ML12087A035

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Draft Regulatory Guide DG-3042, (Proposed Revision 2 of Regulatory Guide 3.50, Dated September 1989), Standard Format and Content for a License Application for an Independent Spent Fuel Storage Installation or a Monitored Retrievable Storag
ML12087A035
Person / Time
Issue date: 11/18/2013
From: Bernie White
Office of Nuclear Material Safety and Safeguards
To:
Parks J
Shared Package
ML12087A030 List:
References
DG-3042 RG-3.005, Rev. 1
Download: ML12087A035 (11)
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Text

U.S. NUCLEAR REGULATORY COMMISSION January 2014 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 3 DRAFT REGULATORY GUIDE

Contact:

J. Goshen (301) 287-9250 DRAFT REGULATORY GUIDE DG-3042 (Proposed Revision 2 of Regulatory Guide 3.50, dated September 1989)

STANDARD FORMAT AND CONTENT FOR A LICENSE APPLICATION FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION OR A MONITORED RETRIEVABLE STORAGE FACILITY A. INTRODUCTION 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 applications for independent spent fuel storage installations (ISFSIs) and monitored retrievable storage (MRS) facilities.

Applicable Rules and Regulations The regulations established by the NRC in Title 10 of the Code of Federal Regulations, Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste (10 CFR Part 72) (Ref. 1), Subpart B, License Application, Form, and Contents, specifies the information that must be in an application 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.

Related Guidance

  • Regulatory Guide (RG) 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 This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this area. It has not received final staff review or approval and does not represent an official NRC final staff position.

Public comments may be submitted through the federal government rulemaking Web site at http://www.regulations.gov.

Alternatively, written comments may be submitted to the Rules, Announcements, and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or faxed to 301-492-3446. Comments must be submitted by January 24, 2014.

Electronic copies of this draft regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/. The draft regulatory guides is available through NRCs Agencywide Document Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html., under Accession No. ML12087A035. The regulatory analysis may be found in ADAMS under Accession No. ML12087A039.

  • 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.
  • Regulatory Guide 1.101, Emergency Response Planning and Preparedness for Nuclear Power Reactors, (Ref. 5), although it does not specifically address ISFSIs, contains information that could be useful to develop the Emergency Plan for a site-specific ISFSI.
  • NUREG-1748, Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, (Ref. 6), provides format and technical content information for environmental reports which are required by 10 CFR 72.34.

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 agencys 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 for the findings required for the issuance or continuance of a permit or license by the Commission.

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.

B. DISCUSSION 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.

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. The guide was revised in September 1989 (Revision 1) to include MRSs 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 DG-3042, Page 2

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 Spent Fuel Storage Installation (Water-Basin Type), and 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 of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste.

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. 7). This document specifically describes format and content for Safety Analysis Reports (SARs) for nuclear plants, but does not cover spent fuel storage facilities. IAEA Safety Guide SSG-12, Licensing Process for Nuclear Installations (Ref. 8) 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. 9) 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.

C. STANDARD FORMAT AND CONTENT This regulatory guide suggests 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. 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 must address each of the requirements of 10 CFR Part 72 and should be complete 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:
  • Proposed technical specifications (see 10 CFR 72.26 and regulatory Guide 3.62),

DG-3042, Page 3

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 (see 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.

DG-3042, Page 4

Applications that do not contain the information described in the regulations may be rejected for review by the NRC.

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 NRCs Web site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to MSHD.Resource@nrc.gov; or by writing to the Office of Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

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 project manager.

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.

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 repeat, or summarize, information furnished in the previously submitted document.

DG-3042, Page 5

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. 10) 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.

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.

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.

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 the previously 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. 11), 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.

Physical Protection Plan As discussed in 10 CFR 72.24(o), as part of the licensing process, the applicant must submit either 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.

DG-3042, Page 6

The 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. 12).

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 event 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 Regulatory Guide 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 statement of the bases of and justifications for these technical specifications. For more information on technical specifications, please review Regulatory Guide 3.62.

Technical Qualifications The regulation at 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: Applicants 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 knowledgeable in all aspects of the project.

The application should include the applicants experience to show that it has the technical qualifications to construct and operate (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.

DG-3042, Page 7

Decommissioning Plan and Decommissioning Funding Plan The proposed final decommissioning plan should include all the criteria discussed in 10 CFR 72.54(2)(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 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 ISFSIs 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 allocated 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. 13), Subpart A, National Environmental Policy ActRegulations 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 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.

D. IMPLEMENTATION The purpose of this section is to provide information on how applicants and licensees1 may use this regulatory guide and information regarding the NRC staffs plans for using this guide. In addition, it describes how the NRC staff has complied with the Backfit Rule, 10 CFR 72.62.

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.

DG-3042, Page 8

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 reduces 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.

This regulatory guide applies only to future applicants, who are not within the scope of entities protected by § 72.62. In addition, the subject matter of this regulatory guide does not concern matters dealing with either 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 draft regulatory guide are not within the scope of the backfitting provisions in § 72.62(a)(1) or (2). 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 are directed to ISFSI applicants and does not make a distinction between, 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 this draft regulatory guide, if finalized, would not be inconsistent with any part 52 issue finality provisions.

DG-3042, Page 9

REFERENCES1

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 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 1Consolidated Decommissioning Guidance -- Financial Assurance, Recordkeeping, and Timeliness, issued February 2012, U.S. Nuclear Regulatory Commission, Washington, DC.
4. Regulatory Guide 5.55, Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities, U.S. Nuclear Regulatory Commission, Washington, DC.
5. Regulatory Guide 1.101, Emergency Response Planning and Preparedness for Nuclear Power Reactors, U.S. Nuclear Regulatory Commission, Washington, DC.
6. NUREG-1748, Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, issued August 2003, U.S. Nuclear Regulatory Commission, Washington, DC.
7. 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 2004.2
8. International Atomic Energy Agency (IAEA) Safety Guide SSG-12, Licensing Process for Nuclear Installations, Vienna, Austria, issued November 2010.
9. International Atomic Energy Agency (IAEA) Safety Guide SSG-15, Storage of Spent Nuclear Fuel, Vienna, Austria, issued March 2012.
10. U.S. Code of Federal Regulations (CFR), Title 10, Energy, Part 2, Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders.
11. U.S. Code of Federal Regulations (CFR), Title10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities.
12. U.S. Code of Federal Regulations (CFR), Title 10, Energy, Part 73, Physical Protection of Plants and Materials.

1 Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and the NRCs 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 NRCs 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 Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.org DG-3042, Page 10

13. U.S. Code of Federal Regulations (CFR), Title 10, Energy, Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.

DG-3042, Page 11

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