10 CFR 50 Appendix Q, Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues

Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues This appendix sets out procedures for the filing, Staff review, and referral to the Advisory Committee on Reactor Safeguards of requests for early review of one or more site suitability issues relating to the construction and operation of certain utilization facilities separately from and prior to the submittal of applications for construction permits for the facilities. The appendix also sets out procedures for the preparation and issuance of Staff Site Reports and for their incorporation by reference in applications for the construction and operation of certain utilization facilities. The utilization facilities are those which are subject to § 51.20(b) of this chapter and are of the type specified in § 50.21(b) (2) or (3) or § 50.22 or are testing facilities. This appendix does not apply to proceedings conducted pursuant to Subpart F of Part 2 of this chapter.
1. Any person may submit information regarding one or more site suitability issues to the Commission's Staff for its review separately from and prior to an application for a construction permit for a facility. Such a submittal shall be accompanied by any fee required by Part 170 of this chapter and shall consist of the portion of the information required of applicants for construction permits by §§ 50.33(a)-(c) and (e), and, insofar as it relates to the issue(s) of site suitability for which early review is sought, by §§ 50.34(a)(1) and 50.30(f), except that information with respect to operation of the facility at the projected initial power level need not be supplied.
2. The submittal for early review of site suitability issue(s) must be made in the same manner and in the same number of copies as provided in §§ 50.4 and 50.30 for license applications. The submittal must include sufficient information concerning a range of postulated facility design and operation parameters to enable the Staff to perform the requested review of site suitability issues. The submittal must contain suggested conclusions on the issues of site suitability submitted for review and must be accompanied by a statement of the bases or the reasons for those conclusions. The submittal must also list, to the extent possible, any long-range objectives for ultimate development of the site, state whether any site selection process was used in preparing the submittal, describe any site selection process used, and explain what consideration, if any, was given to alternative sites.
3. The Staff shall publish a notice of docketing of the submittal in the Federal Register, and shall send a copy of the notice of docketing to the Governor or other appropriate official of the State in which the site is located. This notice shall identify the location of the site, briefly describe the site suitability issue(s) under review, and invite comments from Federal, State, and local agencies and interested persons within 120 days of publication or such other time as may be specified, for consideration by the staff in connection with the initiation or outcome of the review and, if appropriate by the ACRS, in connection with the outcome of their review. The person requesting review shall serve a copy of the submittal on the Governor or other appropriate official of the State in which the site is located, and on the chief executive of the municipality in which the site is located or, if the site is not located in a municipality, on the chief executive of the county. The portion of the submittal containing information required of applicants for construction permits by §§ 50.33(a)-(c) and (e) and 50.34(a)(1) will be referred to the Advisory Committee on Reactor Safeguards (ACRS) for a review and report. There will be no referral to the ACRS unless early review of the site safety issues under § 50.34(a)(1) is requested.
4. Upon completion of review by the NRC staff and, if appropriate by the ACRS, of a submittal under this appendix, the NRC staff shall prepare a Staff Site Report which shall identify the location of the site, state the site suitability issues reviewed, explain the nature and scope of the review, state the conclusions of the staff regarding the issues reviewed and state the reasons for those conclusions. Upon issuance of an NRC Staff Site Report, the NRC staff shall publish a notice of the availability of the report in the Federal Register and shall make the report available at the NRC Web site, http://www.nrc.gov. The NRC staff shall also send a copy of the report to the Governor or other appropriate official of the State in which the site is located, and to the chief executive of the municipality in which the site is located or, if the site is not located in a municipality, to the chief executive of the county.
5. Any Staff Site Report prepared and issued in accordance with this appendix may be incorporated by reference, as appropriate, in an application for a construction permit for a utilization facility which is subject to § 51.20(b) of this chapter and is of the type specified in § 50.21(b) (2) or (3) or § 50.22 of this chapter or is a testing facility. The conclusions of the Staff Site Report will be reexamined by the staff where five years or more have elapsed between the issuance of the Staff Site Report and its incorporation by reference in a construction permit application.
6. Issuance of a Staff Site Report shall not constitute a commitment to issue a permit or license, to permit on-site work under § 50.10(e), or in any way affect the authority of the Commission, Atomic Safety and Licensing Appeal Panel, Atomic Safety and Licensing Board, and other presiding officers in any proceeding under Subpart F and/or G of Part 2 of this chapter.
7. The staff will not conduct more than one review of site suitability issues with regard to a particular site prior to the full construction permit review required by Subpart A of Part 51 of this chapter. The staff may decline to prepare and issue a Staff Site Report in response to a submittal under this appendix where it appears that, (a) in cases where no review of the relative merits of the submitted site and alternative sites under Subpart A of Part 51 of this chapter is requested, there is a reasonable likelihood that further Staff review would identify one or more preferable alternative sites and the Staff review of one or more site suitability issues would lead to an irreversible and irretrievable commitment of resources prior to the submittal of the analysis of alternative sites in the Environmental Report that would prejudice the later review and decision on alternative sites under Subpart F and/or G of Part 2 and Subpart A of Part 51 of this chapter; or (b) in cases where, in the judgment of the Staff, early review of any site suitability issue or issues would not be in the public interest, considering (1) the degree of likelihood that any early findings on those issues would retain their validity in later reviews, (2) the objections, if any, of cognizant state or local government agencies to the conduct of an early review on those issues, and (3) the possible effect on the public interest of having an early, if not necessarily conclusive, resolution of those issues.

