Regulatory Guide 3.50: Difference between revisions

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{{Adams
{{Adams
| number = ML14043A080
| number = ML13038A424
| issue date = 09/30/2014
| issue date = 01/31/1982
| title = Rev. 2, Standard Format and Content for a License Application for an Independent Spent Fuel Storage Installation or a Monitored Retrievable Storage Facility
| title = Guidance on Preparing a License Application to Store Spent Fuel in an Independent Spent Fuel Storage Installation
| author name = Parks J D
| author name =  
| author affiliation = NRC/RES/DE/RGDB
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = White B
| contact person =  
| case reference number = DG-3042
| case reference number = TASK FP 907-4
| document report number = RG 3.50, Rev. 2
| document report number = RG-3.050
| package number = ML14042A476
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 11
| page count = 8
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
September 2014OFFICE OF NUCLEAR REGULATORY RESEARCH
COMMISSION  
Revision 2 REGULATORY GUIDE
January 1982 0 REGULATORY
  Technical Lead B. White Written suggestions regarding this guide or development of new guides may be submitted through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/.  The regulatory guide is also available through the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML14043A080.  The regulatory analysis may be found in ADAMS under Accession No. ML12087A039 and the staff responses to the public comments on DG-3042 may be found under ADAMS Accession No.ML14043A068.
GUIDE OFFICE OF NUCLEAR REGULATORY  
RESEARCH REGULATORY
GUIDE 3.50 (Task FP 907-4)GUIDANCE ON PREPARING
A LICENSE APPLICATION
TO STORE SPENT FUEL IN AN INDEPENDENT
SPENT FUEL STORAGE INSTALLATION
INTRODUCTION
Subpart B, "License Application, Form, and Contents," of 10 CFR Part 72, "Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation," specifies the information to be covered in an application for a license to store spent fuel in an independent spent fuel storage installation (ISFSI).However, Part 72 does not specify the format to be followed in the license application.


REGULATORY GUIDE 3.50
This regulatory guide suggests a format acceptable to the NRC staff for submitting the information specified in Part 72 for a license application to store spent fuel in an ISFSI.Other regulations applicable to the licensing of spent fuel storage in an ISFSI are in the following parts of Title 10,"Energy," of the Code of Federal Regulations:
(Draft was issued as DG-3042, dated December 2013)
2 -Rules of Practice for Domestic Licensing Proceedings
STANDARD FORMAT AND CONTENT FOR A SPECIFIC
8 -Interpretations
LICENSE APPLICATION FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION OR MONITORED
9 -Public Records 11 -Criteria and Procedures for Determining Eligibility for Access to or Control over Special Nuclear Material 19 -Notices, Instructions and Reports to Workers;Inspections.
RETRIEVABLE STORAGE FACILITY


==A. INTRODUCTION==
20 -Standards for Protection against Radiation
Purpose  This regulatory guide provides a description of a standard format and content that the U.S. Nuclear Regulatory Commission (NRC) staff considers acceptable for specific license application for Independent Spent Fuel Storage Installations (ISFSIs) and Monitored Retrievable Storage (MRS) facilities.
-21 -Reporting of Defects and Noncompliance
25 -Access Authorization for Licensee Personnel 51 -Licensing and Regulatory Policy and Procedures for Environmental Protection
73 -Physical Protection of Plants and Materials 75 -Safeguards on Nuclear Material-Implementation of US/IAEA Agreement 95 -Security Facility Approval and Safeguarding of National Security Information and Restricted Data 150 -Exemptions and Continued Regulatory Authority in Agreement States and in Offshore Waters under Section 274 170 -Fees for Facilities and Materials Licenses and other Regulatory Services under the Atomic Energy Act of 1954, as Amended.Part 72 provides for a single licensing procedure.


Applicable Rules and Regulations
The smooth functioning of this one-step licensing procedure requires that the license application be essentially complete in its initial submission.


* Title 10, Part 72, of the Code of Federal Regulations(10 CFR 72), "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste" (Ref. 1), Subpart B, "License Application, Form, and Contents," specifies the information that must be in an appli cation for a license to store spent nuclear fuel, high-level radioactive waste, and power-reactor-related greater than Class C (GTCC) waste in an ISFSI or in a MRS facility.
A license under this part will be issued before the start of construction of any physical facilities involved.


Related Guidance
Under this procedure, the final design details of those ISFSI components, systems, and structures that are important to safety must be available for review and evaluation.


* Regulatory Guide (RG
Part 72 also requires that a site evaluation be provided to ensure that the natural characteristics of the site and its environs are sufficiently known and have been factored into the engineering design of the installation.
) 3.62, "Standard Format and Content for the Safety Analysis Report for Onsite Storage of Spent Fuel Storage Casks," (Ref. 2), provides guidance on the preparation of the Safety Analysis Report (SAR) for an ISFSI or MRS facility using dry storage. It also provides information


on technical specifications that is useful for ISFSIs and MRS facilities
The document in which this information is presented is a Safety Analysis Report (SAR).Although an applicant may plan to contract with another organization for the design, construction, and possibly the operation of the proposed ISFSI, a licensee under Part 72 cannot delegate to a contractor the responsibility for meeting all applicable regulatory requirements.


* NUREG-1757, Volume 3, Revision 1, "Consolidated Decommissioning Guidance - Financial Assurance, Record Keeping and Timeliness," (Ref. 3), contains guidance on financial assurance for ISFSIs licensed under 10 CFR Part 72.
This means that the applicant must make a commitment that, as the licensee, it will have an adequate staff to ensure that regulatory requirements are met at each stage of the proposed project. If the applicant plans to contract with another organization for the operation of the proposed ISFSI, the contractual arrangements must be described in the license application.


Regulatory Guide 3.50, Revision 2, Page 2
Any subsequent changes in such contractual arrangements may require an amendment to the license.This guide represents a standard format that is acceptable to the NRC staff for the license application.
* RG 5.55, "Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities," (Ref. 4), although it does not specifically address ISFSIs or MRS facilities, contains information that


could be useful in developing safeguards contingency plans for these facilities.
Conformance with this guide, however, is not mandatory.


* RG 3.67, "Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities," (Ref. 5), provides format and technical content information for emergency plans which are required by 10 CFR 72.32.
License applica-tions with different formats will be acceptable to the staff if they provide an adequate basis for the findings required for the issuance of a license. However, because it may be USNRC REGULATORY
GUIDES Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specific parts -of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents, or to provide guidance to applicants.


* RG 5.44, "Perimeter Intrusion Alarm Systems." (Ref. 6), although it does not specifically address ISFSIs or MRS facilities, contains information that could be useful in developing physical security plans for these facilities.
Regulatory Guides are not substitutes for regulations, and compliance with them is not required.


* NUREG-1748, "Environmental Review Guidance fo r Licensing Actions Associated with NMSS Programs," (Ref. 7), provides format and technical content information for environmental reports which are required by 10 CFR 72.34.
Methods and solutions different from those set out in the guides will be acceptable If they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.


Purpose of Regulatory Guides The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agency's regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants.  Regulatory guides are not substitutes for regulations and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis fo r the findings required for the issuance or continuance of a permit or license by the Commission.
This guide was Issued after consideration of comments received from the Public. Comments and suggestions for improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa-tion or experience.


Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 72 that the Office of Management and Budget (OMB) approved under OMB control number 3150-0132. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Docketing and Service Branch.The guides are issued in the following ten broad divisions:
1. Power Reactors 6. Products 2. Research and Test Reactors


==B. DISCUSSION==
===7. Transportation===
Reason for Revision This revision to RG 3.50 (Revision 2) was issued to conform to the format and content requirements in 10 CFR Part 72, which has been revised several times since Revision 1 was issued, and to update guidance on electronic submissions of applications. In addition, Revision 2 includes editorial changes to improve clarity.
3. Fuels and Materials Facilities
8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection
10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Publications Sales Manager.


