, and design information, when an applicant seeks review of a major portion of a standard design.
Section 53.4812 Review of applications.
This proposed rule would add § 53.4812, which would require applications for standard design approval to be reviewed for compliance with the standards in parts 20, 53, and 73.
Section 53.4815 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.4815, which would require the ACRS to report on any portions of the application for a standard design approval under Framework B concerning safety.
121 Section 53.4818 Staff approval of design.
This proposed rule would add § 53.4818, which would require the Nuclear Regulatory Commission to make a determination on the acceptability of the design, publish its decision in the Federal Register, and issue a report analyzing the design that is available at http://nrc.gov. Additionally, the rule would establish the conditions under which a design approval under Framework B remains valid.
Section 53.4821 Finality of standard design approvals; information requests.
This proposed rule would add § 53.4821, which would require NRC staff and the ACRS to rely upon an approved design in their review of any standard design certification or individual facility license application under Framework B that references the standard design approval. The proposed rule would also govern requirements for issuing information requests.
Section 53.4830 Standard design certifications.
This proposed rule would add § 53.4830, which would provide an overview of the requirements and procedures that govern the issuance of standard design certifications under Framework B.
Section 53.4833 Filing of applications.
This proposed rule would add § 53.4833, which would enable an application for design certification to be filed, regardless of whether an application for a CP, COL, or manufacturing license has been filed, provided it complies with the filing requirements in
§ 53.040 and §§ 2.811 through 2.819.
122 Section 53.4836 Contents of applications for standard design certifications; general information.
This proposed rule would add § 53.4836, which would require an application for a standard design certification under Framework B to contain all of the information required by § 53.4709(a) through (c) and (j).
Section 53.4839 Contents of applications for standard design certifications; technical information.
This proposed rule would add § 53.4839, which would require applicants for a standard design certification under Framework B to submit a Final Safety Analysis Report that includes technical design information at a level of detail sufficient to enable the Commission to make a safety determination.
Section 53.4841 Contents of applications for standard design certifications; other application content.
This proposed rule would add § 53.4841, which would require applications for standard design certifications under Framework B to include an environmental report, as well as a description of the proposed inspections, tests, analyses, and acceptance (ITAAC) criteria that would demonstrate the facilitys compliance applicable rules and regulations and actions taken to protect Safeguards Information against unauthorized disclosure.
Section 53.4842 Review of applications.
123 This proposed rule would add § 53.4842, which would require applications for standard design certifications to be reviewed for compliance with the standards in parts 2, 51, 53, and 73. It would also establish procedural requirements for reviewing applications and holding hearings in accordance with subpart H of part 2.
Section 53.4845 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.4845, which would require the ACRS to report on any portions of the application for a standard design approval under Framework B concerning safety.
Section 53.4848 Issuance of standard design certification.
This proposed rule would add § 53.4848, which would establish the conditions under which the Commission may issue a design certification rule that specifies the site parameters, design characteristics, and any additional terms and conditions of the design certification rule.
Section 53.4851 Duration of certification.
This proposed rule would add § 53.4851, which would set the conditions under which a standard design certification remains valid.
Section 53.4854 Application for renewal.
This proposed rule would add § 53.4854, which would establish the conditions and procedures for an application to renew a standard design certification under Framework B.
124 Section 53.4857 Criteria for renewal.
This proposed rule would add § 53.4857, which would enable the Commission to issue a rule granting the renewal of a standard design certification under Framework B, impose additional requirements, and grant amendment requests.
Section 53.4860 Duration of renewal.
This proposed rule would add § 53.4860, which would provide that a renewal of a standard design certification under Framework B is valid for not less than 10 years, nor more than 15 years.
Section 53.4863 Finality of standard design certifications.
This proposed rule would add § 53.4863, which would establish limited conditions under which the Commission may initiate a rulemaking to modify, rescind, or impose new requirements on a standard design certification rule under Framework B. It would also address requests for an exemption from elements of the certification information, and require that applicants for a CP, COL, or manufacturing license that references a design certification rule, make information available for audit.
Section 53.4870 Manufacturing licenses.
This proposed rule would add § 53.4870, which would provide an overview of the requirements and procedures for applying for and issuing a manufacturing license under Framework B of this part.
Section 53.4873 Filing of applications.
125 This proposed rule would add § 53.4873, which would establish the requirements to apply for a manufacturing license under Framework B.
Section 53.4876 Contents of applications for manufacturing licenses; general information.
This proposed rule would add § 53.4876, which would require applicants for a manufacturing license under Framework B to include the information contained in
§ 53.4709(a) through (e) and (j).
Section 53.4879 Contents of applications for manufacturing licenses; technical information.
This proposed rule would add § 53.4879, which would require an applicant for a manufacturing license under Framework B to include certain technical information in a Final Safety Analysis Report, including but not limited to information about the principal design criteria and design bases of the manufactured reactor or manufactured reactor module and a description of the SSCs of the reactor to be manufactured.
Section 53.4882 Contents of applications for manufacturing licenses; other application content.
This proposed rule would add § 53.4882, which would require applicants for a manufacturing license under Framework B to include in their application inspections, tests, analyses, and acceptance criteria (ITAAC), an environmental report, a description of actions taken to protect Safeguards Information against unauthorized disclosure, and a description of how design features fulfill design criteria.
126 Section 53.4885 Review of applications.
This proposed rule would add § 53.4885, which would require applications for manufacturing licenses under Framework B to be reviewed for compliance with applicable standards and establish procedural requirements for reviewing applicants and holding hearings in accordance with part 2.
Section 53.4886 Referral to the Advisory Committee on Reactor Safeguards).
This proposed rule would add § 53.4886, which would require the ACRS to report on any portions of the application for a manufacturing license under Framework B concerning safety.
Section 53.4887 Issuance of manufacturing license.
This proposed rule would add § 53.4887, which would establish the conditions under which the Commission may issue a manufacturing license under Framework B.
Section 53.4888 Finality of manufacturing licenses.
This proposed rule would add § 53.4888, which would address the limited circumstances in which the Commission may modify, rescind, or impose new requirements following the issuance of a manufacturing license under Framework B. It would also address requests for a departure from the specifications of the license.
Section 53.4891 Duration of manufacturing licenses.
This proposed rule would add § 53.4891, which would govern the expiration of a manufacturing license under Framework B.
127 Section 53.4893 Transfer of manufacturing licenses.
This proposed rule would add § 53.4893, which would provide that a manufacturing license under Framework B may be transferred in accordance with
§ 53.6070.
Section 53.4895 Renewal of manufacturing licenses.
This proposed rule would add § 53.4895, which would establish the procedures for applicants to apply for and the Commission to grant a renewal of a manufacturing license under Framework B.
Section 53.4900 Construction permits.
This proposed rule would add § 53.4900, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to grant a CP under Framework B.
Section 53.4906 Contents of applications for construction permits; general information.
This proposed rule would add § 53.4906, which would require applicants for a CP under Framework B to submit the general information required by § 53.4709, as well as financial information.
Section 53.4909 Contents of applications for construction permits; technical information.
This proposed rule would add § 53.4909, which would require applicants for a CP under Framework B to submit a Preliminary Safety Analysis Report (PSAR).
128 Section 53.4912 Contents of applications for construction permits; other application content.
This proposed rule would add § 53.4912, which would require applicants for a CP under Framework B to submit an environmental report and to provide additional details in the PSAR if the application references an ESP, standard design approval, or standard design certification.
Section 53.4915 Review of applications.
This proposed rule would add § 53.4915, which would require applications for CPs under Framework B to be reviewed for compliance with applicable standards and establish procedural requirements for reviewing applications and holding hearings in accordance with part 2.
Section 53.4918 Finality of referenced NRC approvals, permits, and certifications.
This proposed rule would add § 53.4918, which would address the finality of ESPs, standard design approvals, and standard design certifications referenced in the CP application.
Section 53.4924 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.4924, which would require the ACRS to report on any portions of the application for a CP under Framework B concerning safety based on applicable standards in parts 20, 51, 53, 70, and 140.
Section 53.4927 Authorization to conduct limited work authorization activities.
129 This proposed rule would add § 53.4927, which would govern authorization to conduct limited work authorization activities.
Section 53.4930 Exemptions, departures, and variances.
This proposed rule would add § 53.4930, which would govern requests for and the issuance of exemptions from the Commissions regulations, and exemptions, departures, and variances from NRC approvals, permits, and certifications.
Section 53.4933 Issuance of construction permits.
This proposed rule would add § 53.4933, which would establish the conditions under which the Commission may issue CPs and accompanying terms and conditions under Framework B.
Section 53.4936 Finality of construction permits.
This proposed rule would add § 53.4936, which would address the finality of CPs.
Section 53.4942 Duration of construction permit.
This proposed rule would add § 53.4942, which would establish requirements for the expiration of a CP.
