U.S. NUCLEAR REGULATORY COMMISSION February 1983

Revision 1

REGULATORY GUIDE 

OFFICE OF NUCLEAR REGULATORY RESEARCH 

REGULATORY GUIDE 5.59 

(Task SG 229-4) 

STANDARD FORMAT AND CONTENT 

FOR A LICENSEE PHYSICAL SECURITY PLAN 

FOR THE PROTECTION OF SPECIAL NUCLEAR MATERIAL 

OF MODERATE OR LOW STRATEGIC SIGNIFICANCE 

The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable 

for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating specific problems 

or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. 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. 

This guide was issued after consideration of comments received from the public. 

Regulatory guides are issued in 10 broad divisions: 1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials 

Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 

9, Antitrust and Financial Review; and 10, General. 

Electronic copies 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’s Electronic Reading Room at 

http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s Agencywide Documents Access and Management 

System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML003739253. 
Rev. 1 of RG-5.59, Page 2 

TABLE OF CONTENTS 

Page

Introduction ................................................................................................................................................... 5 

Part I Special Nuclear Material of Moderate Strategic Significance ................................................ 11 

1. Use and Storage Area at a Fixed Site ............................................................................................. 11 

1.1 Area Where Material is Used [73.67(d)(1)] ...................................................................... 11 

1.2 Area Where Material Is Stored [73.67(d)(2)] ................................................................... 13 

2. Detection Devices and Procedures at a Fixed Site ......................................................................... 16 

2.1 Earliness of Detection [73.67(a)] ...................................................................................... 16

2.2 Detection Through Monitoring Controlled Access Areas [73.67(d)(3)] .......................... 17 

3. Access Control at a Fixed Site ....................................................................................................... 18 

3.1 Preauthorization Screening [73.67(d)(4)] ......................................................................... 18 

3.2 Badging System [73.67(d)(5)] .......................................................................................... 19 

3.3 Lock System [73.67(d)(5)]................................................................................................ 20 

3.4 Personnel Entry Control System [73.67(d)(6)] ................................................................. 20 

3.5 Escort System [73.67(d)(7)] ............................................................................................. 21 

3.6 Search [73.67(d)(10)] ........................................................................................................ 21 

4. Security Organization at a Fixed Site ............................................................................................ 22 

5. Communications at a Fixed Site .................................................................................................... 23 

6. Response Procedures at a Fixed Site.............................................................................................. 24 

7. Material Transportation Requirements .......................................................................................... 24 

7.1 Advance Notification to Receiver [73.67(e)(11(1)] .......................................................... 25 

7.2 Receiver Confirmation [73.67(e)(1)(ii)] ........................................................................... 25 

7.3 Inspection [73.67(e)(1)(iii)] .............................................................................................. 25 

7.4 Responsibility for In-Transit Physical Protection [73.67(e)(1)(iv)] ................................. 26 

8. Receiver Requirements--Transportation ........................................................................................ 26 

8.1 Inspection [73.67(e)(2)(i)] ................................................................................................ 26 

8.2 Notification to Shipper [73.67(e)(2)(ii)] ........................................................................... 27 

8.3 Responsibility for In-Transit Physical Protection [73.57(e)(2)(iii)] ................................. 27 

9. In-Transit Physical Protection Requirements ................................................................................ 27 

9.1 Communications [73.67(e)(3)(i)] ...................................................................................... 28 

9.2 Minimum Transit Times [73.67(e)(3)(ii)] ......................................................................... 29 

9.3 Preauthorization Screening [73.67(e)(3)(iii)] ................................................................... 29 
Rev. 1 of RG-5.59, Page 3 

9.4 Response Procedures [73.67(e)(3)(iv)] ............................................................................. 30 

9.5 Notification [73.67(e)(3)(v)] ............................................................................................. 30 

9.6 Lost Material Notification [73.67(e)(3)(vi)] ..................................................................... 30 

9.7 NRC Notification [73.67(e)(3)(vii)] ................................................................................. 31 

10. Transfer and Control Requirements ............................................................................................... 31 

10.1 Carrier Transfers [73.67(e)(4)(i)] ...................................................................................... 31 