Background RG 3.50 was originally issued in January 1982 to provide an acceptable format for the content of license applications for spent fuel facilities.  Revision 1 of this guide was published in September1989 to include MRS's and updates to 10 CFR 72.  Revision 1 of RG 3.50 became outdated because it discussed how to submit forms on microfilm and the agency has now moved most of its document submission to electronic form.  Most of the guidance that was referenced in Revision 1 has been withdrawn, such as Regulatory Guide 3.44 "Standard Format and Content for the Safety Analysis Report for an Independent Regulatory Guide 3.50, Revision 2, Page 3 Spent Fuel Storage Installation (Water-Basin Type)," and American Nuclear Society Institute (ANSI) Standard N299-1976 "Administrative and Managerial Control for the Operation of Nuclear Fuel Reprocessing Plants."  The information from these referenced documents has been captured in RG 3.62 "Standard Format and Content for the Safety Analysis Report for onsite Storage of Spent Fuel Storage Casks" and the current version of 10 CFR Part 72, "Licensing Requirements for the Independent Storage
more difficult to locate needed information, the staff review time may be longer, and there is a greater likelihood that the staff may regard the license application as incomplete.


of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste." 
As experience is gained in the licensing of spent fuel storage, the Commission's requirements for information needed in its review of applications for licenses to store spent fuel in an ISFSI may change. Revisions of the Commis-sion's needs for information in connection with such licensing actions will be conveyed to the industry and the public by (1) amendments to NRC regulations, (2) revisions to this regulatory guide, (3) issuance of new or revised regulatory guides, and (4) direct communications, as needed, with an applicant by the NRC staff.Since the preparation of a license application pursuant to Part 72 will be a new experience, prospective applicants are encouraged to meet with representatives of the Division of Fuel Cycle and. Material Safety of the Office of Nuclear Material Safety and Safeguards during the development of a license application to resolve any problems that may arise.An early resolution of potential problems is beneficial to all concerned with the licensing process.Contents of the License Application The license application is the basic document that must address each of the requirements of Part 72 and must be complete in itself. However, the following subjects should be covered in separate reports that are identified as enclosures to the license application, and the contents of each report should be summarized in a brief statement in the license application:
  Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety guides and standards constituting a high level of safety for protecting people and the environment.  IAEA safety guides present international good practices and increasingly reflects best practices to help users striving to achieve high levels of safety.  Pertinent to this regulatory guide, the IAEA safety series does not contain a similar document. The only format and content guidance that IAEA has issued is found in GS-G-4.1, "Format and Content of the Safety Analysis Report for Nuclear Power Plants" (Ref. 8). This document specifically describes format and content for SARs for nuclear plants, but does not cover spent fuel storage facilities. IAEA Safety Guide SSG-12, "L
1. Safety Analysis Report 2. Decommissioning Plan 3. Emergency Plan 4. Environmental Report 5. Quality Assurance Program 6. Physical Security Plan 7. Safeguards Contingency Plan 8. Personnel Training Program 9. Proposed License Conditions, including Technical Specifications
icensing Process for Nuclear Installations" (Ref. 9) contains a brief section that lists required contents of a license, but it is not specific to spent fuel storage facilities and it does not provide any detail or format.  Lastly, IAEA Safety Guide SSG -15, "Storage of Spent Nuclear Fuel" (Ref. 10) addresses the design, operation and safety assessment of spent fuel storage facilities as well as the application of safety objectives, principles and criteria to the storage of spent nuclear fuel, but does not provide guidance on the format and content of applications.
10. Design for Physical Security Format and Style The applicant should strive for clear, concise presentation of the information provided in the application.


C.  STANDARD FORM
The applica-tion should be written in plain English and should be understandable to an educated lay person.Abbreviations should be consistent throughout the license application and its enclosures.
AT AND CONTENT
This regulatory guide provides a format that the NRC considers acceptable for submitting the information for 10 CFR Part 72 license applications to store spent nuclear fuel, high-level radioactive waste, and reactor-related Greater than Class C (GTCC) waste pursuant to a  specific license. Conformance with this guide is not mandatory and the NRC staff will consider a license application with different formats acceptable if it provides an adequate basis for the findings required for the issuance of a license.  The staff recommends using the format suggested in this regulatory guide because doing so will allow for a more efficient review by the staff and a potential reduction in the extent or the number of requests for additional information.


1. Contents of the License Application The license application is the document that should address each of the requirements of 10 CFR Part 72 and should be comple ted upon submittal.  The application is required to contain general information about the applicant, pursuant to 10 CFR 72.22.  The license application should also include the following documents: 
Any abbreviations, symbols, or special terms unique to the proposed activity or not in general use should be defined when they first appear.A title page identifying key individuals responsible for the preparation of the license application and the oath required under paragraph
* SAR (see §72.24 and RG 3.62); 
72.11(b) should be included.
* Quality assurance (QA) program (see 10 CFR 72.24(n) and 10 CFR Part 72.140 (d)); 
* Physical security plan (including guard training) (see 10 CFR 72.24(o), and 10 CFR 72.180);
* Safeguards contingency plan (see 10 CFR 72.184) ;
* Proposed technical specifications (see 10 CFR 72.26 and RG 3.62);
* Applicant's technical qualifications (see 10 CFR 72.28);
* Personnel training program (see 10 CFR 72.28(b)); 
Regulatory Guide 3.50, Revision 2, Page 4
* Decommissioning plan and decommissioning funding plan (see 10 CFR 72.30 (a) and 10 CFR
72.54(g),;
* Emergency plan (see 10 CFR 72.32),;
* Environmental report (see 10 CFR 72.34); and 
* Proposed license conditions (see 10 CFR 72.44),.
2. Format and Style The applicant should strive for a clear, concise presentation of the information provided in the license application.  Confusing or ambiguous statements and unnecessarily verbose descriptions do not contribute to expeditious technical review.  Claims about the adequacy of designs or design methods should be supported by technical bases (i.e., an appropriate engineering evaluation or description of actual tests).  Terms should be used as defined in 10 CFR Part 72, specifically or including  10 CFR 72.3. If a particular regulatory requirement does not apply to the proposed storage facility, the applicant should use the term "Not Applicable" instead of omitting the corresponding section.  In addition, applicants should justify their decision not to address a particular requirement when its applicability is questionable.  Appendices to each document in an application should include any appropriate detailed information that was omitted from the main text.  The first appendix to a given document in an application should provide a list of documents that are referenced in the text of that application, including page numbers, if appropriate.  If a license application references a proprietary document, it should also reference the nonproprietary summary description of that document.  Applicants may also use appendices to provide supplemental information such as calculational methods or design approaches used by the applicant. When a license application cites numerical parameters or values, the number of significant figures should reflect the accuracy or precision to which the number is known.  When possible, the applicant should specify estimated limits of error or uncertainty.  Applicants should not drop or round off significant figures if this action would affect subsequent conclusions. Applicants should use acronyms, abbreviations, symbols, and special terms consistently throughout a license application and in a manner that is consistent with generally accepted usage.  Each document in an application should define any acronyms, abbreviations, symbols, or special terms used in the given section that are unique to the proposed storage system or not common in general usage.  Applicants should use drawings, diagrams, sketches, and charts when these media would more accurately or conveniently convey the information.  However, applicants should ensure that drawings, diagrams, sketches, and charts present information in a legible and consistent form and define relevant symbols.  In addition, applicants should not reduce drawings, diagrams, sketches, and charts to the extent that readers need visual aids to interpret pertinent information. Applicants should number pages sequentially within each document, section, and appendix.  For example, the fourth page of Section six would be numbered 6-4. A title page should identify key individuals responsible for the preparation of the license application and should include the oath or affirmation as required by 10 CFR 72.16(b).  A table of contents should also be included.


Regulatory Guide 3.50, Revision 2, Page 5 Applications that do not contain the information described in the regulations may be rejected for review by the NRC.
A table of contents should also be included.Physical Specifications
1. Paper size: 8h x I Iinches 2. Paper stock and ink: Suitable quality in substance, paper color, and ink density for handling and reproduction by microfilming or image-cbpying equipment.


3. Submissions and Revisions Procedures for Submissions Applications may be submitted either electronically, by mail, or by hand delivery to NRC headquarters.  For details on communications with the NRC, including submitting applications, see 10 CFR 72.4. Detailed guidance on submitting electronic applications and supplements can be found on the NRC's Web site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to MSHD.Resource@nrc.gov
3. Paper margins: A margin of no less than 1 inch should be maintained on the top, bottom, and binding side of all pages.4. Printing: a. Composition:
; or by writing to the Office of Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Text should be single or 11/2 spaced.b. Type face and style: Suitable for microfilming or image-copying equipment.


The guidance on electronic submissions discusses, among other topics, the formats that the NRC can accept, the use of electronic signatures, and the treatment of nonpublic information. If electronic submissions are utilized, applicants are encouraged to also send an electronic copy to the pertinent NRC
c. Reproduction:
project manager.
Either mechanical or photographic.