Section 53.4945 Transfer of construction permits.
This proposed rule would add § 53.4945, which would govern the transfer of CPs under Framework B in accordance with § 53.6070.
130 Section 53.4948 Termination of construction permits.
This proposed rule would add § 53.4948, which would require the holder of a permit under Framework B to provide written certification to the Commission within 30 days of permanently ceasing construction.
Section 53.4960 Operating licenses.
This proposed rule would add § 53.4960, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to issue an operating license under Framework B.
Section 53.4966 Contents of applications for operating licenses; general information.
This proposed rule would add § 53.4966, which would require an application for an operating license under Framework B to include the information required by
§ 53.4709 as well as financial information.
Section 53.4969 Contents of applications for operating licenses; technical information.
This proposed rule would add § 53.4969, which would require an application for an operating license under Framework B to include certain technical information in a Final Safety Analysis report describing the facility, design bases, and limits on the facilitys operations, and providing a safety analysis of the SSCs and facility.
Section 53.4972 Contents of applications for operating licenses; other application content.
131 This proposed rule would add § 53.4972, which would require an application for an operating license under Framework B to include an environmental report. Applicants for an operating license under Framework B that do not demonstrate compliance with the criteria of § 53.4730(a)(34)(ii)(A) and (B) must submit a plan for achieving compliance with § 53.4420 to mitigate beyond-design-basis events.
Section 53.4975 Review of applications.
This proposed rule would add § 53.4975, which would establish the standards and procedures for reviewing applications and holding hearings on operating licenses under Framework B.
Section 53.4981 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.4981, which would require the ACRS to report on any portions of the application for a CP under Framework B concerning safety based on applicable standards in parts 20, 26, 51, 53, 73, and 140.
Section 53.4984 Exemptions, departures, and variances.
This proposed rule would add § 53.4984, which would govern requests for and the issuance of exemptions from the Commissions regulations, and exemptions, departures, and variances from NRC approvals, permits, and certifications.
Section 53.4987 Issuance of operating licenses.
This proposed rule would add § 53.4987, which would establish the conditions under which the Commission may issue operating licenses and accompanying conditions and limitations, including technical specifications, under Framework B.
132 Section 53.4990 Finality of operating licenses.
This proposed rule would add § 53.4990, which would prevent the Commission from modifying, adding, or deleting any terms or conditions of the operating license, except in accordance with § 53.6090.
Section 53.4996 Duration of operating license.
This proposed rule would add § 53.4996, which would provide that an operating license under Framework B may be valid for up to 40 years.
Section 53.4999 Transfer of an operating license.
This proposed rule would add § 53.4999, which would provide that an operating license under Framework B may be transferred in accordance with § 53.6070.
Section 53.5002 Application for renewal.
This proposed rule would add § 53.5002, which would provide that an application for a renewed operating license under Framework B must be filed in accordance with
§ 53.6095.
Section 53.5005 Continuation of an operating license.
This proposed rule would add § 53.5005, which would govern the continuing obligations of the holder of an operating license under Framework B following the permanent cessation of operations.
Section 53.5010 Combined licenses.
133 This proposed rule would add § 53.5010, which would provide an overview of the requirements and procedures for applicants to apply for and the Commission to issue a COL under Framework B.
Section 53.5013 Contents of applications for combined licenses; general information.
This proposed rule would add § 53.5013, which would require an application for an COL under Framework B to include the information required by § 53.4709 as well as financial information.
Section 53.5016 Contents of applications for combined licenses; technical information.
This proposed rule would add § 53.5016, which would require applicants for a COL under Framework B to submit a Final Safety Analysis Report describing the facility, design basis, limits on facility operation, and a safety analysis of the SSCs and facility.
Section 53.5019 Contents of applications for combined licenses; other application content.
This proposed rule would add § 53.5019, which would require applicants for a COL under Framework B to submit an environmental report and a description of the inspections, tests, analyses and acceptance criteria that the licensee must perform.
Section 53.5022 Review of applications.
This proposed rule would add § 53.5022, which would require applications for COLs under Framework B to be reviewed for compliance with applicable standards and
134 establish procedural requirements for reviewing applicants and holding hearings in accordance with part 2.
Section 53.5025 Finality of referenced NRC approvals.
This proposed rule would add § 53.5025 which would address the finality of ESPs, standard design certification rules, standard design approvals, or manufacturing licenses referenced in the application for a COL under Framework B.
Section 53.5031 Referral to the Advisory Committee on Reactor Safeguards.
This proposed rule would add § 53.5031, which would require the ACRS to report on any portions of the application for a COL under Framework B concerning safety based on applicable standards in parts 20, 51, 53, 73, and 140.
Section 53.5034 Authorization to conduct limited work authorization activities.
This proposed rule would add § 53.5034, which would address authorization to conduct limited work authorization activities.
Section 53.5037 Exemptions, departures, and variances.
This proposed rule would add § 53.5037, which would govern the conditions in which the Commission may grant an exemption for one or more of its regulations, or an exemption, variance, or departure from a permit, design approval, or license.
Section 53.5040 Issuance of combined licenses.
135 This proposed rule would add § 53.5040, which would establish the conditions under which the Commission may issue COLs and accompanying conditions and limitations, including technical specifications, under Framework B.
Section 53.5043 Finality of combined licenses.
This proposed rule would add § 53.5043, which would govern permissible modifications or amendments that the Commission may make to a COL, as well as permissible changes that a licensee may make to facilities and procedures as described in the FSAR.
Section 53.5049 Inspection during construction.
This proposed rule would add § 53.5049, which would establish requirements related to inspections, tests, and analyses for the holder of a COL under Framework B.
Section 53.5052 Operation under a combined license.
This proposed rule would add § 53.5052, which would establish requirements describing the notifications, hearings, and findings to be made prior to commencing facility operations.
Section 53.5055 Duration of a combined license.
This proposed rule would add § 53.5055, which would govern the validity of a COL under Framework B.
Section 53.5056 Transfer of a combined license.
136 This proposed rule would add § 53.5056, which would permit the transfer of a COL under Framework B in accordance with § 53.6070.
Section 53.5058 Application for renewal.
This proposed rule would add § 53.5058, which would provide that an application for renewal of a COL must be filed in accordance with § 53.6095.
Section 53.5061 Continuation of combined license.
This proposed rule would add § 53.5061, which would govern the continuing obligations of the holder of a COL under Framework B following the permanent cessation of operations.
Section 53.5070 Standardization of commercial nuclear power plant designs:
licenses to construct and operate nuclear power reactors of identical design at multiple sites.
This proposed rule would add § 53.5070, which would govern the requirements and procedures for filing and issuing applications for a CP, operating license, or COL under Framework B in which the applicant seeks approval of the same design for multiple sites.
10 CFR part 53, subpart SMaintaining and Revising Licensing Basis Information This proposed rule would add subpart S, License Maintenance, which would address the maintenance of licensing basis information for Framework B.
137 Section 53.6000 Licensing basis information.
This proposed rule would add § 53.6000, describing the purpose of subpart S, which would be to provide the requirements for the maintenance of licensing basis information for commercial nuclear plants licensed under Framework B.
Section 53.6002 Specific terms and conditions of licenses.
This proposed rule would add § 53.6002, which would outline the specific terms and conditions for obtaining a license under Framework B. Specifically, licensees would be subject to terms and conditions that are equivalent to §§ 50.54(h), 50.54(aa), and 50.54(dd).
Section 53.6005 Changes to licensing basis information requiring NRC approval.
This proposed rule would add § 53.6005, which would provide an overview of the process for licensees to request, and the Commission to issue, amendments to licensing basis information under Framework B.
Section 53.6010 Application for amendment of license.
This proposed rule would add § 53.6010, which would require licensees under Framework B of this part to file an application to request an amendment to the license.
Applicants must assess whether the requested amendment involves no significant hazards consideration using the standards in § 53.1520 and evaluate the potential impact on environmental factors.
138 Section 53.6015 Public notices; State consultation.
This proposed rule would add § 53.6015, which would outline the Commissions procedures for issuing a Federal Register notice and consulting with the State in which the commercial nuclear facility is located, in connection with the NRCs consideration of applications for an amendment to an OL or COL under Framework B of this part. This section would be equivalent to § 50.91.
Section 53.6020 Issuance of amendment.
This proposed rule would add § 53.6020, which would outline criteria for the Commission to consider when issuing license amendments under Framework B. It would continue to use the criteria in § 50.92 to determine whether a proposed amendment involves no significant hazards consideration.
Section 53.6025 Revising information from a certified design.
This proposed rule would add § 53.6025, which would address the requirements for applicants to request, and the Commission to grant, an exemption to a design certification rule under Framework B of this part.
Section 53.6030 Revising design information within a manufacturing license.