10.2 Control of Shipments [73.67(e)(4)(ii)] ............................................................................. 32 

11. Export Requirements ..................................................................................................................... 33 

12. Import Requirements ..................................................................................................................... 33 

12.1 Security Requirements [73.67(e)(6)(i)] ............................................................................ 33 

12.2 Notification [73.67(e)(6)(ii)]............................................................................................. 34 

13. Orders To Delay SSNM Shipments ............................................................................................... 34 

13.1 Notification of Receipt of SSNM [73.67(e)(7)(ii)] ........................................................... 36 

Part II Special Nuclear Material of Low Strategic Significance ........................................................ 37 

1. Use and Storage Area at a Fixed Site ............................................................................................. 37 

1.1 Areas for Use and Temporary Storage [73.67(f)(1)] ........................................................ 37 

1.2 Areas for Permanent Storage [73.67(f)(1)] ....................................................................... 39 

2. Detection Devices and Procedures at a Fixed Site ......................................................................... 40 

2.1 Earliness of Detection [73.67(a)] ...................................................................................... 40

2.2 Monitoring Controlled Access Areas [73.67(f)(2)] .......................................................... 41 

3. Security Response at a Fixed Site .................................................................................................. 45 

4. Response Procedures at a Fixed Site.............................................................................................. 46 

5. Material Transportation Requirements .......................................................................................... 46 

5.1 Advance Notification [73.67(g)(1)(i)] .............................................................................. 47 

5.2 Receiver Confirmation [73.67(g)(1)(ii)] ........................................................................... 47 

5.3 Container [73.67(g)(1)(iii)] ............................................................................................... 47 

5.4 Inspection [73.67(g)(1)(iv)] .............................................................................................. 48 

5.5 Responsibility for In-Transit Physical Protection [73.67(g)(1)(v)] .................................. 48 

6. Receiver Requirements—Transportation ....................................................................................... 48 

6.1 Inspection [73.67(g)(2)(i)] ................................................................................................ 49 

6.2 Notification [73.67(g)(2)(ii)] ............................................................................................ 49 

6.3 Responsibility for In-Transit Physical Protection [73.67(g)(2)(iii)] ................................. 49 
Rev. 1 of RG-5.59, Page 4 

7. In-Transit Physical Protection Requirements ................................................................................ 49 

7.1 Response Procedures [73.67(g)(3)(i)] ............................................................................... 50 

7.2 Notification [73.67(g)(3)(ii)] ............................................................................................ 50 

7.3 Lost Material Notification [73.67(g)(3)(iii)] ..................................................................... 51 

8. Export Requirements ..................................................................................................................... 51 

9. Import Requirements ..................................................................................................................... 51 

9.1 Security Requirements [73.67(g)(5)(i)] ............................................................................ 51 

9.2 Notification [73.67(g)(5)(ii)] ............................................................................................ 52 

VALUE/IMPACT STATEMENT .............................................................................................................. 52 
Rev. 1 of RG-5.59, Page 5 

INTRODUCTION 

The Atomic Energy Act of 1954, as amended, directed the U.S. Atomic Energy Commission 

(AEC) to regulate the receipt, manufacture, production, transfer, possession, use, import, and export of 

special nuclear material (SNM) in order to protect the public health and safety and to provide for the 

common defense and security. The Energy Reorganization Act of 1974 transferred all the licensing and 

related regulatory functions of the AEC to the Nuclear Regulatory Commission (NRC). 

The principal requirements with respect to the physical protection of licensed activities against 

industrial sabotage and with respect to the physical protection of special nuclear material in transit are 

found in 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities”; Part 70, 

“Domestic Licensing of Special Nuclear Material”; Part 73, “Physical Protection of Plants and Materials”; 

and Part 110, “Export and Import of Nuclear Equipment and Materials.” 