Procedures for Updating or Revising Pages For applicants making electronic submissions, a consolidated document is preferable to submission of individually edited pages and will enable reviewers to have the latest information with minimal effort to print and replace pages. For paper submissions, applicants should update data and text by replacing entire pages whenever a change is made to that page.  Applicants should also highlight the updated or revised portion of each page using a "change indicator" consisting of a bold vertical line drawn in the margin opposite the binding margin.
Text should be printed on both sides of the paper with the image printed head to head.5. Binding: Pages. should be punched for a standard 3-hole loose-leaf binder.6. Chapter and page numbering:
Each requirement of the regulation addressed should be shown as a separate chapter with the same number as the chapter given in this guide, e.g., Chapter 8, "Operator Training." Pages should be numbered sequentially in each chapter, e.g., 8-1, 8-2, etc.Do not number the entire document sequentially.


All pages submitted to update, revise, or add pages to an application should show the date of the revision and the corresponding change or amendment number. A transmittal letter, including a guide page listing the pages to be inserted and removed, should accompany the revised pages.  When applicable, supplemental pages may follow the revised page, with the pages still being numbered sequentially.  Applicants should distinguish between changes made under the change authority in 10 CFR 72.48 (c)(1) and amendment to the license or Certificate of Compliance as required by 72.48 (c)(2). All statements on a revised page should be accurate as of the date of each submittal.  Applicants should take special care to ensure that they revise the documents submitted as part of the application to reflect any changes to the design, contents, analysis, and tests reported in supplemental information (e.g., responses to NRC staff requests for information or responses to regulatory positions). Referenced Materials Under 10 CFR 72.18, applicants may avoid repetition by incorporating by reference material previously filed with the NRC. However, applicants should use caution in making such references and should ensure that they are pertinent to the subject discussed, contain current information, and are readily obtainable or extractable from the referenced documents. It may be more efficient in some cases to
Procedures for Updating or Revising Pages All pages submitted to update, revise, or add to the license application should. show the date of change and a change or amendment number. The changed or revised portion of each page should be highlighted by a "change indicator" mark consisting of a bold vertical line drawn in the margin opposite the binding side.Referenced Materials Caution should be used in references to information previously filed with the AEC or NRC. Such references must be pertinent to the subject discussed, must contain current information, and must be readily obtainable or extractable from the referenced documents.


repeat, or summarize, information furnished in the previously submitted document.
It may be more efficient in some cases to repeat in a license application previously furnished information.


Regulatory Guide 3.50, Revision 2, Page 6 Protection of Proprietary Information The applicant should identify and submit under separate cover any information that it considers proprietary.  The requirements in 10 CFR 2.390(b) (Ref. 11) should be followed for such information.  For safeguards information, applicants should also adhere to requirements in 10 CFR 73.21, 10 CFR 73.22, and 10 CFR 73.23 as applicable.
Chapter 1. GENERAL AND FINANCIAL
INFORMATION
The license application should address the requirements of § 72.14 of 10 CFR Part 72 regarding details on the identity of an applicant.


4. Further Information General and Financial Information Information on the contents of applications is found in 10 CFR 72.22. Applicants, except for DOE, must provide sufficient information to demonstrate to the Commission that they can satisfy the financial qualifications of activities associated with an ISFSI or MRS facility.  This includes but is not limited to: estimated construction costs, estimated operating costs over the planned life of the facility, and estimated decommissioning costs.
If the applicant is other than the owner or planned operator of the proposed ISFSI, details of the working and contractual arrangements between all parties involved should be set forth. Any information on such matters considered as proprietary information by the applicant should be identified and submitted under separate 3.50-2 cover. The procedures in 10 CFR 2.790(b) should be followed.If the proposed ISFSI is to be built on the site of another licensed activity or facility such as a nuclear power plant, details of the working arrangements and responsibilities of the licensees involved should be stated. Similarly, if unlicensed activities are carried out at the proposed site, any potential interactions between the proposed ISFSI and these other site activities should be explained.


Safety Analysis Report Each application for a license should include a SAR as described in 10 CFR 72.24.  The information should describe the proposed ISFSI or MRS facility for the receipt, handling, packaging, and storage of spent fuel, high-level radioactive waste and/or reactor related GTCC waste.  Regulatory Guide 3.62, (Ref. 2), "Standard Format and Content for a Safety Analysis Report for Dry Storage of Spent Fuel at an Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Facility," provides additional guidance on the preparation of the SARs for ISFSIs and MRS facilities using dry storage.
Paragraph
72.14(e) specifically addresses the required financial information that must be submitted with the application.


Quality Assurance Program The application should contain either the QA program required by 10 CFR Part 72, Subpart G, "Quality Assurance" (as an enclosure), or should reference a currently NRC-approved QA program.  The SAR should briefly describe the QA program.  A QA program that has been approved by the NRC as meeting Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities" (Ref. 12), may be applied to the ISFSI.  Note that 10 CFR 72.140(d) states, "A quality assurance program previously approved by the Commission as satisfying the requirements of Appendix B of Part 50 of this chapter, Subpart H to part 71 of this chapter, or Subpart G to this part will be accepted as satisfying the requirements of paragraph (b) of this section, except that a licensee, applicant for a license, certificate holder, and applicant for a CoC who is using an Appendix B or Subpart H quality assurance program shall also meet the record keeping requirement of 72.174.  In filing the description of the quality assurance program required by paragraph (c) of this section, each licensee, applicant for license, certificate holder, and applicant for a COC shall notify the NRC, in accordance with section 72.4, of its intent to apply its previously-approved quality assurance program to ISFSI activities or spent fuel storage casks activities.  The notification shall identify the previously-approved quality assurance program by date of submittal to the Commission, docket number, and date of Commission approval." 
If the applicant is a government agency or a regulated utility, the assumption is made that the applicant is financially qualified for a license under Part 72. If the applicant is a corporation organized for the specific purpose of owning and operating the proposed ISFSI, details of its organizational structure, including the responsibilities of its members to meet the financial requirements of the proposed ISFSI throughout its proposed operating life and ultimate decommissioning, must be stated. This requirement is applicable even if the proposed ISFSI is to be owned and operated by a consortium of utilities.
Physical Protection Plan As discussed in 10 CFR 72.24(o), as part of the licensing process, the applicant must submit  a physical protection program that satisfies the requirements in 10 CFR Part 72, Subpart H, "Physical Protection."  Because the details of the provisions for physical protection are withheld from public disclosure, the applicant may submit this document(s) separately from the rest of the application.  The Regulatory Guide 3.50, Revision 2, Page 7 license application should contain a reference to the submission for the physical security program and the date of NRC approval if the NRC had approved the program before submittal of the application.  The physical protection plan should describe the design criteria for the physical protection of the proposed ISFSI or MRS facility, the design bases, and how the design bases relate to the design criteria, and should ensure that the physical protection plan meets the requirements in 10 CFR 73.51,  
"Requirements for the physical protection of stored spent nuclear fuel and high-level radioactive waste" (Ref. 13). 
Safeguards Contingency Plan A safeguard contingency plan is a documented plan to give guidance to licensee personnel in order to accomplish specific defined objectives in the ev ent of threats, theft, or radiological sabotage relating to special nuclear materials or nuclear facilities.  As required by 10 CFR 72.184, the licensee shall prepare and maintain a safeguards contingency plan in accordance with Appendix C to 10 CFR Part 73 "Nuclear Power Plant Safeguards Contingency Plans."  Although RG 5.55, "Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities" (Ref. 4) relates to a fuel cycle plant, it provides information that might be useful for creating safeguards contingency plans for ISFSIs and MRS facilities.


Proposed Technical Specifications The regulations in 10 CFR 72.26 "Contents of application: Technical specifications," require applications to include proposed technical specifications in accordance with requirements of 10 CFR 72.44 "License conditions," in addition to a summary st atement of the bases of and justifications for these technical specifications.  For more information on technical specifications, please review RG 3.62.
Chapter


Technical Qualifications Title 10 CFR 72.40(a)(4) requires a finding by the NRC that the applicant is qualified through training and experience to operate an ISFSI or MRS facility. Information that the application must include for this purpose can be found in 10 CFR 72.28, "Contents of application:  Applicant's technical qualifications."  The licensee is responsible for implementing the proposed project as described in the license application.  This means that, even though a contractor may perform much of the actual work involved during the site selection, design, procurement, construction, and even the operating phases of the project, the licensee must have staff that is know ledgeable in all aspects of the project.  The application should include the applicant's experience to show that it has the technical qualifications to construct and ope rate (or oversee the construction and operation of) the ISFSI or MRS facility.  Note that if previous sections have discussed the operating organization and delegations and/or adequately described the minimum skills and experience, the information need not be repeated but may be referenced as appropriate. Personnel Training Program Applicants should describe a training program in their application as discussed in 10 CFR 72.28(b).  Requirements for the personnel training program are in 10 CFR Part 72, Subpart I "Training and Certification of Personnel."
===2. TECHNICAL ===
QUALIFICATIONS
Paragraph
72.31 (a)(4) and § 72.17 require a finding by the staff that the applicant is qualified by training and experience to construct and operate an ISFSI.Although spent fuel storage in an ISFSI is generally considered a relatively low-risk operation compared to some other types of nuclear activities, the design, construc-tion, and operation of an ISFSI require certain skills and an understanding of the requirements involved to ensure that the objective of a relatively low-risk operation is achieved in practice.