This proposed rule would add § 53.6030, which would require manufacturing licensees to request an amendment under §§ 53.6010 and 53.6020 to make changes to the design of a manufactured reactor or manufactured reactor module. It would also outline the requirements for holders of a COL under Framework B to request amendments for changes to the design information of a manufactured reactor.
139 Section 53.6035 Amendments during construction.
This proposed rule would add § 53.6035, which would outline the process for licensees under Framework B to request amendments to CPs or limited work authorizations during construction.
Section 53.6040 Updating licensing basis information and determining the need for NRC approval.
This proposed rule would add § 53.6040, which would provide an overview of the regulations in subpart S for holders of an OL or COL under Framework B to modify licensing basis information, the circumstances in which NRC approval would be required to implement modifications, and definitions relevant to §§ 53.6045 through 53.6065.
Section 53.6045 Updating Final Safety Analysis Reports.
This proposed rule would add § 53.6045, which would require licensees under Framework B to regularly update FSARs in accordance with the requirements of this section to reflect changes to licensing basis information. The proposed requirements in Framework B would be equivalent to the requirements of § 50.71.
Section 53.6050 Evaluating changes to facility as described in Final Safety Analysis Reports.
This proposed rule would add § 53.6050, which would require licensees under Framework B to follow the guidelines outlined in this section in determining whether the changes to licensing basis information described in the updated Final Safety Analysis Report require them to obtain a license amendment.
140 Section 53.6052 Maintenance of risk evaluations.
This proposed rule would add § 53.6052, which would require that certain applicants and licensees submit, update, and maintain a risk evaluation.
Section 53.6054 Control of aircraft impact assessments.
This proposed rule would add § 53.6054, which would require licensees under Framework B to evaluate plant changes to ensure the protections against aircraft impacts would be maintained.
Section 53.6060 Updating program documents included in licensing basis information.
This proposed rule would add § 53.6060, which would require the holders of an OL or COL under Framework B to regularly update the program documents that they submitted in their application for a license in accordance with the requirements of this section.
Section 53.6065 Evaluating changes to programs included in licensing basis information.
This proposed rule would add § 53.6065, which would enable licensees under Framework B to make changes to the facility, procedures, or organization, or address changes to site environs as described in program documents without NRC approval if these changes satisfy the generic criteria outlined in this section.
Section 53.6070 Transfer of licenses.
141 This proposed rule would add § 53.6070, which would outline the requirements for an application for transfer of a license issued under Framework B of this part. These requirements are equivalent to § 50.80.
Section 53.6075 Termination of license.
This proposed rule would add § 53.6075, which would outline the process for terminating an OL or COL issued under Framework B. These requirements are equivalent to those in § 50.82.
Section 53.6080 Information requests.
This proposed rule would add § 53.6080, which would parallel the requirements of § 50.54(f) regarding the process and circumstances under which the NRC may send information requests to the various types of licensees within Framework B.
Section 53.6085 Revocation, suspension, modification of licenses and approvals for cause.
This proposed rule would add § 53.6085, which would provide equivalent requirements to § 50.100 regarding grounds for the revocation, suspension, or modification of a license or standard design approval issued under Framework B.
Section 53.6090 Backfitting.
This proposed rule would add § 53.6090, which would define backfitting and introduce requirements for licensees under Framework B to undertake backfitting analyses and, when necessary, to backfit a facility to bring it into compliance with a license or the rules or orders of the Commission.
142 Section 53.6095 Renewal.
This proposed rule would add § 53.6095, which would provide for the renewal of a license under Framework B upon expiration.
10 CFR part 53, subpart TReporting and Other Administrative Requirements This proposed rule would add subpart T, Reporting and Other Administrative Requirements, to establish various reporting and other administrative requirements for licensees under Framework B of this part.
Section 53.6300 General Information.
This proposed rule would add § 53.6300, which would require applicants and licensees under Framework B to provide NRC inspectors with unfettered access to sites and facilities, maintain records and make reports, demonstrate compliance with financial qualification and reporting requirements, and maintain required financial protection for accidents.
Section 53.6310 Unfettered access for inspections.
This proposed rule would add § 53.6310 which would require applicants and licensees under part 53 to provide unfettered access to NRC inspectors, including access to records, premises, activities, and licensed materials, in addition to office space to accommodate temporary or resident inspectors.
143 Section 53.6320 Maintenance of records, making of reports.
This proposed rule would add § 53.6320 which would require part 53 licensees to retain all records and make reports as required by the conditions of the license or by the regulations in Framework B.
Section 53.6330 Immediate notification requirements for operating commercial nuclear plants.
This proposed rule would add § 53.6330 which would impose immediate notification requirements on part 53 licensees following the declaration of an emergency class or the discovery of certain non-emergency events.
Section 53.6340 Licensee event report system.
This proposed rule would add § 53.6340 which would require any commercial plant licensee holding an operating license under Framework B of this part to submit a Licensee Event Report in accordance with the specifications outlined in this section.
Section 53.6345 Effluent reports.
The proposed rule would add § 53.6345 which would require periodic (generally annual) reports to the Commission of the quantity of radionuclides released to unrestricted areas in liquid and gaseous effluents.
Section 53.6350 Facility information and verification.
The proposed rule would add § 53.6350 which would include a reporting requirement for applicants and holders of a CP or license under part 53 to support
144 safeguards agreements between the United States and the International Atomic Energy Agency.
Section 53.6360 Financial requirements.
This proposed rule would add § 53.6360 which would introduce requirements and procedures related to financial qualifications and reporting requirements.
Section 53.6370 Financial qualifications.
This proposed rule would add § 53.6370 which would require an applicant for a CP, operating license, or COL under this part to must demonstrate possession or ability to obtain funds necessary for the activities for which the permit or license is sought.
Section 53.6380 Annual financial reports.
This proposed rule would add § 53.6380 which would require licensees and holders of a CP under part 53 to submit annual financial reports to the Commission, with exceptions for those that submit financial forms to the Securities and Exchange Commission or the Federal Energy Regulatory Commission.
Section 53.6390 Licensees change of status; financial qualifications.
This proposed rule would add § 53.6390 which would require electric utility licensees that hold an operating or COL for a commercial nuclear plant under part 53 to provide the Nuclear Regulatory Commission with the financial qualifications information outlined in this section within seventy-five days of ceasing to be an electric utility.
145 Section 53.6400 Creditor regulations.
This proposed rule would add § 53.6400 which would establish regulations with respect to the creditors of any facility under Framework B of this part.
Section 53.6410 Financial protection.
This proposed rule would add § 53.6410 which would establish requirements for licenses under part 53 to obtain and maintain insurance to cover the costs of an accident.
Section 53.6420 Insurance required to stabilize and decontaminate plant following an accident.
This proposed rule would add § 53.6420 which would require commercial nuclear plant licensees under Framework B of this part to obtain insurance sufficient to cover the costs of stabilizing and decontaminating the plant in the event of an accident.
Section 53.6430 Financial protection requirements.
This proposed rule would add § 53.6430 which would require commercial nuclear plant licensees under part 53 to satisfy the provisions of part 140, Financial Protection Requirements and Indemnity Agreements, of this chapter.
10 CFR part 53, subpart UQuality Assurance Criteria This proposed rule would add subpart U, Quality Assurance Criteria, that would establish quality assurance requirements for applicants for or holders of an OL or COL under 10CFRpart53 applicable to the design, manufacture, construction, and operation of safety-related SSCs.
146 Section 53.6600 General provisions.
This proposed rule would add § 53.6600 that would define the applicability of subpartU of part 53.
Section 53.6610 Quality assurance program.
This proposed rule would add § 53.6610 that would detail requirements for an applicants quality assurance programs, including requirements for documentation, scope, review, indoctrination and training, and management of the program.
Section 53.6605 Organization.
This proposed rule would add § 53.6605 that would establish requirements for establishing and executing a quality assurance program.
Section 53.6615 Design control.
This proposed rule would add § 53.6615 that would detail required design control measures for applicants.
Section 53.6620 Procurement document control.
This proposed rule would add § 53.6620 that would establish requirements for procurement document control related to quality assurance.
Section 53.6625 Instructions, procedures, and drawings.
This proposed rule would add § 53.6625 that would establish requirements for documenting activities affecting quality.
147 Section 53.6630 Document control.
This proposed rule would add § 53.6630 that would require that applicants establish measures to control the issuance of documents that govern activities affecting quality.
Section 53.6635 Control of purchased material, equipment, and services.
This proposed rule would add § 53.6635 that would establish requirements for ensuring that purchased material, equipment, and services conform to procurement documents.
Section 53.6640 Identification and control of materials, parts, and components.
This proposed rule would add § 53.6640 that would establish requirements for measures to identify and control materials, parts, and components including partially fabricated assemblies.
Section 53.6645 Control of special processes.
This proposed rule would add § 53.6645 that would establish requirements for special processes, such as welding, heat treating, and nondestructive testing.