Paragraph 50.34(c) of 10 CFR Part 50 and paragraphs 70.22(g), 70.22(h), and 70.22(k) of 10 CFR 

Part 70 identify the physical protection information that must be provided in a physical security plan as 

part of a license application. This plan is required in Order for the applicant to demonstrate compliance 

with the specific physical protection requirements of 10 CFR Part 73 and must be submitted with each 

application for a license to possess or use SNM (or for a license authorizing transport or delivery of 

SNM), except for a license to possess, use, or transport less than 10 kg of SNM of low strategic 

significance, in which case a physical security plan is not required. However, for the protection of SNM 

of low strategic significance, the licensee is required to meet the requirements of § 73.67, “Licensee Fixed 

Site and In-Transit Requirements for the Physical Protection of Special Nuclear Material of Moderate and 

Low Strategic Significance,” of 10 CFR Part 73. 

Any guidance in this document related to information collection activities has been cleared under 

OMB Clearance Nos. 3150-0002, 3150-0009, and 3150-0011. 

This regulatory guide describes the information required in the physical security plan submitted 

as part of an application for a license to possess, use, or transport SNM of moderate strategic significance 

or 10 kg or more of SNM of low strategic significance and recommends a standard format for presenting 

the information in an orderly arrangement. This standard format will thus serve as an aid to uniformity 

and completeness in the preparation and review of the physical security plan of the license application. 

This document can also be used as guidance by licensees possessing or transporting less than 10 kg of 

SNM of low strategic significance in understanding the intent and implementing the requirements of 

paragraphs 73.67(a), 73.67(f), and 73.67(g) of 10 CFR Part 73. 

Aside from providing guidance for the standard format and content of physical security plans, this 

regulatory guide explains the intent of the various provisions of the regulation. The intent of each 

requirement is found in the discussion of each subsection and is implicitly provided by outlining 

alternative systems that could be used to fulfill the requirements. The discussion section and list of 

alternatives should provide the licensee with the sense of the NRC regulations. 

This guide is divided into two parts. Part I, “Special Nuclear Material of Moderate Strategic 

Significance,” provides a standard format for preparing the licensee’s security plans and provides 

guidance to licensees who possess, use, or transport SNM of moderate strategic significance. Chapters 1 

through 6 of Part I apply to applications for a license to possess or use at any fixed site, or at contiguous 

sites subject to control by the licensee, SNM of moderate strategic significance. Chapters 7 through 13 of 

Part I apply to applications for authorization to transport or deliver to a carrier for transport SNM of 

moderate strategic significance. 
Rev. 1 of RG-5.59, Page 6 

Part II, “Special Nuclear Material of Low Strategic Significance,” provides a standard format for 

preparing the licensee’s security plan for licensees who possess, use, or transport more than 10 kg of 

SNM of low strategic significance. It also provides guidance to all licensees who possess, use, or 

transport SNM of low strategic significance. Chapters 1 through 4 of Part II apply to applications for a 

license to possess or use at any fixed site, or at contiguous sites subject to control by the licensee, more 

than 10 kg of SNM of low strategic significance. Included in this category are licensees who have 

nuclear power reactors under construction and are seeking a license to possess nuclear fuel onsite prior to 

obtaining their operating license. Chapters 5 through 9 of Part II apply to applications for authorization to 

transport or deliver to a carrier for transport more than 10 kg of SNM of low strategic significance. 

Table 1 shows the type and amount of SNM covered in § 73.67 of 10 CFR Part 73. It should be 

noted, as stated in the footnote to Table 1, that (1) plutonium with an isotopic concentration exceeding 80 

percent or more in Pu-238, (2) special nuclear material that is not readily separable from other radioactive 

material and that has a total external radiation dose rate in excess of 100 rems per hour at a distance of 3 

feet from any accessible surface without intervening shielding, and (3) sealed plutonium-beryllium 

neutron sources totaling 500 grams or less of contained plutonium at any one site or contiguous sites are 

exempt from the requirements of S 73.67 of 10 CFR Part 73. 

This guide has been prepared to minimize time lost because of incomplete physical security plans 

and to standardize the review process. Applicants are encouraged to prepare their physical security plans 

in accordance with this guide and to provide information in each section to support the conclusion that 

they will be able to operate in accordance with the pertinent regulations. Although conformance with this 

guide is not required, the format and content presented are acceptable to the NRC staff. 

As developments and changes in the nuclear industry occur, the Commission’s requirements for 

information may need modification; revisions to this guide will be made as necessary to accommodate 

these changes. 