Regulatory Guide 3.50, Revision 2, Page 8 Decommissioning Plan and Decommissioning Funding Plan The proposed final decommissioning plan should include all the criteria discussed in 10 CFR 72.54(g). Updated and detailed plans must be submitted and approved by the Commission prior to the start of any decommissioning activity.  Each application should include a decommissioning plan and decommissioning funding plan that contains sufficient information on proposed practices and procedures for decontamination and decommissioning and associated funding in accordance with the requirements of
The license application should contain a commit-ment that the applicant will staff the project with an adequate cadre of personnel possessing the required skills throughout all phases of the project. This element of the license. application is in addition to the discussion of the conduct of operations covered in Chapter 9 of the SAR.The licensee is responsible for the execution of the proposed project as described in the license application.
10 CFR 72.30, "Financial assurance and recordkeeping for decommissioning."  NUREG-1757, Volume 3, Revision 1, "Consolidated Decommissioning Guidance -- Financial Assurance, Recordkeeping and Timeliness, contains additional guidance on financial assurance for ISFSI's licensed under 10 CFR Part 72. Emergency Plan The applicant should submit a plan for coping with emergencies as discussed in 10 CFR 72.32.


If the ISFSI is located on the site of a facility licensed under 10 CFR Part 50, the emergency plan required by 10 CFR 50.47, "Emergency plans," satisfies the requirements in 10 CFR 72.32, "Emergency Plan."  Additionally for ISFSIs or MRS facilities that are not located on the site of a nuclear power plant, the guidance in Regulatory Guide 1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors" (Ref. 5), provides useful information for applicants when developing the Emergency Plan for a site-specific ISFSI. Environmental Report The regulations at 10 CFR 72.34, "Environmental report," require applicants to submit as part of the license application, an environmental report that satisfies the requirements in 10 CFR Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions" (Ref. 14), Subpart A, "National Environmental Policy Act-Regulations Implementing Section 102(2).Chapter 6 of NUREG-1748, "Environmental Review Guidance for Licensing Actions Associated with NMSS Programs," (Ref. 6) issued August 2003, provides format and technical content information for the environmental report that is required by 10 CFR 72.34.
This means that, even though much of the actual work involved during the site selection, design, procurement, con-struction, and even the operating phases of the project may be performed by a contractor, the licensee must have a staff that is knowledgeable in all aspects of the project. If such a staff does not actually exist, the applicant should describe the staffing plans in sufficient detail to support the finding required by paragraph
72.3 l(a)(4).Chapter  


Proposed License Conditions According to 10 CFR 72.44, license conditions are required to be included with the license.  Applicants may propose license conditions to address design, construction and operation of the facilities.
===3. TECHNICAL ===
INFORMATION;
SAFETY ANALYSIS REPORT As required by § 72.15, the technical information is presented in the SAR, which should be submitted as an enclosure to the license application.


Regulatory Guide 3.50, Revision 2, Page 9
A summary statement identifying the type of installation proposed (e.g., a water basin), its design capacity, any unique features incorporated in its design, and its mode of operation is adequate for the license application document.The SAR required for an ISFSI differs from the SARs for some other nuclear facilities in that the initial SAR is expected *to be complete and comparable in scope and detail to the final. SAR for facilities licensed under 10 CFR Part 50. Section 72.15 identifies the minimum information that is required to be included in the SAR. Although§ 72.50 provides for the subsequent updating of the SAR, such changes during the design and construction phases of the project are expected to be of minor importance.


==D. IMPLEMENTATION==
Any of these changes deemed significant by the staff may cause delay in the granting of the final clearance to receive spent fuel.Guidance on the preparation of the SAR for an ISFSI of the conventional water-basin type is contained in Regulatory Guide 3.44, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)." For the dry storage ISFSI, guidance on the preparation of the SAR is contained in Regulatory Guide 3.48, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)." Chapter
The purpose of this section is to provide information on how applicants and licensees
1 may use this regulatory guide and information regarding the NRC staff's plans for using this guide. In addition, it describes how the NRC staff has complied with the backfitting provisions in 10 CFR 72.62 and issue finality provisions of 10 CFR Part 52.


The staff recommends that applicants use the format suggested in this regulatory guide because doing so will allow for a more efficient review by the staff and potentially reduce the extent or the number of staff requests for additional information. Conformance with this guide is not mandatory and the NRC staff will consider license applications with different formats acceptable if they provide an adequate basis for the findings required for the issuance of a license.
===4. CONFORMITY ===
TO GENERAL DESIGN CRITERIA Subpart F of 10 CFR Part 72 contains the general design criteria for an ISFSI. The subject of conformity to the genera- design. criteria o.i .overed in tala 11- the C A r3. II *sufficient that the license application contain a summary discussion of each criterion and reference where more detailed information on a specific subject can be found in the SAR.Chapter


This regulatory guide applies only to applicants who are not within the scope of entities protected by § 72.62.  In addition, the subject matter of this regulatory guide does not c oncern matters dealing with either of the structures, systems and components of an ISFSI or MRS, or the procedures or organization for operating an ISFSI or MRS. Therefore, the matters addressed in this regulatory guide are not within the scope of the backfitting provisions in § 72.62(a)(1) or (2).  
===5. OPERATING ===
PROCEDURES;  
ADMINIS-TRATIVE AND MANAGEMENT
CONTROLS Paragraph
72.31 (a)(5) requires a finding by the staff that the applicant's proposed operating procedures to protect health and to minimize danger to life or property are adequate.


This regulatory guide does not apply to entities protected by issue finality provisions in 10 CFR Part 52 with respect to the matters addressed in this regulatory guide.  Although Part 52 combined license applicants and holders may apply for specific ISFSI licenses, the guidance in this regulatory guide is directed to ISFSI applicants and does not make a distinction between ISFSI applicants who are also combined license applicants or holders and ISFSI applicants who are not combined license applicants and holders, and presents no more onerous guidance for ISFSI applicants who are also combined license applicants or holders versus ISFSI applicants who are not combined license applicants and holders.  Accordingly, the NRC concludes that the staff's use of this regulatory guide is not inconsistent with any Part 52 issue finality provision
Essential to these operating procedures are the applicant's proposed administrative and management controls.


====s.      ====
Guidance on this subject is available in ANSI N299-1976, "Administrative and Managerial Control for the Operation of Nuclear Fuel Reprocessing Plants."*
1 In this section, "licensees" refers to holders of, and the term "applications for, the following: (1) special nuclear material licenses under 10 CFR Part 70; (2) Licenses for independent spent fuel storage installations or monitored retrievable storage installations or certificates of compliance for spent fuel storage cask designs under 10 CFR Part 72; and (3) certificates of compliance or approvals or a compliance plan for gaseous diffusion plants under 10 CFR Part 76.
Although ANSI N299-1976 is designed for the much more complex operating requirements of a fuel reprocessing plant, the basic principles set forth for administrative and managerial controls are considered applicable to the operation of an ISFSI. Paragraph
72.15(a)(8)  
identifies the information that is to be included in the SAR.If the proposed ISFSI is to be operated by the owner, a relatively brief explanation of how the requirements of ANSI N299-1976 will be met may be adequate.


Regulatory Guide 3.50, Revision 2, Page 10
However, if*Copies may be obtained from the American National Standards Institute, Inc., 1430 Broadway, New York, N.Y. 10018.3.50-3 the proposed ISFSI is to be operated by a contractor, con-siderable detail will be required on the working arrangements between the parties involved.
REFERENCES
1  1. U.S. Code of Federal Regulations (CFR), Title 10, "Energy," Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste," U.S. Nuclear Regulatory Commission, Washington, DC.