Section 53.6650 Inspection.
This proposed rule would add § 53.6650 that would establish requirements for inspection of activities affecting quality.
148 Section 53.6655 Test control.
This proposed rule would add § 53.6655 that would establish requirements for a test program for demonstrating SSCs will perform satisfactorily in service.
Section 53.6660 Control of measuring and test equipment.
This proposed rule would add § 53.6600 that would require that measures are established to ensure that measuring or testing devices are properly controlled, calibrated, and adjusted to maintain accuracy within necessary limits.
Section 53.6665 Handling, storage, and shipping.
This proposed rule would add § 53.6665 that would establish requirements for handling, storage, shipping, and cleaning and preservation of materials and equipment.
Section 53.6670 Inspections, test, and operating status.
This proposed rule would add § 53.6670 that would establish requirements for indicating inspection and test status of individual items and for including operating status of SSCs of a commercial nuclear power plant or manufactured reactor module.
Section 53.6675 Nonconforming materials, parts, or components.
This proposed rule would add § 53.6675 that would establish requirements for measures to control materials, parts, or components which do not conform to requirements.
149 Section 53.6680 Corrective action.
This proposed rule would add § 53.6680 that would establish requirements for corrective action of conditions adverse to quality.
Section 53.6685 Quality assurance records.
This proposed rule would add § 53.6685 that would establish requirements for records of activities affecting quality.
Section 53.6690 Audits.
This proposed rule would add § 53.6690 that would establish requirements for auditing of the quality assurance program.
10 CFR part 70 - Domestic Licensing of Special Nuclear Material 10 CFR part 70, subpart C - General Licenses Section 70.20a General license to possess special nuclear material for transport.
This proposed rule would revise § 70.20a, paragraph (b) to include a reference to part 53.
10 CFR part 70, subpart D - License Applications Section 70.22 Contents of applications.
This proposed rule would revise § 70.22, paragraphs (b), (h)(1), (j)(1), and (k) to include the appropriate references to part 53.
150 10 CFR part 70, subpart E - Licenses Section 70.32 Conditions of licenses.
This proposed rule would update § 70.32, paragraphs (c)(1) and (d) to incorporate the appropriate references to part 53.
10 CFR part 70, subpart G - Special Nuclear Material Control Records, Reports, and Inspections Section 70.50 Reporting requirements.
This proposed rule would revise § 70.50, paragraph (d) to clarify the applicability of the reporting requirements of this section to part 53 licensees.
10 CFR part 72 - Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-level Radioactive Waste, and Reactor-Related Greater Than Class C Waste 10 CFR part 72, subpart A - General Provisions Section 72.3 Definitions.
This proposed rule would update the definition of independent spent fuel storage installation or ISFSI in § 72.3 to include a reference to facilities licensed under part 53.
10 CFR part 72, subpart B - License Application, Form, and Contents Section 72.30 Financial assurance and recordkeeping for decommissioning.
This proposed rule would revise § 72.30, paragraph (e)(5) to include the appropriate references to part 53.
151 Section 72.32 Emergency plan.
This proposed rule would revise § 72.32 to include a reference to the exclusion area as defined in part 53.
10 CFR part 72, subpart C - Issuance and Conditions Of License Section 72.40 Issuance of license.
This proposed rule would revise § 72.40, paragraph (c) regarding the issuance of a license under part 72 to include a reference to previous licensing actions, including the issuance of a CP under part 53.
10 CFR part 72, subpart D - Records, Reports, Inspections, and Enforcement Section 72.75 Reporting requirements for specific events and conditions.
This proposed rule would update § 72.75(i)(1)(ii) regarding reporting requirements for specific events and conditions with references to reactors licensed under part 53.
Section 72.184 Safeguards contingency plan.
This proposed rule would update § 72.184 regarding the requirements of a licensees safeguarding contingency plan with a reference to nuclear facilities licensed under part 53.
152 10 CFR part 72, subpart K - General License for Storage of Spent Fuel at Power Reactor Sites Section 72.210 General license issued.
This proposed rule would update § 72.210 to issue a general license for the storage of spent fuel in an independent spent storage installation at power to persons authorized to possess or operate nuclear power reactors under part 53.
Section 72.212 Conditions of general license issued under § 72.210.
This proposed rule would update § 72.212 regarding the conditions of a general license issued under § 72.210 to include a reference to license amendments for a facility made pursuant to part 53.
Section 72.218 Termination of licenses.
This proposed rule would revise § 72.218, paragraph (a) to include a reference to the notification required under part 53 regarding the plan for managing spent fuel prior to decommissioning. It would also extend the provisions of paragraph (b) to a reactor operating or COL under part 53.
10 CFR part 73 - Physical Protection of Plants and Materials Part 73 placeholder.
10 CFR part 74 - Material Control and Accounting of Special Nuclear Material
153 10 CFR part 74, subpart C - Special Nuclear Material of Low Strategic Significance Section 74.31 Nuclear material control and accounting for special nuclear material of low strategic significance.
This proposed rule would update § 74.31, paragraph (a) to include a reference to production or utilization facilities licensed under part 53, in addition to parts 50 and 70.
10 CFR part 74, subpart D - Special Nuclear Material of Moderate Strategic Significance Section 74.41 Nuclear material control and accounting for special nuclear material of moderate strategic significance.
This proposed rule would revise § 74.41, paragraph (a) to include a reference to nuclear reactors licensed under part 53.
10 CFR part 74, subpart E - Formula Quantities of Strategic Special Nuclear Material Section 74.51 Nuclear material control and accounting for strategic special nuclear material.
This proposed rule would revise § 74.51, paragraph (a) to include a reference to nuclear reactions licensed under part 53.
10 CFR part 75 - Safeguards on Nuclear Material - Implementation of Safeguards Agreements Between the United States and the International Atomic Energy Agency
154 Section 75.4 Definitions.
This proposed rule would update § 75.4 such that terms defined in § 53.020 have the same meaning when used in this part. The definition of facility would also be updated to include any plant or location where more than 1 effective kilogram of nuclear material is licensed pursuant to part 53.
10 CFR part 95 - Facility Security Clearance and Safeguarding of National Security Information and Restricted Data Section 95.5 Definitions.
This proposed rule would update the definition of license under § 95.5 to include those issued under part 53.
Section 95.39 External transmission of documents and material.
This proposed rule would update § 95.39, paragraph (a) to apply restrictions to the external transmission of documents and material containing classified information in connection with NRC licenses, certificates, standard design approvals, or standard design certifications issued under part 53.
10 CFR part 140 - Financial Protection Requirements and Indemnitiy Agreements 10 CFR part 140, subpart A - General Provisions Section 140.2 Scope.
This proposed rule would update § 140.2, paragraphs (a)(1) and (2) to include part 53 applicants and licensees within the scope of part 140 regulations.
155 10 CFR part 140, subpart B - Provisions Applicable Only to Applicants and Licenses Other Than Federal Agencies and Nonprofit Educational Institutions Section 140.10 Scope.
This proposed rule would update § 140.10 to apply the provisions of subpart B to applicants or holders of a license to operate a nuclear reactor under part 53, as well as applicants and holders of a COL under part 53.
Section 140.11 Amounts of financial protection for certain reactors.
This proposed rule would update § 140.11 to include a reference to persons authorized under part 53, in addition to parts 50, 52, and 54, to operate two or more nuclear reactors at the same location.
Section 140.12 Amount of financial protection required for other reactors.
This proposed rule would update § 140.12 to include a reference to persons authorized under part 53, in addition to parts 50, 52, and 54, to operate two or more nuclear reactors at the same location.
Section 140.13 Amount of financial protection required of certain holders of construction permits and combined licenses under 10 CFR part 52.
This proposed rule would update § 140.13 with the appropriate references to part 53 regarding the requirement for holders of a CP or COL under part 53 to obtain financial protection.
156 Section 140.20 Indemnity agreements and liens.
This proposed rule would update § 140.20, paragraphs (a)(1)(i) and (ii) with the appropriate references to part 53.
10 CFR part 150 - Persons Not Exempt Section 150.15 Persons not exempt.
The proposed rule would revise § 150.15, paragraphs (a)(7)(iii) and (a)(8) to add a reference to facilities licensed under part 53.
10 CFR part 170 - Fees for Facilities, Materials, Import and Export Licenses, and Other Regualtory Services Under the Atomic Energy Act of 1954, As Amended Section 170.3 Definitions.
The proposed rule would update § 170.3 to incorporate references to part 53 into the definitions of manufacturing license, Part 55 Reviews, power reactor, and special projects.
Section 170.12 Payment of fees.
The proposed rule would revise § 170.12, paragraph (d)(1)(v) regarding special project fees in connection with Final Safety Analysis Reports under part 53.