Purpose and Applicability 

This standard format has been prepared as an aid to uniformity and completeness in the 

preparation and review of the physical protection section of license applications and to clarify the intent 

of the regulations. The information this guide contains will help the licensee plan a physical protection 

system designed to detect the theft of SNM of moderate or low strategic significance. The physical 

protection subsystems identified are those that will usually be included in a protection system that would 

normally be capable of meeting the performance requirements of paragraph 73.67(a) of 10 CFR Part 73. 

However, it is recognized that at any particular site there may be some subsystems and components not 

needed or additional ones needed to meet these performance requirements. In these cases, applicants are 

encouraged to address in the license application specific departures of subsystems or components from 

this guide. 

The information requested in this guide is the minimum needed for the review of a physical 

security plan. Additional information may be required for completing the staff review of a particular plan 

and should be included as appropriate. It is also the applicant’s responsibility to be aware of new and 

revised NRC regulations. The information provided should be up to date with respect to the state of 

technology for the physical protection techniques and systems that the applicant proposes to use. 

In cases where NRC-approved security plans are already in existence and where the measures 

included therein meet or exceed the requirements of § 73.67 of 10 CFR Part 73, licensees may reference 

in their proposed security plans those sections of the NRC-approved security plans that are applicable. 
Rev. 1 of RG-5.59, Page 7 

Table 1. Categories of Special Nuclear Material 

MATERIALa ENRICHMENT 

MODERATE STRATEGIC 

SIGNIFICANCE 

LOW S

SIGNI

1. Plutonium Less than 2,000 g but more than 500 g 500 g or less but m2. Uranium-235 20% or more in U-235 isotope Less than 5,000 g but more than 1,000 g 1,000 g or less but  10% or more but less than 20% in 

U-235 isotope 

10,000 g or more Less than 10,000 g 

 Above natural but less than 10% -- 10,000 g or more 3. Uranium-233 -- Less than 2,000 g but more than 500 g 500 g or less but m4. Uranium-235, 

uranium-233, and plutonium in combination 

U-235 portion enriched to 20% or more. 

Less than 5,000 g according to the formula: grams = (grams contained U235) + 2.5 (grams U-233 + grams plutonium) but more than 1,000 g according to the formula: grams = (grams U-235) + 2.0 (grams U-233 + grams plutonium) 

1,000 g or less accgrams = (grams co(grams U-233 + grmore than 15 g accgrams = grams, conU-233 + grams plu

a. The following materials are exempt: 

1. Special nuclear material that is not readily separable from the radioactive material and that has a total external radiation dose r

per hour at a distance of 3 feet from any accessible surface without intervening shielding, 

2. Plutonium with an isotopic concentration of 80 percent or more in Pu-238, and 3. Sealed plutonium-beryllium neutron sources totaling 500 grams or less of contained plutonium at any one site or contiguous si
Rev. 1 of RG-5.59, Page 8 

Information and procedures delineated in the regulatory guides in Division 5, “Materials and 

Plant Protection,” that are appropriate to certain sections of the physical security plan may be 

incorporated by reference. 

Applicants should discuss their plans and programs with the NRC staff before preparing the 

applications. These discussions should give particular emphasis to the depth of information required for 

the plans. 

Upon receipt of an application, the NRC staff will perform a preliminary review to determine 

whether the application provides a reasonably complete presentation of the information needed to form a 

basis for the findings required before issuance of a license. The standard format will be used by the staff, 

as a guideline for identifying the type of information needed. If an application does not provide a 

reasonably complete presentation of the necessary information, further review of an application will be 

suspended until this needed information is provided. 

Use of Standard Format 

The applicant should follow the numbering system of the Standard Format down to the level of 

section (e.g., 3.4). Under some circumstances, certain sections may not be applicable to a specific 

application. If so, this should be clearly stated and sufficient information should be provided to support 

that conclusion. 

The applicant may wish to submit in support of the application information that is not required by 

regulations and is not essential to the description of the applicant’s physical protection program. Such 

information could include, for example, historical data submitted in demonstration of certain criteria, 

discussion of alternatives considered by the applicant, or supplementary data regarding assumed models, 

data, or calculations. This information should be provided as an appendix to the application. 