2. Regulatory Guide (RG) 3.62, "Standard Format and Content for the Safety Analysis Report for Onsite Storage of Spent Fuel Storage Casks," U.S. Nuclear Regulatory Commission, Washington, DC.  3. NUREG-1757, Volume 3, Revision 1"Consolidated Decommissioning Guidance -- Financial Assurance, Recordkeeping, and Timeliness," issued February 2012, U.S. Nuclear Regulatory Commission, Washington, DC.
Particular attention should be placed on the description of the administration of the Independent Review and Audit Program that is identi-fied in ANSI N299-1976.


4. RG 5.55, "Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities," U.S. Nuclear Regulatory Commission, Washington, DC
Chapter
5. RG 3.67, "Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities," U.S. Nuclear Regulatory Commission, Washington, DC.


6. RG 5.54, "Perimeter Intrusion Alarm Systems," U.S. Nuclear Regulatory Commission, Washington, DC.
===6. QUALITY ASSURANCE ===
PROGRAM The quality assurance program required by § 72.80 must be submitted as an enclosure to the application and is briefly discussed in Chapter I I of the SAR. It is sufficient that the license application contain a commitment that the quality assurance program described is (or will be)understood by all involved in its execution and that the program will be implemented, as applicable, for all phases of the project, including any activities important to safety that have been carried out prior to submission of the license application.


7. NUREG-1748, "Environmental Review Guidance fo r Licensing Actions Associated with NMSS Programs," issued August 2003, U.S. Nuclear Regulatory Commission, Washington, DC.
This program should cover the engineering aspects of the site investigation, facility design, procurement, shop fabrica-tion, onsite construction, preoperational testing, conduct of operations, and ultimate decommissioning.


8. International Atomic Energy Agency (IAEA) Safety Guide GS-G-4.1, "Format and Content of the Safety Analysis Report for Nuclear Power Plants," Vienna, Austria, issued April 2004.
The emphasis of this program should be on those activities and items that are identified as being important to safety. The planned quality assurance effort should be commensurate with the importance to safety of such identified activities and items.Chapter 7. OPERATOR TRAINING ISFSI operators are not required to be licensed.


2  9. IAEA Safety Guide SSG-12, "Licensing Process for Nuclear Installations," Vienna, Austria, issued November 2010.
However, they must have a level of qual!ifications and training in subjects and operating procedures applicable to the opera-tion of an ISF SI comparable to the requirements of 10 CFR Part 55 on spent fuel pool operation for licensed operators of a reprocessing plant or nuclear power plant. Appropriate documentation of training activities and certifications of proficiency should be included in the ISFSI records.Subpart I, "Training and Certification of ISFSI Personnel," of 10 CFR Part 72 requires that a training program be established and that the personnel training program document be included as an enclosure to the license application.


10. IAEA Safety Guide SSG-15, "Storage of Spent Nuclear Fuel," Vienna, Austria, issued March 2012.
A brief summary of the program. should be included in the application.


11. CFR, Title 10, "Energy," Part 2, "Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders.
In addition to the specific operating requirements of the planned facility, the training program should also cover the nuclear engineering principles involved in the safe handling and storage of spent fuel and the regulations, regulatory guides, and national standards applicable to ISFSI operations.


12. CFR, Title10, "Energy," Part 50, "Domestic Li censing of Production and Utilization Facilities."
Guidance on the content of the required training program is available from the Fuel and Spent Fuel Licensing Branch, Division of Fuel Cycle and Material Safety, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regu-latory Commission, Washington, D.C. 20555.Chapter


1  Publicly available NRC published documents are available electronically through the NRC Library on the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html  The documents can also be viewed online or printed for a fee in the NRC's Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD.  For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; fax (301) 415-3548; or e-mail pdr.resource@nrc.gov.  2  Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site: www.IAEA.org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400
===8. INVENTORY ===
Vienna, Austria.  Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.org
AND RECORDS REQUIREMENTS
A description of the inventory and records system for the stored fuel should be included in the license application.


Regulatory Guide 3.50, Revision 2, Page 11
Section 72.51 identifies the inventory and record require-ments for spent fuel stored at an ISFSI. Because of the uncertainty as to the ultimate disposition of spent fuel stored in an ISFSI, the records on the identity of each fuel assembly should be complete.
13. CFR, Title 10, "Energy," Part 73, "Physical Protection of Plants and Materials.
 
14. CFR, Title 10, "Energy," Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions."}}
As a minimum, these records should cover: a. Fuel manufacturer, b. Date of manufacture, c. Reactor exposure history, d. Burnup, e. Pertinent observations on discharge and during storage at the reactor, transfer to the ISFSI, and storage in the ISFSI.If storage of consolidated fuel rods is being considered, special requirements concerning inventory and recordkeep- ing for stored fuel pins should be described.
 
Chapter
 
===9. PHYSICAL PROTECTION===
Subpart H, "Physical Protection," of 10 CFR Part 72 requires that a physical security plan (§ 72.81), a design for physical protection
(§ 72.82), and a safeguards contingency plan (§ 72.83) be submitted.
 
Since the details of the provisions for physical protection are withheld from public disclosure, this subject should be covered in separate reports. The license application should contain only a reference to the identity of the reports and when they were submitted.
 
Interim guidance regarding the proposed design for phy-Jc seclrity and the format and content of the physical security plan can be obtained from the Director, Division of Safeguards, Office of Nuclear Material Safety and Safe-guards; U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.Guidance for the safeguards contingency plan is contained in Regulatory Guide 5.55, "Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities." Chapter 1
 
===0. DECOMMISSIONING ===
PLAN Section 72.18 requires the submission of a decommis-sioning plan as part of the license application.
 
A brief description of the decommissioning plan is included in Section 9.6 of the SAR. The license application need contain only a brief summary statement, enough to identify what will be involved and the basis for the estimated costs of decommissioning.
 
However, the financial provisions for carrying out the decommissioning plan at the end of useful life of the proposed ISFSI are not necessarily addressed in the SAR and must be covered in either the license application or the decommissioning plan.Chapter 1
 
===1. EMERGENCY ===
PLAN Section 72.19 requires that an emergency plan be provided as part of the license application.
 
The plan must 3.50-4 include the information listed in Section IV, "Content of Emergency Plans," of Appendix E to 10 CFR Part 50.Chapter 1
 
===2. ENVIRONMENTAL ===
REPORT Section 72.20 requires that an environmental report be provided as part of the license application.
 
Guidance on the format and content of an environmental report for an ISFSI may be found in 10 CFR Part 51, "Licensing and Regulatory Policy and Procedures for Environmental Protection." In the interests of keeping the size of this report within reasonable bounds and its structure and language keyed to the general public, it is recommended that a prospective applicant confer with the NRC staff to obtain definitive guidance on the scope and content of this report.Chapter 13. PROPOSED LICENSE CONDITIONS
License conditions proposed by an applicant constitute a commitment by the applicant to take the actions specified therein. Because a license issued pursuant to Part 72 is issued prior to the commencement of construction, license conditions cover the entire proposed life of the ISFSI, from site selection through the subsequent phases of design, construction, operation, and ultimate decommissioning.
 
License conditions can be considered in two broad categories:
(1) administrative and management organization and controls and (2) technical specifications, Those addressing administrative and management subjects should be covered in the license application;
those addressing technical subjects can be covered very briefly in the license application with appropriate references to Chapter 10 of the SAR. Care should be taken to ensure that such references are clear and explicit.Proposed license conditions should address such subjects as: 1. Administrative and management organization;
proce-dures and controls, including review and approval activities;
and auditing and reporting requirements.
 
In particular, the subject of interfaces between the licensee and its contractors should be covered.2. Verification of design features that are important to safety. In particular, those quality assurance activities that confirm that design and construction are being carried out in accordance with plans, e.g., inspection hold points, should be covered.3. Test procedures throughout the life of the project.Such subjects as conditions applicable to site evaluation, component testing during design and construction, preopera-tional testing prior to startup, and conditions applicable to tests that may be desirable after the commencement of operations should be covered.4. Functional and operating limits of monitoring instru-ments and limiting control settings.5. Limiting conditions of operation.
 
The functional capabilities or performance levels of equipment and systems that are important to safety should be addressed.
 
The subject includes setpoint limits on monitoring instruments and any controls that may need to be imposed on personnel access to any part of the installation.
 