157 Section 170.21 Schedule of fees for production and utilization facilities, review of standard referenced design approvals, special projects, inspections, and import and export licenses.
The proposed rule would revise § 170.21, footnote 1 to include fees charged for approvals issued under the exemption provision in § 53.080.
Section 170.41 Failure by applicant or licensee to pay prescribed fees.
The proposed rule would revise § 170.41 to include a general reference to part 53 in connection with remedial actions that the Commission might take when an applicant or licensee fails to pay a prescribed fee required by this part.
10 CFR part 171 - Annual Fees for Reactor Licenses and Fuel Cycle Licenses and Materials Licenses, Including Holders of Certificates of Compliance, Registrations, and Quality Assurance Program Approvals and Government Agencies Licensed by the NRC Section 171.3 Scope.
The proposed rule would revise § 171.3 to apply the provisions of this part to any person holding an operating license for a power reactor licensed under part 53 or a COL issued under part 53.
Section 171.5 Definitions.
This proposed rule would update the definitions of operating license and power reactor in § 171.5 to incorporate the appropriate references to part 53.
158 Section 171.15 Annual fees: Non-power production or utilization licenses; reactor licenses and independent spent fuel storage licenses.
This proposed rule would update § 171.15, paragraphs (a), (b)(2)(iii), (c)(1), and (d)(1) regarding annual fees that are applicable to part 53 licensees.
Section 171.17 Proration.
This proposed rule would update § 171.17, paragraphs (a), (a)(1)(ii) and (a)(2) with references to part 53 licenses.
IX. Regulatory Flexibility Certification The Regulatory Flexibility Act of 1980 (RFA), as amended at 5 U.S.C. 601 et seq, requires that agencies consider the impact of their rulemakings on small entities and, consistent with applicable statutes, consider alternatives to minimize these impacts on the businesses, organizations, and government jurisdictions to which they apply.
In accordance with the Small Business Administrations regulation at 13 CFR 121.903(c), the NRC has developed its own size standards for performing an RFA analysis and has verified with the SBA Office of Advocacy that its size standards are appropriate for NRC analyses. The NRC size standards at § 2.810, NRC size standards, are used to determine whether an applicant or licensee qualifies as a small entity in the NRCs regulatory programs. Section 2.810 defines the following types of small entities:
Small business is a for-profit concern and is a(1) Concern that provides a service or a concern not engaged in manufacturing with average gross receipts of $8.0 million or less over its last 5 completed fiscal years; or (2) Manufacturing concern with an
159 average number of 500 or fewer employees based upon employment during each pay period for the preceding 12 calendar months.
Small organization is a not-for-profit organization which is independently owned and operated and has annual gross receipts of $8.0 million or less.
Small governmental jurisdiction is a government of a city, county, town, township, village, school district, or special district with a population of less than 50,000.
Small educational institution is one that is(1) Supported by a qualifying small governmental jurisdiction; or (2) Not state or publicly supported and has 500 or fewer employees.
Number of Small Entities Affected The NRC is currently not aware of any known small entities as defined in § 2.810 that are planning to apply for a commercial nuclear plant ESP, CP, operating license, manufacturing license, or COL under part 53 that would be impacted by this proposed rule. Based on this finding, the NRC has preliminarily determined that the proposed rule would not have a significant economic impact on a substantial number of small entities.
Economic Impact on Small Entities Depending on how the ownership and/or operating responsibilities for such an enterprise were structured, applicants for a commercial nuclear plant rated 8 MWe or less could conceivably demonstrate compliance with the definition of small entities as defined by § 2.810. Owners that operate power reactors rated greater than 8 MWe could generate sufficient electricity revenue that exceeds the gross annual receipts limit of $8 million, assuming a 90 percent capacity factor and the June 2021 U.S. Department of Energys Energy Information Administration U.S. average price of electricity to the ultimate customer for all sectors of 11.3 cents per kilowatt-hour.
160 Although the NRC is not aware of any small entities that would be affected by the proposed rule, there is a possibility that future applications for a commercial nuclear plant permit or license could be submitted by small entities who plan to own and operate a commercial nuclear plant rated 8 MWe or less. Commercial nuclear plants that are rated 8 MWe or less would most likely be used to support electrical demand for military bases or small remote towns, and would process heat, so would not directly compete with larger a commercial nuclear plant that would typically produce electricity for the grid.
As a result of these differing purposes, the NRC would expect that small and large entities would not be in direct competition with each other.
Therefore, the NRC preliminarily concludes that this proposed rule would not have a significant economic impact on a substantial number of small entities.
Request for Comments The NRC is seeking comments on both its initial RFA analysis and on its preliminary conclusion that this proposed rule would not have a significant economic impact on a substantial number of small entities because of the likelihood that most expected applicants would not qualify as a small entity. Additionally, the NRC is seeking comments on its preliminary conclusion that if a small entity were to submit a commercial nuclear plant application, the small entity would not incur a significant economic impact as it would most likely not be in competition with a large entity.
Any small entity that could be subject to this regulation that determines, because of its size, it is likely to bear a disproportionate adverse economic impact should notify the Commission of this opinion in a comment that indicates
- 1) The applicants size and how the proposed regulation would impose a significant economic burden on the applicant as compared to the economic burden on a larger applicant;
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- 2) How the proposed regulations could be modified to take into account the applicants differing needs or capabilities;
- 3) The benefits that would accrue or the detriments that would be avoided if the proposed regulations were modified as suggested by the applicant;
- 4) How the proposed regulation, as modified, would more closely equalize the impact of NRC regulations or create more equal access to the benefits of Federal programs as opposed to providing special advantages to any individual or group; and
- 5) How the proposed regulation, as modified, would still adequately demonstrate compliance with the NRCs obligations under the Atomic Energy Act of 1954, as amended.
X. Regulatory Analysis The NRC has prepared a draft regulatory analysis for this proposed rule. The analysis examines the costs and benefits of the alternatives considered by the NRC. The conclusion from the analysis is that this proposed rule and associated guidance would result in net averted costs to the industry and the NRC of $XXX,XXX using a 7-percent discount rate and $YYY,YYY using a 3-percent discount rate due to reductions in exemption requests. The NRC requests public comment on the draft regulatory analysis, which is available as indicated in the Availability of Documents section of this document. Comments on the draft regulatory analysis may be submitted to the NRC as indicated under the ADDRESSES caption of this document.
XI. Backfitting and Issue Finality This section describes the backfitting and issue finality implications of this proposed rule and the draft guidance documents described in section XVIII, Availability
162 of Guidance, in this document, as applied to pertinent NRC approvals and certain applicants that reference NRC approvals in their applications. The NRCs current backfitting provisions associated with nuclear power plants appear in § 50.109, Backfitting, and apply to CPs and operating licenses under part 50. Issue finality provisions (analogous to the backfitting provisions in § 50.109) for approvals under part 52 are located in various provisions of part 52. NRC Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests, describes the Commissions policies on backfitting and issue finality.
This proposed rule would provide a regulatory scheme for entities to apply for approvals under part 53. The part 50 backfitting provisions and part 52 issue finality provisions apply to actions taken by the NRC under part 50 or part 52, respectively, or actions taken by the NRC under other parts of 10 CFR chapter I that, for holders of certain approvals under part 50 or part 52, inextricably affect their activities regulated under part 50 or part 52. Issuance and implementation of this proposed rule would not constitute actions taken under part 50 or part 52. Also, proposed part 53 would not allow an applicant to reference approvals issued under part 50 or part 52. Thus, the issuance and implementation of proposed part 53 would not affect part 50 or part 52 entities activities. Therefore, the part 53 proposed rule would not be within the scope of the part 50 backfitting and part 52 issue finality provisions.
The NRC is issuing 7 DGs that, if issued as final regulatory guides, would provide guidance on the methods acceptable to the NRC for complying with aspects of this proposed rule. These DGs would not apply to holders of approvals issued under part 50 or part 52. Further, as discussed in the DGs, applicants and licensees would not be required to comply with the positions set forth in the DGs. Therefore, issuance of the
163 DGs as final regulatory guides would not constitute backfitting under part 50 or affect the issue finality of any approval issued under part 52.
XII. Cumulative Effects of Regulation The NRC is following its CER process by engaging with external stakeholders throughout this proposed rule and related regulatory activities. Public involvement has included numerous public meetings to examine the part 53 risk-informed, technology-inclusive requirements for commercial nuclear plants and the publication of numerous versions of preliminary proposed rule language. The NRC is considering holding additional public meetings during the remainder of the rulemaking process.
In parallel with this proposed rule, the NRC is issuing 10 draft implementing guidance documents for comment to support informed external stakeholder feedback.
section XVIII, Availability of Guidance, of this document describes how the public can access the draft implementing guidance.