Upon completion of the application, the applicant should use the Table of Contents of the 

Standard Format as a checklist to ensure that each subject has been addressed. 

Style and Composition 

A table of contents should be included in each submittal. 

The applicant should strive for clear, concise presentation of information. Confusing or 

ambiguous statements and general statements of intent should be avoided. Definitions and abbreviations 

should be consistent throughout the submittal and consistent with generally accepted usage. 

Wherever possible, duplication of information should be avoided. Thus, information already 

included in other sections of the applications may be covered by specific reference to those sections. 

Where numerical values are stated, the number of significant figures should reflect the accuracy 

or precision to which the number is known. The use of relative values should be clearly indicated. 

Drawings, diagrams, and tables should be used when information may be presented more 

adequately or conveniently by such means. These illustrations should be located in the section where 

they are first referenced. Care should be taken to ensure that all information presented in drawings is 

legible, that symbols are defined, and that drawings are not reduced to the extent that they cannot be read 

by unaided normal eyes. 
Rev. 1 of RG-5.59, Page 9 

Physical Specifications of Submittals 

All material submitted in an application should conform to the following physical dimensions of 

page size, quality of paper and inks, numbering of pages, etc.: 

1. Paper Size 

Text pages: 81⁄2 × 11 inches. 

Drawings and graphics: 81⁄2 × 11 inches preferred; however, a larger size is acceptable provided 

the finished copy when folded does not exceed 81⁄2 × 11 inches. 

2. Paper Stock and Ink 

Suitable quality in substance, paper color, and ink density for handling and for reproduction by 

microfilming. 

3. Page Margins 

A margin of no less than 1 inch is to be maintained on the top, bottom, and binding side of all 

pages submitted. 

4. Printing

Composition: text pages should be single spaced. 

Type face and style: must be suitable for microfilming. 

Reproduction: may be mechanically or photographically reproduced. All pages of the text may 

be printed on both sides, and images should be printed head to head. 

5. Binding 

Pages should be punched for looseleaf ring binding. 

6. Page Numbering 

Pages should be numbered by section and sequentially within the section. Do not number the 

entire report sequentially. (This entire Standard Format has been numbered sequentially because 

the individual chapters were too short for sequential numbering within each section to be 

meaningful.) 

7. Format References 

In the application, references to this Standard Format should be by part, chapter, and section 

numbers. 

Procedures for Updating or Revising Pages 

The updating or revising of data and text should be on a replacement page basis. 

The changed or revised portion of each page should be highlighted by a vertical line in the margin 

opposite the binding margin for each line changed or added. All pages submitted to update, revise, or add 

pages to the report should show the date of the change. The transmittal letter should include an index 

page listing the pages to be inserted and the pages to be removed. When major changes or additions are 

made, pages for a revised table of contents should be provided. 
Rev. 1 of RG-5.59, Page 10 

Number of Copies 

The applicant should submit the appropriate number of copies of each required submittal pursuant 

to § 70.21, “Filing,” of 10 CFR Part 70. 

Public Disclosure 

The NRC has determined that the public disclosure of the details of physical protection programs 

is not in the public interest, and such details are withheld pursuant to paragraph 2.790(d) of 

10 CFR Part 2, “Rules of Practice for Domestic Licensing Proceedings.” Thus the physical protection 

section of each application should be submitted as a separate enclosure. Other proprietary and classified 

information should be clearly identified and submitted in separate enclosures. Each such submittal of 

proprietary information should be accompanied by the applicant’s detailed reasons and justifications for 

requesting exemption from public disclosure as required in paragraph 2.790(b) of 10 CFR Part 2. 
Rev. 1 of RG-5.59, Page 11 

PART I SPECIAL NUCLEAR MATERIAL OF MODERATE 

STRATEGIC SIGNIFICANCE 

1. Use and Storage Area at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraphs 73.67(d)(1) and (d)(2), 

which are as follows: 

(d)(1) Use the material only within a controlled access area which is illuminated sufficiently to 

allow detection and surveillance of unauthorized penetration or activities.1

 