6. Surveillance requirements.
 
Such items as the periodic inspection of cranes and, for water pools, water purity and evidence of corrosion should be covered.3.50-5 VALUE/IMPACT
STATEMENT 1. ACTION
 
===3. PROCEDURAL ===
APPROACH 3.1 Procedural Alternatives
1.1 Description This guide is an updating of the material in -Regulatory Guide 3.24 to correct omissions and reflect regulatory devel-opments since Regulatory Guide 3.24 was issued. Regulatory Guide 3.24 was withdrawn on February 27, 1981 (46 FR 14507).1.2 Need There is increasing interest in the nuclear community in the licensing requirements for the storage of spent fuel in an ISFSI. The guide is designed to assist prospective applicants by discussing in more detail specific requirements of Part 72 for the license application.
 
1.3 Value/Impact
.1.3.1 NRC The further explanation of the content of license applica-tions covering the storage of spent fuel in an ISFSI will be helpful to the licensing staff in their contacts with potential licensees and in the review of these applications when received, particularly during the "mini-review" before docketing of such applications.
 
1.3.2 Other Government Agencies The Tennessee Valley Authority has expressed interest in the storage of spent fuel in an ISFSI and is now trying to determine the applicable licensing requirements.
 
1.3.3 Industry The further explanation of the content of license applica-tions covering the storage of spent fuel in an ISFSI is thought to be particularly useful to the utilities, which deal primarily with the NRC Office of Nuclear Reactor Regula-tion and which now will be dealing with the NRC Office of Nuclear Material Safety and Safeguards, which handles the licensing of spent fuel storage in an ISFSI and operates somewhat differently.
 
1.3.4 Public There is a need to aid the public in becoming better informed on the various aspects of the licensing of spent fuel storage in an ISFSI. The guide will contribute to meeting this need.
 
===2. TECHNICAL ===
APPROACH The guide is nontechnical in its content.The following are potential NRC procedures that may be used to disseminate the information contained in the guide:* Regulation
* Regulatory guide* Branch position paper* NUREG-series report 3.2 Value/Impact of Procedural Alternatives A regulation is not a suitable means of disseminating the explanatory type of information contained in the proposed guide. A NUREG-series report is also not a viable alternative because the proposed guide contains regulatory positions.
 
Only a regulatory guide or branch position paper are considered to be viable alternatives.
 
Branch positions are sometimes presented for guidance of this sort. However, because of the limited distribution within NRC for concurrence, branch positions should be formalized by the issuance of a. regulatory guide. In this case, no branch position has been prepared or is anticipated.
 
3.3 Decision on Procedural Approach* A regulatory guide should be prepared.
 
===4. STATUTORY ===
CONSIDERATIONS
4.1 NRC Authority Authority for this guide is derived from the Atomic Energy Act of 1954, as amended, and the Energy Reorganiza- tion Act of 1974, as amended, and implemented through the Commission's regulations.
 
4.2 Need for NEPA Assessment The action is not a major Federal action as defined by 10 CFR 51(a)(10)
and does not require an environmental impact statement.
 
===5. RELATIONSHIP ===
TO OTHER EXISTING OR PROPOSED REGULATIONS
OR POLICIES The guide is one of a series of guides that will replace Regulatory Guide 3.24, Other guides in this series include Regulatory Guide 3.44, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)"; Regulatory
3.50-6 Guide 3.48, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)";
and Regulatory Guide 3.49,"Design of an Independent Spent Fuel Storage Installation (Water-Basin Type)." 6. SUMMARY AND CONCLUSIONS
The regulatory guide should be issued to meet a current need in the written development of the regulatory bases for the licensing of spent fuel storage in an ISFSI.3.50-7 UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, 0. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORy COMMISSION
120 9550,5 5 466 1 op (IS NPC ofCm P 7-G GY SHUTTL EWD:TH A P rf3 W ASH! NG Tr-N oC 2r955}}


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Revision as of 20:11, 17 September 2018

Guidance on Preparing a License Application to Store Spent Fuel in an Independent Spent Fuel Storage Installation
ML13038A424
Person / Time
Issue date: 01/31/1982
From:
Office of Nuclear Regulatory Research
To:
References
TASK FP 907-4 RG-3.050
Download: ML13038A424 (8)


U.S. NUCLEAR REGULATORY

COMMISSION

January 1982 0 REGULATORY

GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 3.50 (Task FP 907-4)GUIDANCE ON PREPARING

A LICENSE APPLICATION

TO STORE SPENT FUEL IN AN INDEPENDENT

SPENT FUEL STORAGE INSTALLATION

INTRODUCTION

Subpart B, "License Application, Form, and Contents," of 10 CFR Part 72, "Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation," specifies the information to be covered in an application for a license to store spent fuel in an independent spent fuel storage installation (ISFSI).However, Part 72 does not specify the format to be followed in the license application.

This regulatory guide suggests a format acceptable to the NRC staff for submitting the information specified in Part 72 for a license application to store spent fuel in an ISFSI.Other regulations applicable to the licensing of spent fuel storage in an ISFSI are in the following parts of Title 10,"Energy," of the Code of Federal Regulations:

2 -Rules of Practice for Domestic Licensing Proceedings

8 -Interpretations

9 -Public Records 11 -Criteria and Procedures for Determining Eligibility for Access to or Control over Special Nuclear Material 19 -Notices, Instructions and Reports to Workers;Inspections.

20 -Standards for Protection against Radiation

-21 -Reporting of Defects and Noncompliance

25 -Access Authorization for Licensee Personnel 51 -Licensing and Regulatory Policy and Procedures for Environmental Protection

73 -Physical Protection of Plants and Materials 75 -Safeguards on Nuclear Material-Implementation of US/IAEA Agreement 95 -Security Facility Approval and Safeguarding of National Security Information and Restricted Data 150 -Exemptions and Continued Regulatory Authority in Agreement States and in Offshore Waters under Section 274 170 -Fees for Facilities and Materials Licenses and other Regulatory Services under the Atomic Energy Act of 1954, as Amended.Part 72 provides for a single licensing procedure.

The smooth functioning of this one-step licensing procedure requires that the license application be essentially complete in its initial submission.

A license under this part will be issued before the start of construction of any physical facilities involved.

Under this procedure, the final design details of those ISFSI components, systems, and structures that are important to safety must be available for review and evaluation.

Part 72 also requires that a site evaluation be provided to ensure that the natural characteristics of the site and its environs are sufficiently known and have been factored into the engineering design of the installation.

The document in which this information is presented is a Safety Analysis Report (SAR).Although an applicant may plan to contract with another organization for the design, construction, and possibly the operation of the proposed ISFSI, a licensee under Part 72 cannot delegate to a contractor the responsibility for meeting all applicable regulatory requirements.

This means that the applicant must make a commitment that, as the licensee, it will have an adequate staff to ensure that regulatory requirements are met at each stage of the proposed project. If the applicant plans to contract with another organization for the operation of the proposed ISFSI, the contractual arrangements must be described in the license application.

Any subsequent changes in such contractual arrangements may require an amendment to the license.This guide represents a standard format that is acceptable to the NRC staff for the license application.

Conformance with this guide, however, is not mandatory.

License applica-tions with different formats will be acceptable to the staff if they provide an adequate basis for the findings required for the issuance of a license. However, because it may be USNRC REGULATORY

GUIDES Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specific parts -of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents, or to provide guidance to applicants.

Regulatory Guides are not substitutes for regulations, and compliance with them is not required.

Methods and solutions different from those set out in the guides will be acceptable If they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.

This guide was Issued after consideration of comments received from the Public. Comments and suggestions for improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa-tion or experience.

Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:

Docketing and Service Branch.The guides are issued in the following ten broad divisions:

1. Power Reactors 6. Products 2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection

10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:

Publications Sales Manager.

more difficult to locate needed information, the staff review time may be longer, and there is a greater likelihood that the staff may regard the license application as incomplete.

As experience is gained in the licensing of spent fuel storage, the Commission's requirements for information needed in its review of applications for licenses to store spent fuel in an ISFSI may change. Revisions of the Commis-sion's needs for information in connection with such licensing actions will be conveyed to the industry and the public by (1) amendments to NRC regulations, (2) revisions to this regulatory guide, (3) issuance of new or revised regulatory guides, and (4) direct communications, as needed, with an applicant by the NRC staff.Since the preparation of a license application pursuant to Part 72 will be a new experience, prospective applicants are encouraged to meet with representatives of the Division of Fuel Cycle and. Material Safety of the Office of Nuclear Material Safety and Safeguards during the development of a license application to resolve any problems that may arise.An early resolution of potential problems is beneficial to all concerned with the licensing process.Contents of the License Application The license application is the basic document that must address each of the requirements of Part 72 and must be complete in itself. However, the following subjects should be covered in separate reports that are identified as enclosures to the license application, and the contents of each report should be summarized in a brief statement in the license application:

1. Safety Analysis Report 2. Decommissioning Plan 3. Emergency Plan 4. Environmental Report 5. Quality Assurance Program 6. Physical Security Plan 7. Safeguards Contingency Plan 8. Personnel Training Program 9. Proposed License Conditions, including Technical Specifications

10. Design for Physical Security Format and Style The applicant should strive for clear, concise presentation of the information provided in the application.