In addition to the questions in the Specific Requests for Comments section of this document, the NRC is requesting CER feedback on the following questions:
- 1. In light of any current or projected CER challenges, does the proposed rules effective date provide sufficient time to implement the new proposed requirements, including changes to programs, procedures, and the facility?
- 2. If CER challenges currently exist or are expected, what should be done to address them? For example, if more time is required for implementation of the new requirements, what period of time is sufficient?
- 3. Do other (NRC or other agency) regulatory actions (e.g., orders, generic communications, license amendment requests, inspection findings of a generic nature) influence the implementation of the proposed rules requirements?
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- 4. Are there unintended consequences? Does the proposed rule create conditions that would be contrary to the proposed rules purpose and objectives? If so, what are the unintended consequences, and how should they be addressed?
Please comment on the NRCs cost and benefit estimates in the regulatory analysis that supports this proposed rule. The draft regulatory analysis is available as indicated under the Availability of Documents section of this document.
XIII. Plain Writing The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to write documents in a clear, concise, and well-organized manner. The NRC has written this document to be consistent with the Plain Writing Act as well as the Presidential Memorandum, Plain Language in Government Writing, published June 10, 1998 (63 FR 31885). The NRC requests comment on this document with respect to the clarity and effectiveness of the language used.
XIV. Environmental Assessment and Proposed Finding of No Significant Environmental Impact The Commission has determined under the National Environmental Policy Act of 1969, as amended, and the Commissions regulations in subpart A of part 51, that this rule, if adopted, would not be a major Federal action significantly affecting the quality of the human environment, and an environmental impact statement is not required. The implementation of the proposed rule requirements does not have a significant impact on the environment. The proposed rulemaking would either have requirements that are administrative in application, matters of procedure, or provide an equivalent level of
165 safety as existing requirements; therefore, there would be similar environmental impacts from the implementation of the part 53 regulations.
The determination of this environmental assessment is that there will be no significant effect on the quality of the human environment from this action. Public stakeholders should note, however, that comments on any aspect of this environmental assessment may be submitted to the NRC as indicated under the ADDRESSES caption.
The environmental assessment is available as indicated under the Availability of Documents section.
The NRC has sent a copy of the environmental assessment, and this proposed rule to every State Liaison Officer and has requested comments.
XV. Paperwork Reduction Act This proposed rule contains new or amended collections of information contained in parts 26, 53, and 73 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq). The collections of information have been submitted to the Office of Management and Budget for review and approval. Existing collections of information were approved by the Office of Management and Budget, approval number(s) 3150-0002 (part 73), 3150-0011 (part 50), and 3150-0151 (part 52).
Type of submission, new or revision: New The title of the information collection: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors.
The form number if applicable: Not Applicable.
166 How often the collection is required or requested: On occasion.
Who will be required or asked to respond: Future power reactor licensees or license applicants for commercial nuclear plants to be licensed under part 53.
An estimate of the number of annual responses: XXX.
The estimated number of annual respondents: XXX.
An estimate of the total number of hours needed annually to comply with the information collection requirement or request: XXXX.
Abstract: The proposed rule would result in changes in reporting, recordkeeping, and third-party disclosure requirements relative to existing rules by providing certain alternative, risk-informed, performance-based requirements for commercial nuclear plants. Part 53 applicants or licensees would also be required to maintain a record of the technical analysis related to eligibility until the certifications of cessation of operations required by §§ 53.1070(a) or 53.4670(a) have been docketed by the NRC.
The U.S. Nuclear Regulatory Commission is seeking public comment on the potential impact of the information collection(s) contained in this proposed rule and on the following issues:
- 1.
Is the proposed information collection necessary for the proper performance of the functions of the NRC, including whether the information will have practical utility?
167
- 2.
Is the estimate of the burden of the proposed information collection accurate?
- 3.
Is there a way to enhance the quality, utility, and clarity of the information to be collected?
- 4.
How can the burden of the proposed information collection on respondents be minimized, including the use of automated collection techniques or other forms of information technology?
A copy of the OMB clearance package and proposed rule is available in ADAMS under Accession No. MLXXXXXXXXX or may be viewed free of charge by contacting the NRCs Public Document Room reference staff at 1-800-397-4209, at 301-415-4737, or by email to PDR.resource@nrc.gov. You may obtain information and comment submissions related to the OMB clearance package by searching on http://www.regulations.gov under Docket ID NRC-2019-0062.
You may submit comments on any aspect of these proposed information collection(s), including suggestions for reducing the burden and on the above issues, by the following methods:
Federal rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2017-0227.
Mail comments to: FOIA, Library, and Information Collections Branch, Office of the Chief Information Officer, Mail Stop: T6-A10M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 or by e-mail to Infocollects.Resource@nrc.gov or to the OMB reviewer at: OMB Office of Information and Regulatory Affairs (3150--0011, -0151, -0002), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; email:
oira_submission@omb.eop.gov.
168 Submit comments by [INSERT DATE 30 DAYS AFTER PUBLICATION IN THE FEDERAL REGISTER]. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date.
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
XVI. Criminal Penalties For the purposes of Section 223 of the AEA, the NRC is issuing this proposed rule that would add §§ 53.725 through 53.830 under one or more of Sections 161b, 161i, or 161o of the AEA. Willful violations of the rule would be subject to criminal enforcement. Criminal penalties as they apply to regulations in part 53 are discussed in
§§ 53.755 and 53.4236.
XVII. Voluntary Consensus Standards The National Technology Transfer and Advancement Act of 1995, Pub. L. 104-113, requires that Federal agencies use technical standards that are developed or adopted by voluntary consensus standards bodies unless the use of such a standard is inconsistent with applicable law or otherwise impractical. In this proposed rule, the NRC would revise regulations by adding a risk-informed, technology-inclusive regulatory
169 framework for commercial advanced nuclear reactors. This action does not constitute the establishment of a standard that contains generally applicable requirements.
XVIII. Availability of Guidance As discussed in the section II, Background, the NRC staff developed part 53 building upon recent and ongoing activities such as those described in SECY-19-0117 to develop the proposed part 53. Because a number of activities are ongoing to support new reactor applications under the existing regulatory framework, the NRC staff identified in its response to SRM-SECY-20-0032 (ADAMS Accession No. ML20276A293) that the timing of guidance document development to support the part 53 rulemaking was a key risk and uncertainty to publishing the final part 53 rule. To mitigate this risk, the NRC staff engaged external stakeholders to ensure common prioritization of guidance documents that must be developed and to work diligently on those that are needed early to support the rulemaking, early applications, or broader efforts such as the Advanced Reactor Demonstration Program being sponsored by DOE. The NRC staff also recognizes that guidance development to support part 53 and advanced reactors will continue to be developed as the industry and NRC staff learn lessons from licensing reviews and operating experience. Therefore, the NRC staff categorized guidance supporting the part 53 rulemaking into various categories: (1) guidance issued to support applications under the existing regulatory framework, (2) guidance under development to support applications under the existing regulatory framework, (3) implementing guidance for part 53-specific proposed rule language, and (4) future guidance activities that would need to be completed after the part 53 proposed rule is published for public comment.
170 (1) Hundreds of guidance documents exist for the current fleet of operating reactors. While some of the guidance is specific to light-water reactor technologies, other guidance is technology inclusive in nature and should be considered, as appropriate, in the development of all licensing applications and NRC staff reviews. In addition, the NRC has undertaken efforts to incorporate or reference the most relevant guidance in its efforts to develop additional guidance for future advanced reactors. The following guidance has been issued by the NRC staff to support licensing reviews of advanced reactors under the existing regulatory framework that will continue to inform applicant development and NRC staff reviews under parts 50 and 52. Conforming changes would be needed to ensure they are applicable under part 53, and these revisions would occur between the proposed rule and the final rule. The NRC staff will issue revisions to these guidance documents for public comment after the publication of the proposed rule, and they will be finalized and issued with the final part 53 rule.