(d)(2) Store the material only within a controlled access area such as a vault-type room or 

approved security cabinet or their equivalent which is illuminated sufficiently to allow 

detection and surveillance of unauthorized penetration or activities.1

 

A controlled access area (CAA) is defined in paragraph 73.2(z) as “any temporarily or 

permanently established area which is clearly demarcated, access to which is controlled and which affords 

isolation of the material or persons within it.” “Access control” means measures used to allow only 

specified personnel, materials, and vehicles ingress into and egress from a given area, while “isolation” 

refers to measures taken to deter persons, materials, or vehicles from entering or leaving a given area 

through other than established access control points. Thus, a CAA includes provisions for both isolation 

and access control. In some cases, isolation or access control systems may also serve the purpose of 

aiding in the detection of unauthorized penetration or activities1

 within the CAA. Therefore, these 

detection-related considerations are alluded to in this chapter. 

In the discussion that follows, CAAs intended for use and the possible storage of SNM of 

moderate strategic significance are discussed separately from those intended solely for the storage of such 

SNM. Although the requirements for these two different applications of CAA are in most respects 

similar, it is recognized that the means used to isolate the material and control access may differ markedly 

for use areas compared with storage areas and therefore warrant separate discussion. 

1.1 Area Where Material is Used [73.67(d)(1)] 

Intent 

This section discusses CAAs intended primarily for the use of SNM of moderate strategic 

significance. These may be temporarily established to meet transitory or intermittent SNM use 

requirements or they may be permanently established. Permanently established CAAs for use of SNM 

may also be suitable for storage. “Use” means that the material is undergoing processing (e.g., fuel 

fabrication, irradiation in a reactor) or utilization of its properties in conjunction with experimental 

equipment (e.g., equipment used for research or educational laboratory experiments). Different 

isolation/access control measures may be used for periods during which the area is occupied versus 

unoccupied. 

Illumination sufficient to allow detection and surveillance of unauthorized penetration or 

activities within the CAA where the material is used need not require the use of high-intensity lighting 

throughout the CAA. What is intended is the use of normal lighting sufficiently uniform throughout the 

CAA to ensure that material or unauthorized personnel cannot be secreted in a darkened area until a time 

 

1

 Unauthorized activities are those activities deemed by the licensee to be indicative of or contributory to the possible 

theft of SNM. 
Rev. 1 of RG-5.59, Page 12 

more convenient for the unauthorized removal of the material. For those facilities where experiments 

must be conducted in a darkened room, the lighting requirement is exempted for as long as is needed 

provided access control is ensured and the material is accounted for at the end of the experiment. 

1. Temporarily Established CAAs 

Temporarily established CAAs for the use of SNM need not have permanent barriers at their 

boundaries. Isolation of the material and persons using the material may be provided by office partitions, 

cordons, or other devices used to warn passersby of the restricted nature of the area. Access control can 

be effected through surveillance or supervision of the area by those who are using the SNM and who are 

responsible for the material. However, the provision of access control through personal supervision is 

suitable only for those situations in which the size of the CAA and the number of persons to be admitted 

are sufficiently small and in which the CAA is suitably configured to make such procedures practical. 

When material located in a temporarily established CAA is to be left unattended (i.e., because it 

is impractical to replace the material in a CAA designed for long-term storage of the material), access 

control and improved isolation for the temporary CAA may be provided to substitute for the discontinued 

personal supervision over the material. (In addition, provisions must be made for satisfying the 

monitoring requirement of paragraph 73.67(d)(3).) Improved isolation can sometimes be provided by 

increasing the penetration resistance of existing barriers (e.g., locking doors and windows, placing the 

material in a locked drawer or supply room). Access control may be provided by any of the measures 

suggested below for permanently established CAAs left unattended; some of these suggestions may be 

more suitable for temporary use than others. If no suitable barrier is available to provide isolation, 

material left unattended may be protected by a motion alarm covering the area immediately surrounding 

the material. This improved detection capability would be considered an acceptable substitute for the 

rudimentary isolation provided by temporary barricades, cordons, signs, and other less substantial means 

of isolation that may be used on a temporary basis. 