The applica-tion should be written in plain English and should be understandable to an educated lay person.Abbreviations should be consistent throughout the license application and its enclosures.

Any abbreviations, symbols, or special terms unique to the proposed activity or not in general use should be defined when they first appear.A title page identifying key individuals responsible for the preparation of the license application and the oath required under paragraph

72.11(b) should be included.

A table of contents should also be included.Physical Specifications

1. Paper size: 8h x I Iinches 2. Paper stock and ink: Suitable quality in substance, paper color, and ink density for handling and reproduction by microfilming or image-cbpying equipment.

3. Paper margins: A margin of no less than 1 inch should be maintained on the top, bottom, and binding side of all pages.4. Printing: a. Composition:

Text should be single or 11/2 spaced.b. Type face and style: Suitable for microfilming or image-copying equipment.

c. Reproduction:

Either mechanical or photographic.

Text should be printed on both sides of the paper with the image printed head to head.5. Binding: Pages. should be punched for a standard 3-hole loose-leaf binder.6. Chapter and page numbering:

Each requirement of the regulation addressed should be shown as a separate chapter with the same number as the chapter given in this guide, e.g., Chapter 8, "Operator Training." Pages should be numbered sequentially in each chapter, e.g., 8-1, 8-2, etc.Do not number the entire document sequentially.

Procedures for Updating or Revising Pages All pages submitted to update, revise, or add to the license application should. show the date of change and a change or amendment number. The changed or revised portion of each page should be highlighted by a "change indicator" mark consisting of a bold vertical line drawn in the margin opposite the binding side.Referenced Materials Caution should be used in references to information previously filed with the AEC or NRC. Such references must be pertinent to the subject discussed, must contain current information, and must be readily obtainable or extractable from the referenced documents.

It may be more efficient in some cases to repeat in a license application previously furnished information.

Chapter 1. GENERAL AND FINANCIAL

INFORMATION

The license application should address the requirements of § 72.14 of 10 CFR Part 72 regarding details on the identity of an applicant.

If the applicant is other than the owner or planned operator of the proposed ISFSI, details of the working and contractual arrangements between all parties involved should be set forth. Any information on such matters considered as proprietary information by the applicant should be identified and submitted under separate 3.50-2 cover. The procedures in 10 CFR 2.790(b) should be followed.If the proposed ISFSI is to be built on the site of another licensed activity or facility such as a nuclear power plant, details of the working arrangements and responsibilities of the licensees involved should be stated. Similarly, if unlicensed activities are carried out at the proposed site, any potential interactions between the proposed ISFSI and these other site activities should be explained.

Paragraph

72.14(e) specifically addresses the required financial information that must be submitted with the application.

If the applicant is a government agency or a regulated utility, the assumption is made that the applicant is financially qualified for a license under Part 72. If the applicant is a corporation organized for the specific purpose of owning and operating the proposed ISFSI, details of its organizational structure, including the responsibilities of its members to meet the financial requirements of the proposed ISFSI throughout its proposed operating life and ultimate decommissioning, must be stated. This requirement is applicable even if the proposed ISFSI is to be owned and operated by a consortium of utilities.

Chapter

2. TECHNICAL

QUALIFICATIONS

Paragraph

72.31 (a)(4) and § 72.17 require a finding by the staff that the applicant is qualified by training and experience to construct and operate an ISFSI.Although spent fuel storage in an ISFSI is generally considered a relatively low-risk operation compared to some other types of nuclear activities, the design, construc-tion, and operation of an ISFSI require certain skills and an understanding of the requirements involved to ensure that the objective of a relatively low-risk operation is achieved in practice.

The license application should contain a commit-ment that the applicant will staff the project with an adequate cadre of personnel possessing the required skills throughout all phases of the project. This element of the license. application is in addition to the discussion of the conduct of operations covered in Chapter 9 of the SAR.The licensee is responsible for the execution of the proposed project as described in the license application.

This means that, even though much of the actual work involved during the site selection, design, procurement, con-struction, and even the operating phases of the project may be performed by a contractor, the licensee must have a staff that is knowledgeable in all aspects of the project. If such a staff does not actually exist, the applicant should describe the staffing plans in sufficient detail to support the finding required by paragraph

72.3 l(a)(4).Chapter

3. TECHNICAL

INFORMATION;

SAFETY ANALYSIS REPORT As required by § 72.15, the technical information is presented in the SAR, which should be submitted as an enclosure to the license application.

A summary statement identifying the type of installation proposed (e.g., a water basin), its design capacity, any unique features incorporated in its design, and its mode of operation is adequate for the license application document.The SAR required for an ISFSI differs from the SARs for some other nuclear facilities in that the initial SAR is expected *to be complete and comparable in scope and detail to the final. SAR for facilities licensed under 10 CFR Part 50. Section 72.15 identifies the minimum information that is required to be included in the SAR. Although§ 72.50 provides for the subsequent updating of the SAR, such changes during the design and construction phases of the project are expected to be of minor importance.

Any of these changes deemed significant by the staff may cause delay in the granting of the final clearance to receive spent fuel.Guidance on the preparation of the SAR for an ISFSI of the conventional water-basin type is contained in Regulatory Guide 3.44, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)." For the dry storage ISFSI, guidance on the preparation of the SAR is contained in Regulatory Guide 3.48, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)." Chapter

4. CONFORMITY

TO GENERAL DESIGN CRITERIA Subpart F of 10 CFR Part 72 contains the general design criteria for an ISFSI. The subject of conformity to the genera- design. criteria o.i .overed in tala 11- the C A r3. II *sufficient that the license application contain a summary discussion of each criterion and reference where more detailed information on a specific subject can be found in the SAR.Chapter

5. OPERATING

PROCEDURES;

ADMINIS-TRATIVE AND MANAGEMENT

CONTROLS Paragraph

72.31 (a)(5) requires a finding by the staff that the applicant's proposed operating procedures to protect health and to minimize danger to life or property are adequate.

Essential to these operating procedures are the applicant's proposed administrative and management controls.

Guidance on this subject is available in ANSI N299-1976, "Administrative and Managerial Control for the Operation of Nuclear Fuel Reprocessing Plants."*

Although ANSI N299-1976 is designed for the much more complex operating requirements of a fuel reprocessing plant, the basic principles set forth for administrative and managerial controls are considered applicable to the operation of an ISFSI. Paragraph

72.15(a)(8)

identifies the information that is to be included in the SAR.If the proposed ISFSI is to be operated by the owner, a relatively brief explanation of how the requirements of ANSI N299-1976 will be met may be adequate.

However, if*Copies may be obtained from the American National Standards Institute, Inc., 1430 Broadway, New York, N.Y. 10018.3.50-3 the proposed ISFSI is to be operated by a contractor, con-siderable detail will be required on the working arrangements between the parties involved.

Particular attention should be placed on the description of the administration of the Independent Review and Audit Program that is identi-fied in ANSI N299-1976.

Chapter

6. QUALITY ASSURANCE

PROGRAM The quality assurance program required by § 72.80 must be submitted as an enclosure to the application and is briefly discussed in Chapter I I of the SAR. It is sufficient that the license application contain a commitment that the quality assurance program described is (or will be)understood by all involved in its execution and that the program will be implemented, as applicable, for all phases of the project, including any activities important to safety that have been carried out prior to submission of the license application.

This program should cover the engineering aspects of the site investigation, facility design, procurement, shop fabrica-tion, onsite construction, preoperational testing, conduct of operations, and ultimate decommissioning.

The emphasis of this program should be on those activities and items that are identified as being important to safety. The planned quality assurance effort should be commensurate with the importance to safety of such identified activities and items.Chapter 7. OPERATOR TRAINING ISFSI operators are not required to be licensed.