Regulatory Guide (RG) 1.233, Rev. 0, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors RG 1.232, Rev. 0, Guidance for Developing Principal Design Criteria for Non-Light Water Reactors NUREG-2246, Fuel Qualification for Advanced Reactors RG 1.87, Rev. 2, Acceptability of ASME Code,Section III, Division 5, High Temperature Reactors RG 1.246, Rev. 0, 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
171 (2) The NRC staff is developing additional guidance to support licensing reviews of advanced reactors under the existing regulatory framework. These guidance documents will be issued prior to the finalization of part 53 to support near-term applicants and NRC staff reviews. Conforming changes would be needed to ensure they are applicable under part 53, and these revisions would occur between the proposed rule and the final rule. The NRC staff is currently engaged with the DOE and industry to develop content of application guidance for advanced reactors, initially developed to support applications under the existing regulatory framework (parts 50 and 52). These guidance documents, the industry-led Technology-Inclusive Risk-Informed Content of Application Project (TICAP) guidance found in NEI 21-07 and the NRC staff-led Advanced Reactor Content of Application Project (ARCAP) interim staff guidance (ISG) documents will support developers in developing advanced reactor applications and facilitate the NRC staffs review of applications for CPs, operating licenses (OLs), COLs, manufacturing licenses (MLs), standard design approval (SDAs), and design certifications (DCs) under Framework A of this part. These guidance documents provide an overview of the information that should be included in an advanced reactor application, a review roadmap for NRC staff with the principal purpose of ensuring consistency, quality and uniformity of NRC staff reviews, and a well-defined base from which the NRC staff can evaluate proposed changes in the scope and requirements of reviews. While specific sections of the information are primarily aligned with the LMP methodology, as endorsed in RG-1.233, as one acceptable process for applicants to use when developing portions of an application, the concepts and general information may be used to inform the review of an application submitted using other traditional licensing approach methodologies (as applicable). Other sections of the information are generally
172 applicable and independent of the methodology used to develop an advanced reactor application. The ARCAP ISGs, in particular, provide references to numerous regulatory guidance documents that should be considered by both applicants and the NRC staff in developing and reviewing advanced reactor applications. The following documents will be issued for public comment after the publication of the proposed rule, and they will be finalized and issued with the final part 53 rule.
DG-1404, Guidance for a Technology Inclusive Content of Application Methodology to Inform the Licensing Basis And Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors DANU-ISG-2022-01, Advanced Reactor Content of Application Project, Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications - Roadmap DANU-ISG-2022-02, Advanced Reactor Content of Application Project Chapter 2, Site Information DANU-ISG-2022-03, Advanced Reactor Content of Application Project Chapter 9, Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste DANU-ISG-2022-04, Advanced Reactor Content of Application Project Chapter 10, Control of Occupational Dose DANU-ISG-2022-05, Advanced Reactor Content of Application Project Chapter 11, Organization and Human-System Considerations DANU-ISG-2022-06, Advanced Reactor Content of Application Project Chapter 12, Post-Construction Inspection, Testing, and Analysis Program DANU-ISG-2022-07, Advanced Reactor Content of Application Project, Risk-Informed Inservice Inspection/Inservice Testing
173 DANU-ISG-2022-08, Advanced Reactor Content of Application Project, Risk-Informed Technical Specifications DANU-ISG-2022-09, Advanced Reactor Content of Application Project, Risk-Informed, Performance-Based Fire Protection Program (for Operations)
DG-1350 (RG 1.242), Performance-Based Emergency Preparedness for Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities RG 1.247, Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activities RG 4.7, General Site Suitability Criteria for Nuclear Power Stations (3) The NRC is issuing for comment XX draft guidance documents for the implementation of the proposed requirements in this rulemaking. The guidance is available in ADAMS under the Accession Numbers listed below. Comments on this draft regulatory guidance may be submitted by the methods outlined in the ADDRESSES section of this document. Interested persons may obtain information and comment submissions related to the draft guidance by searching on http://www.regulations.gov under Docket ID NRC-2019-0062.
DG-1413, Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants (ML22158A127)
This DG describes an acceptable approach for identifying licensing events that can be used to inform the design basis, licensing basis, and content of applications for commercial nuclear plants, including light water reactors (LWRs) and non-light water reactors (non-LWRs). It applies to nuclear power reactor designers, applicants, and licensees of commercial nuclear plants applying for permits, licenses, certifications, and
174 approvals under parts 50, 52, and 53. In this DG, the term licensing events is used in a generic sense to refer to collections of designated event categories such as, but not limited to, anticipated operational occurrences (AOOs), DBAs, design-basis events (DBEs), and postulated accidents. Specifically, this DG provides an acceptable approach for (1) conducting a comprehensive and systematic search for initiating events, (2) using a systematic process to delineate a comprehensive set of event sequences, (3) grouping initiating events and event sequences into designated licensing event categories, and (4) providing assurance that the set of licensing events is complete.
DG-1414, Alternative Evaluation for Risk Insights (AERI) Methodology (ML22158A131)
This DG describes an acceptable approach for performing an AERI. Applicants for permits, licenses, certifications, and approvals under part 53 Framework B may elect to develop an AERI in lieu of a probabilistic risk assessment (PRA) when the AERI entry conditions in 10CFR53.4730(a)(34)(ii) are met. Specifically, this DG provides an acceptable approach to (1) identifying and characterizing a bounding event or events, (2) confirming that the commercial nuclear plant design demonstrate compliance with the AERI entry conditions specified in § 53.4730(a)(34)(ii) by determining a dose estimate for the bounding event or events, (3) developing a demonstrably conservative risk estimate for the bounding event to show that the Commissions safety goals and associated quantitative health objectives (QHOs) as stated in Safety Goals for the Operation of Nuclear Power Plants, (51 FR 28044; August 4, 1986 as corrected and republished at 51 FR 30028; August 21, 1986) are met, (4) searching for severe accident vulnerabilities for the entire set of licensing events, (5) identifying risk insights for the entire set of licensing events, (6) assessing defense in depth adequacy for the entire set of licensing events, (7) maintaining and upgrading the AERI, (8) considering
175 application-specific aspects such as developing an AERI to support a CP application when an applicant may have a conceptual design that does not include sufficient information to demonstrate that AERI entry conditions are met at the time of application, and (9) addressing procedural and other non-technical aspects such as independent review and the use of expert opinion.
[Placeholder for parts 26 and 73 DGs.]
The NRC is issuing for public comment the following draft interim staff guidance (ISG) documents for the implementation of the proposed requirements in this rulemaking:
DRO-ISG-2023-01, Operator Licensing Programs (ML22266A066)
This draft ISG provides guidance for the review of tailored operator licensing programs that are submitted for review consistent with the technical requirements of
§ 53.730(g). This guidance primarily addresses the review of operator licensing examination processes to facilitate the ability of reviewers to assess whether a proposed approach to the testing of licensed operators and trainees reflects sound assessment testing practices that are suitable for the screening of competent licensed operators.
Additionally, this ISG provides further review guidance in other areas such as licensed operator continuing training and proficiency programs.
DRO-ISG-2023-02, Interim Staff Guidance Augmenting NUREG-1791, Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m), for Licensing Commercial Nuclear Plants under 10 CFR Part 53 (ML22266A068)
This draft ISG provides guidance for the review of customized facility operator staffing plans that are submitted for review consistent with the technical requirements of
176
§ 53.730(f). This ISG is structured as a companion document to the existing NUREG-1791 and adapts the existing human factors engineering-based methodologies of that document for use in the evaluation of staffing plans submitted within the context of part 53 facilities. Additionally, this ISG provides further guidance to address other staffing-related considerations, such as provisions for engineering expertise.
DRO-ISG-2023-03, Development of Scalable Human Factors Engineering Review Plans (ML22266A072)
This draft ISG applies to the human factors engineering (HFE) review of applications for operating licenses, COLs, design certifications, and standard design approvals for commercial nuclear plants submitted under proposed part 53. The purpose of this ISG is to facilitate staff understanding of an acceptable method for developing a scalable (i.e., application-specific) plan for the review of these applications for compliance with applicable HFE requirements. The ISG describes a process and provides implementation guidance for NRC staff to tailor HFE review plans to each application to achieve an effective and efficient review.
(4) The NRC staff has identified future guidance activities that would need to be completed after the part 53 proposed rule is published for public comment to support advanced reactor applications and NRC staff reviews. For example, the NRC staff recognizes that a standardized content of application for applications under Framework B of this part would ensure review consistency and predictability from NRC staff.
Accordingly, the NRC staff has prioritized development of content of application guidance that would serve the same purpose as the TICAP and ARCAP efforts underway to support applications under Framework A of this part. The NRC staff has not yet initiated the development of these guidance documents, but will engage stakeholders
177 during the development of these documents to ensure common prioritization. In addition, the NRC works with standards development organizations (SDOs), advanced reactor developers, DOE, and other stakeholders to identify and facilitate new consensus codes and standards needed for advanced reactor development. The NRC will continue its membership and participation on standards development committees and working groups to support standards for advanced reactor technologies, where appropriate.
XIX. Public Meeting The NRC will conduct a public meeting on the proposed rule for the purpose of describing the proposed rule and implementation guidance to the public and answering questions from the public on the proposed rule and implementation guidance.
The NRC will publish a notice of the public meetings location, time, and agenda on the NRCs public meeting Web site at least 10 calendar days before the meeting.
Stakeholders should monitor the NRCs public meeting Web site for information about the public meeting at: http://www.nrc.gov/public-involve/public-meetings/index.cfm.
XX. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the following methods, as indicated.