2. Permanently Established CAAs 

Permanently established CAAs for the use and temporary storage of SNM of moderate strategic 

significance would most likely provide isolation for the SNM through the use of permanent barriers. 

These could consist of fences; gates or freestanding walls for exterior areas; or exterior or interior 

building walls, locked doors, windows, bars, grillwork; or other barriers for interior areas. Such barriers 

are not required to meet the more stringent criteria for physical barriers used for the protection of formula 

quantities of strategic special nuclear material (SSNM).2

 However, good security management practice 

would dictate that the barrier be substantial enough to deter casual passersby from unauthorized 

penetration. If the barriers are also designed to aid in detection, the criteria for penetration resistance or 

tamper indication in accordance with the specific monitoring procedures to be used also apply. 

Access control for permanently established CAAs during periods they are occupied can be 

provided by personal supervision. However, when these areas are unoccupied or when the size, 

configuration, or numbers of persons intended to be admitted to the area make personal supervision 

 

2

 “Strategic special nuclear material” means uranium-235 (contained in uranium enriched to 20 percent or more in the U235 isotope), uranium-233, or plutonium. 
Rev. 1 of RG-5.59, Page 13 

impractical, other means of access control may be called for. Some of the additional access control 

measures that may be used for permanently established CAAs3

 in these situations are: 

• Stationing a watchman at CAA access control points, 

• Limiting distribution of keys, keycards, or combinations to doors and gates, 

• Using a coded badging system to identify authorized personnel at CAA access control points, 

• Controlling locked CAA doors and gates by use of remote surveillance (e.g., intercom or CCTV) 

by personnel stationed at a centrally located access control facility, or 

• Controlling access of personnel, material, and vehicles into CAAs by other means. 

It is expected that large facilities will have more complex isolation and access control systems 

than small facilities in order to achieve comparable levels of protection. 

Content 

(This section needs to be completed only for CAAs designated exclusively for use of SNM. 

CAAs designated for both use and storage are to be described as recommended in Section 1.2 of Part I of 

this Standard Format.) 

Describe the CAAs designated exclusively for use of the material. Indicate under what 

conditions CAAs will be established on a temporary basis. For each CAA identified, provide the 

following information: 

1. A description of the area and its features relative to other facility features, showing the 

normal routes of ingress to each CAA (including a scale diagram). 

2. Descriptions of physical barriers, cordons, walls, partitions, or other means of providing 

isolation of the CAA and channeling entry through established access control points into the CAA. 

3. The means and criteria used for controlling access into the CAA at established access 

control points. 

4. If more than one CAA is designated, the types of material normally used in each CAA; 

for temporarily established CAAs, the types of activities normally performed within each area. 

5. The lighting level and uniformity of lighting provided to allow detection and surveillance 

of unauthorized penetration or activities within the CAA or in the immediate vicinity of the CAA. 

1.2 Area Where Material Is Stored [73.67(d)(2)] 

Intent 

CAAs normally used only for storage of SNM are described in this section. Such CAAs may be 

very limited in size since they need only contain the material itself, and access to them is expected to be 

 

3

 Access control requirements for CAAs for the use or storage of SNM of moderate strategic significance are discussed 

in Chapter 3, “Access Control at a Fixed Site,” of Part I of this guide. 
Rev. 1 of RG-5.59, Page 14 

infrequent. Where small amounts of material are involved, the CAA may consist of relatively small 

containers such as security cabinets, safes, and locked closets or supply rooms. 

The same basic isolation and access control4

 capabilities that apply to CAAs for the use of SNM 

of moderate strategic significance also apply to CAAs for the storage of this material. However, the CAA 

for storage is, in addition, specifically required to be equivalent to either an approved security cabinet or a 

vault-type room. This additional requirement embodies a tradeoff decision to be made by the licensee 

between the capability for immediate detection of penetration attempts into a vault-type room and the 

improved penetration resistance likely to be provided by an approved security cabinet. 