However, they must have a level of qual!ifications and training in subjects and operating procedures applicable to the opera-tion of an ISF SI comparable to the requirements of 10 CFR Part 55 on spent fuel pool operation for licensed operators of a reprocessing plant or nuclear power plant. Appropriate documentation of training activities and certifications of proficiency should be included in the ISFSI records.Subpart I, "Training and Certification of ISFSI Personnel," of 10 CFR Part 72 requires that a training program be established and that the personnel training program document be included as an enclosure to the license application.

A brief summary of the program. should be included in the application.

In addition to the specific operating requirements of the planned facility, the training program should also cover the nuclear engineering principles involved in the safe handling and storage of spent fuel and the regulations, regulatory guides, and national standards applicable to ISFSI operations.

Guidance on the content of the required training program is available from the Fuel and Spent Fuel Licensing Branch, Division of Fuel Cycle and Material Safety, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regu-latory Commission, Washington, D.C. 20555.Chapter

8. INVENTORY

AND RECORDS REQUIREMENTS

A description of the inventory and records system for the stored fuel should be included in the license application.

Section 72.51 identifies the inventory and record require-ments for spent fuel stored at an ISFSI. Because of the uncertainty as to the ultimate disposition of spent fuel stored in an ISFSI, the records on the identity of each fuel assembly should be complete.

As a minimum, these records should cover: a. Fuel manufacturer, b. Date of manufacture, c. Reactor exposure history, d. Burnup, e. Pertinent observations on discharge and during storage at the reactor, transfer to the ISFSI, and storage in the ISFSI.If storage of consolidated fuel rods is being considered, special requirements concerning inventory and recordkeep- ing for stored fuel pins should be described.

Chapter

9. PHYSICAL PROTECTION

Subpart H, "Physical Protection," of 10 CFR Part 72 requires that a physical security plan (§ 72.81), a design for physical protection

(§ 72.82), and a safeguards contingency plan (§ 72.83) be submitted.

Since the details of the provisions for physical protection are withheld from public disclosure, this subject should be covered in separate reports. The license application should contain only a reference to the identity of the reports and when they were submitted.

Interim guidance regarding the proposed design for phy-Jc seclrity and the format and content of the physical security plan can be obtained from the Director, Division of Safeguards, Office of Nuclear Material Safety and Safe-guards; U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.Guidance for the safeguards contingency plan is contained in Regulatory Guide 5.55, "Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities." Chapter 1

0. DECOMMISSIONING

PLAN Section 72.18 requires the submission of a decommis-sioning plan as part of the license application.

A brief description of the decommissioning plan is included in Section 9.6 of the SAR. The license application need contain only a brief summary statement, enough to identify what will be involved and the basis for the estimated costs of decommissioning.

However, the financial provisions for carrying out the decommissioning plan at the end of useful life of the proposed ISFSI are not necessarily addressed in the SAR and must be covered in either the license application or the decommissioning plan.Chapter 1

1. EMERGENCY

PLAN Section 72.19 requires that an emergency plan be provided as part of the license application.

The plan must 3.50-4 include the information listed in Section IV, "Content of Emergency Plans," of Appendix E to 10 CFR Part 50.Chapter 1

2. ENVIRONMENTAL

REPORT Section 72.20 requires that an environmental report be provided as part of the license application.

Guidance on the format and content of an environmental report for an ISFSI may be found in 10 CFR Part 51, "Licensing and Regulatory Policy and Procedures for Environmental Protection." In the interests of keeping the size of this report within reasonable bounds and its structure and language keyed to the general public, it is recommended that a prospective applicant confer with the NRC staff to obtain definitive guidance on the scope and content of this report.Chapter 13. PROPOSED LICENSE CONDITIONS

License conditions proposed by an applicant constitute a commitment by the applicant to take the actions specified therein. Because a license issued pursuant to Part 72 is issued prior to the commencement of construction, license conditions cover the entire proposed life of the ISFSI, from site selection through the subsequent phases of design, construction, operation, and ultimate decommissioning.

License conditions can be considered in two broad categories:

(1) administrative and management organization and controls and (2) technical specifications, Those addressing administrative and management subjects should be covered in the license application;

those addressing technical subjects can be covered very briefly in the license application with appropriate references to Chapter 10 of the SAR. Care should be taken to ensure that such references are clear and explicit.Proposed license conditions should address such subjects as: 1. Administrative and management organization;

proce-dures and controls, including review and approval activities;

and auditing and reporting requirements.

In particular, the subject of interfaces between the licensee and its contractors should be covered.2. Verification of design features that are important to safety. In particular, those quality assurance activities that confirm that design and construction are being carried out in accordance with plans, e.g., inspection hold points, should be covered.3. Test procedures throughout the life of the project.Such subjects as conditions applicable to site evaluation, component testing during design and construction, preopera-tional testing prior to startup, and conditions applicable to tests that may be desirable after the commencement of operations should be covered.4. Functional and operating limits of monitoring instru-ments and limiting control settings.5. Limiting conditions of operation.

The functional capabilities or performance levels of equipment and systems that are important to safety should be addressed.

The subject includes setpoint limits on monitoring instruments and any controls that may need to be imposed on personnel access to any part of the installation.

6. Surveillance requirements.

Such items as the periodic inspection of cranes and, for water pools, water purity and evidence of corrosion should be covered.3.50-5 VALUE/IMPACT

STATEMENT 1. ACTION

3. PROCEDURAL

APPROACH 3.1 Procedural Alternatives

1.1 Description This guide is an updating of the material in -Regulatory Guide 3.24 to correct omissions and reflect regulatory devel-opments since Regulatory Guide 3.24 was issued. Regulatory Guide 3.24 was withdrawn on February 27, 1981 (46 FR 14507).1.2 Need There is increasing interest in the nuclear community in the licensing requirements for the storage of spent fuel in an ISFSI. The guide is designed to assist prospective applicants by discussing in more detail specific requirements of Part 72 for the license application.

1.3 Value/Impact

.1.3.1 NRC The further explanation of the content of license applica-tions covering the storage of spent fuel in an ISFSI will be helpful to the licensing staff in their contacts with potential licensees and in the review of these applications when received, particularly during the "mini-review" before docketing of such applications.

1.3.2 Other Government Agencies The Tennessee Valley Authority has expressed interest in the storage of spent fuel in an ISFSI and is now trying to determine the applicable licensing requirements.

1.3.3 Industry The further explanation of the content of license applica-tions covering the storage of spent fuel in an ISFSI is thought to be particularly useful to the utilities, which deal primarily with the NRC Office of Nuclear Reactor Regula-tion and which now will be dealing with the NRC Office of Nuclear Material Safety and Safeguards, which handles the licensing of spent fuel storage in an ISFSI and operates somewhat differently.

1.3.4 Public There is a need to aid the public in becoming better informed on the various aspects of the licensing of spent fuel storage in an ISFSI. The guide will contribute to meeting this need.

2. TECHNICAL

APPROACH The guide is nontechnical in its content.The following are potential NRC procedures that may be used to disseminate the information contained in the guide:* Regulation

  • Regulatory guide* Branch position paper* NUREG-series report 3.2 Value/Impact of Procedural Alternatives A regulation is not a suitable means of disseminating the explanatory type of information contained in the proposed guide. A NUREG-series report is also not a viable alternative because the proposed guide contains regulatory positions.

Only a regulatory guide or branch position paper are considered to be viable alternatives.

Branch positions are sometimes presented for guidance of this sort. However, because of the limited distribution within NRC for concurrence, branch positions should be formalized by the issuance of a. regulatory guide. In this case, no branch position has been prepared or is anticipated.

3.3 Decision on Procedural Approach* A regulatory guide should be prepared.

4. STATUTORY

CONSIDERATIONS

4.1 NRC Authority Authority for this guide is derived from the Atomic Energy Act of 1954, as amended, and the Energy Reorganiza- tion Act of 1974, as amended, and implemented through the Commission's regulations.

4.2 Need for NEPA Assessment The action is not a major Federal action as defined by 10 CFR 51(a)(10)

and does not require an environmental impact statement.

5. RELATIONSHIP

TO OTHER EXISTING OR PROPOSED REGULATIONS

OR POLICIES The guide is one of a series of guides that will replace Regulatory Guide 3.24, Other guides in this series include Regulatory Guide 3.44, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)"; Regulatory

3.50-6 Guide 3.48, "Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)";

and Regulatory Guide 3.49,"Design of an Independent Spent Fuel Storage Installation (Water-Basin Type)." 6. SUMMARY AND CONCLUSIONS

The regulatory guide should be issued to meet a current need in the written development of the regulatory bases for the licensing of spent fuel storage in an ISFSI.3.50-7 UNITED STATES NUCLEAR REGULATORY

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