DOCUMENT ADAMS ACCESSION NO. / WEB LINK / FEDERAL REGISTER CITATION Proposed Rule Documents SECY-23-XXXX, Proposed Rulemaking: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN 315-AK31), <INSERT DATE>
178 SECY-23-XXXX, Enclosure 2, Draft Environmental Assessment for the Proposed RuleRisk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors,
<INSERT DATE>
ML21162A104 SECY-23-XXXX, Enclosure 3, Draft Regulatory Analysis, <INSERT DATE>
ML21162A112 SECY-23-XXXX, Enclosure 4, Alternative Approaches Considered for Selected Topics During the Development of Part 53 ML22244A001 Draft Information Collection Analysis, <INSERT DATE>
ML21162A109 Draft Regulatory Guidance Documents Draft Regulatory Guide DG-1413, Technology-Inclusive Identification Of Licensing Events For Commercial Nuclear Plants, <INSERT DATE>
ML22257A173 Draft Regulatory Guide DG-1414, "Alternative Evaluation for Risk Insights (AERI) Framework,"
<INSERT DATE>
ML22257A248 Draft Interim Staff Guidance Documents Draft Interim Staff Guidance DRO-ISG-2023-01, Operator Licensing Programs, <INSERT DATE>
ML22266A066 Draft Interim Staff Guidance DRO-ISG-2023-02, Interim Staff Guidance Augmenting NUREG-1791, Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m), for Licensing Commercial Nuclear Plants under 10 CFR Part 53, <INSERT DATE>
ML22266A068 Draft Interim Staff Guidance DRO-ISG-2023-03, Development of Scalable Human Factors Engineering Review Plans, <INSERT DATE>
ML22266A072 Other References American National Standards Institute/ANS-3.4-2013, Medical Certification And Monitoring Of Personnel Requiring Operator Licenses For Nuclear Power Plants, https://webstore.ansi.org/Standards/ANS I/ansians2013 ASME/ (ANS) RA-S-1.4-2021, Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants https://www.asme.org/codes-standards/find-codes-standards/ra-s-1 probabilistic-risk-assessment-standard-advanced-non-light-water-reactor-nuclear-power-plants/2021/drm-enabled-pdf ASCE/Structural Engineering Institute (SEI) 43-19, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities https://doi.org/10.1061/9780784415405 Draft Regulatory Guide DG-5071, Target Set Identification and Development for Nuclear Power Plants, dated December 23, 2019 ML13152A355.
Federal Register noticeFinal policy statement, Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities; Final Policy Statement, dated August 16, 1995 60 FR 42622.
179 Federal Register notice - Final rule, Fitness-for-Duty Programs, dated June 7,1989 54 FR 24473.
Federal Register notice - Final rule, Fitness for Duty Programs, dated March 31, 2008 84 FR 16970.
Federal Register noticeFinal rule, Licenses, Certifications, and Approvals for Nuclear Power Plants, dated August 28, 2007 72 FR 49351.
Federal Register noticeFinal rule, Technical Specifications, dated July 19,1995 60 FR 36953, 36955.
Federal Register notice - Final rule, Loss of all alternating current power, dated June 21, 1988 52 FR 23203.
Federal Register noticePolicy Statement, Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants, dated August 8, 1985 50 FR 32138.
Federal Register noticePolicy Statement, Safety Goals for the Operation of Nuclear Power Plants; Policy Statement; Correction and Republication, dated August 21, 1986 51 FR 30028.
Federal Register noticePolicy Statement, Tribal Policy Statement, dated January 9, 2017 82 FR 2402.
Federal Register noticePolicy Statement, Policy Statement on the Regulation of Advanced Reactors, dated October 14, 2008 73 FR 60612.
Federal Register noticePolicy Statement, Final Safety Culture Policy Statement, dated June 14, 2011 76 FR 34773 Federal Register noticeProposed rule, Emergency Preparedness for Small Modular Reactors and Other New Technologies, dated May 12, 2020.
Federal Register noticeProposed rule, Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning, dated March 3, 2022 87 FR 12254.
Federal Register noticePublic meeting, Reporting Requirements for Nonemergency Events at Nuclear Power Plants, dated November 29, 2021 86 FR 67669.
International Commission on Radiological Protection (ICRP), Publication 2 Permissible dose for internal radiation, dated 1960.
https://www.icrp.org/publication.asp?id=i crp%20publication%202 ICRP, Publication 26 Recommendations of the ICRP, dated 1977 https://www.icrp.org/publication.asp?id=I CRP%20Publication%2026 ICRP, Publication 30 Limits for Intakes of Radionuclides by Workers, dated 1979 https://www.icrp.org/publication.asp?id=I CRP%20Publication%2030%20(Index)
Michigan v. EPA, 135 S. Ct. 2699 (2015).
NEI 18-04, Rev. 1, Risk-Informed Performance-Based Technology-Inclusive Guidance for Non-Light Water Reactors, dated August 2019 ML19251A472.
Nuclear Innovation Alliance (NIA), Clarifying Major Portions of a Reactor Design in Support of a Standard Design Approval, dated April 2017 https://www.nuclearinnovationalliance.or g/clarifying-major-portions-reactor-design-support-standard-design-approval
180 NRC, A Regulatory Review Roadmap for Non-Light Water Reactors, dated December 2017 ML17312B567.
NRC, Risk-Informed and Performance-Based Human-System Considerations for Advanced Reactors, dated March 2021 ML21069A003.
NUREG-0654/FEMA-REP-1, Revision 2, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedess in Support of Nuclear Power Plants, dated December 2019 ML19347D139.
NUREG-0880, Safety Goals for Nuclear Power Plant Operation, dated May 1983 ML071770230.
NUREG-1530, Revision 1, Reassessment of NRCs Dollar Per Person-Rem Conversion Factor Policy, Final Report, dated February 2022 ML22053A025.
NUREG/BR-0058, Revision 5, Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission, dated April 2017 ML17100A480.
NUREG/CR-5884, Revised Analyses of Decommissioning for the Reference Pressurized Water Reactor Power Station, dated November 1995 ML14008A187.
NUREG/CR-6187, Volume 1, Revised Analyses of Decommissioning for the Reference Boiling Water Reactor Power Station, dated July 1996 ML14008A186.
Office of Management and Budget Circular No. A-119, Federal Participation in the Development and Use of Voluntary Consensus Standards and in Conformity Assessment Activities, dated February 19, 1998 https://obamawhitehouse.archives.gov/o mb/circulars_a119_a119fr Pacific Northwest National Laboratory, Technical Letter Report, The Use of Electronic Communications to Perform Determinations of Fitness, dated August 2017 ML18081A607.
Preliminary Proposed Rule Language for the Part 53 Rulemaking: Subpart A -General Provisions, 2nd Iteration of Subparts B and C, and Subparts D, E, and F-Requirements for Operations (Operational Objectives & Programs), dated April 23, 2021 ML21112A195.
Preliminary Proposed Rule Language for the Part 53 Rulemaking: Subpart B, Technology-Inclusive Safety Requirements ML20289A591.
Research Information Letter (RIL) 2021-04, Feasibility Study on a Potential Consequence-Based Seismic Design Approach for Nuclear Facilities, dated April 2021 ML21113A066.
RG 1.110, Revision 1, Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors, dated October 2013 ML13241A052.
181 RG 1.134, Revision 4, Medical Assessment Of Licensed Operators Or Applicants For Operator Licenses At Nuclear Power Plants, dated September 2014.
ML003740140 RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 3, dated January 2018 ML17317A256.
RG 1.208, A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, dated March 2007 ML070310619.
RG 1.232, Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors, Revision 0, dated April 2018 ML17325A611 RG 1.233, Revision 0, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors, dated June 2020 ML20091L698.
RG 1.247, Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activites, issued March 2022 for trial use ML21235A008 RG 5.77, Insider Mitigation Program, issued March 2009 ML15219A609 SECY-83-293, Amendments to 10 CFR 50 Related to Anticipated Transients Without Scram (ATWS) Events," dated July 19, 1983 MLXXXXXXXXX SECY-18-0096, Functional Containment Performance Criteria For Non-Light-Water-Reactors, dated September 28, 2018 ML18115A157 SECY-19-0117, Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors, dated December 2019 ML18311A264.
SRM-SECY-20-0045, Population Related Siting Considerations for Advanced Reactors, dated July 2022 ML22194A885.
SECY-22-0052, Proposed Rule: Alignment of Licensing Processes and Lessons Learned from New Reactor Licensing (RIN 3150 AI66), dated June 6, 2022 ML21159A057.
Throughout the development of this rule, the NRC may post documents related to this rule, including public comments, on the Federal rulemaking website at https://www.regulations.gov under Docket ID NRC-2019-0062. The Federal rulemaking
182 website allows you to receive alerts when changes or additions occur in a docket folder.
To subscribe: (1) Navigate to the docket folder (NRC-2019-0062-0012); (2) click the Sign up for E-mail Alerts link; and (3) enter your e-mail address and select how frequently you would like to receive e-mails (daily, weekly, or monthly).