Federal Register

, as amended at 49 FR 9405, Mar. 12, 1984; 51 FR 40311, Nov. 6, 1986; 53 FR 43420, Oct. 27, 1988; 64 FR 48952, Sept. 9, 1999]

External Links

[[URL::http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-appq.html%7CNRC website 10 CFR 50 Appendix Q]]

v t e Code of Federal Regulations
Title 10 Part 50 - DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
1, General Provisions, Basis, purpose, and procedures applicable 2, Definitions 3, Interpretations 4, Written communications 5, Deliberate misconduct 7, Employee protection 8, Information collection requirements: OMB approval 9, Completeness and accuracy of information 10, Requirement of License, Exceptions, License required; limited work authorization 11, Exceptions and exemptions from licensing requirements 12, Specific exemptions 13, Attacks and destructive acts by enemies of the United States; and defense activities 20, Classification and Description of Licenses, Two classes of licenses 21, Class 104 licenses; for medical therapy and research and development facilities 22, Class 103 licenses; for commercial and industrial facilities 23, Construction permits 30, Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain Applicants, Filing of application for licenses; oath or affirmation 31, Combining applications 32, Elimination of repetition 33, Contents of applications; general information 34, Contents of applications; technical information 36, Technical specifications 37, Agreement limiting access to Classified Information 38, Ineligibility of certain applicants 39, Public inspection of applications 40, Standards for Licenses, Certifications, and Regulatory Approvals, Common standards 41, Additional standards for class 104 licenses 42, Additional standard for class 103 licenses 43, Additional standards and provisions affecting class 103 licenses and certifications for commercial power 44, Combustible gas control for nuclear power reactors 45, Standards for construction permits, operating licenses, and combined licenses 46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors 47, Emergency plans 48, Fire protection 49, Environmental qualification of electric equipment important to safety for nuclear power plants 50, Issuance, Limitations, and Conditions of Licenses and Construction Permits, Issuance of licenses and construction permits 51, Continuation of license 52, Combining licenses 53, Jurisdictional limitations 54, Conditions of licenses 55, Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses 56, Conversion of construction permit to license; or amendment of license 57, Issuance of operating license 58, Hearings and report of the Advisory Committee on Reactor Safeguards 59, Changes, tests and experiments 60, Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation 61, Fracture toughness requirements for protection against pressurized thermal shock events 62, Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants 63, Loss of all alternating current power 64, Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors 65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants 66, Requirements for thermal annealing of the reactor pressure vessel 67, Accident source term 68, Criticality accident requirements 69, Inspections, Records, Reports, Notifications, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors 70, Inspections 71, Maintenance of records, making of reports 72, Immediate notification requirements for operating nuclear power reactors 73, Licensee event report system 74, Notification of change in operator or senior operator status 75, Reporting and recordkeeping for decommissioning planning 76, . Licensee's change of status; financial qualifications 78, US/IAEA Safeguards Agreement, Facility information and verification 80, Transfers of Licenses--Creditors' Rights--Surrender of Licenses, Transfer of licenses 81, Creditor regulations 82, Termination of license 83, Release of part of a power reactor facility or site for unrestricted use 90, Amendment of License or Construction Permit at Request of Holder, Application for amendment of license, construction permit, or early site permit 91, Notice for public comment; State consultation 92, Issuance of amendment 100, Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission, Revocation, suspension, modification of licenses, permits, and approvals for cause 101, Retaking possession of special nuclear material 102, Commission order for operation after revocation 103, Suspension and operation in war or national emergency 109, Backfitting 110, Enforcement, Violations 111, Criminal penalties 120, Additional Standards for Licenses, Certifications, and Regulatory Approvals, Training and qualification of nuclear power plant personnel 150, Aircraft impact assessment Appendices: 10 CFR 50 Appendix A, Appendix a to Part 50-General Design Criteria for Nuclear Power Plants 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants 10 CFR 50 Appendix C, Appendix C to Part 50-A Guide for the Financial Data and Related Information Required to Establish Financial Qualifications for Construction Permits and Combined Licenses 10 CFR 50 Appendix D, Appendix D to Part 50--Reserved 10 CFR 50 Appendix E, Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities 10 CFR 50 Appendix F, Appendix F to Part 50--Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities 10 CFR 50 Appendix G, Appendix G to Part 50-Fracture Toughness Requirements 10 CFR 50 Appendix H, Appendix H to Part 50-Reactor Vessel Material Surveillance Program Requirements 10 CFR 50 Appendix I, Appendix I to Part 50-Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Is Reasonably Achievable" for Radioactive Material In Light-Water-Cooled Nuclear Power Reactor E 10 CFR 50 Appendix J, Appendix J to Part 50-Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors 10 CFR 50 Appendix K, Appendix K to Part 50-Eccs Evaluation Models 10 CFR 50 Appendix L, Appendix L to Part 50--Reserved 10 CFR 50 Appendix M, Appendix M to Part 50--Reserved 10 CFR 50 Appendix N, Appendix N to Part 50-Standardization of Nuclear Power Plant Designs: Permits to Construct and Licenses to Operate Nuclear Power Reactors of Identical Design At Multiple Sites 10 CFR 50 Appendix O, Appendix O to Part 50-Reserved 10 CFR 50 Appendix P, Appendix P to Part 50--Reserved 10 CFR 50 Appendix Q, Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues 10 CFR 50 Appendix R, Appendix R to Part 50-Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 10 CFR 50 Appendix S, General Information

10 CFR 50 Appendix Q, Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues

Federal Register

External Links

Navigation menu

Search