A vault-type room is defined in paragraph 73.2(o) of 10 CFR Part 73 as “a room with one or more 

doors, all capable of being locked, protected by an intrusion alarm which creates an alarm upon the entry 

of a person anywhere into the room and upon exit from the room or upon movement of an individual 

within the room.” The vault-type room can be a locked laboratory, supply room, closet, or other room 

equipped with a tamper-resistant motion detector alarm system. The motion detector would 

simultaneously satisfy the monitoring requirement of paragraph 73.67(d)(3) addressed in the next chapter. 

The expression “equivalent to a vault-type room” means that a piece of equipment (such as a fission 

chamber, reactor core, or storage rack), even though it does not resemble a “room,” may meet the 

requirement for a storage-type CAA if there is a means of isolation (e.g., a locked grill, inaccessibility 

beneath water as in a storage pool, intricate and time-consuming procedures required for removal) and it 

is protected with a tamper-resistant motion detection system. 

Note that, in some cases, material located in such pieces of equipment may be considered in use 

rather than in storage. In this case, whether the material is being personally supervised or not, the 

requirement for use of a motion detection system to satisfy the monitoring requirement is removed, and 

other monitoring devices or procedures may be used instead. 

When a container equivalent to an approved security cabinet is chosen to satisfy paragraph 

73.67(d)(2), the equivalency is based on the penetration resistance of the container and the difficulty 

associated with manipulating the lock. The basic premise used to determine whether such a container 

may be monitored by procedures or devices other than a motion detector is whether it is unreasonable to 

expect that an external adversary could penetrate the container in a reasonable amount of time without 

leaving an indication of the penetration. The amount of time that would be required for penetration 

without such an indication may be used to govern the frequency of patrols when monitoring procedures 

are used. An approved security cabinet or its equivalent is one whose design has been certified by the 

General Services Administration or other nationally recognized standards organization (e.g., ANSI) to 

afford protection against surreptitious entry and lock manipulation equivalent to that provided by a 

Class-6 GSA rating or better. 

Isolation for CAAs intended only for storage usually will be provided by the penetration-resistant 

features of the perimeter barriers or container walls of the CAA. The level of penetration resistance of 

such barriers is not required to meet the more stringent criteria for physical barriers used to protect 

formula quantities of SSNM. Rather, the physical barriers or container walls of the CAA are intended 

only to deter penetration by unauthorized persons and to aid detection by providing an indication of 

forced penetration. 

In determining the level of isolation/access control required for such CAAs, the time required for 

extricating SNM from its storage location in relationship to the licensee’s time of detection and 

 

4

 Access control requirements for CAAs for the use or storage of SNM of moderate strategic significance are discussed 

in Chapter 3 of Part I of this guide. 
Rev. 1 of RG-5.59, Page 15 

assessment may be taken into account (e.g., spent fuel assemblies stored in spent fuel storage pools or fuel 

residing in nonpower reactor cores). 

Examples of typical CAAs where special nuclear material of moderate strategic significance may 

be stored are: 

1. Vault. A structure that satisfies the definition for a vault as stated in paragraph 73.2(n) 

would provide more than adequate isolation protection. 

2. Approved Security Cabinets. Those cabinets that are designed to provide delay and 

resistance against surreptitious entry and lock manipulation. 

3. Reactor. Reactors that are so designed that removal of material is difficult. 

4. Vault-Type Room. Some typical vault-type rooms where materials are stored and 

protected with a motion detector are storage pools, a room containing in-process storage 

racks, and laboratories where material is left unattended. In all cases, movement in the 

near vicinity of the material or of the material itself generates an alarm signal. 

5. Locked Laboratories, Supply Rooms. These areas must be sufficiently penetration 

resistant to afford a means of isolation/access control and permit the proper functioning 

of the system for monitoring the storage area as required by paragraph 73.67(d)(3) of the 

rule and as described in Chapter 2, “Detection Devices and Procedures at a Fixed Site,” 

of Part I of this guide. 

The illumination level required for the CAA should be sufficiently uniform and bright (a) in the 

case of a security cabinet, to detect penetration of or tampering with the CAA containment or (b) in the 

case of a vault-type room or its equivalent, to detect unauthorized penetration of or activities within the 

CAA. 

Content 

Describe the CAAs where the material will be stored and, in some cases, used. For each such 

CAA, provide the following information: 

1. A description of the area and its features relative to other facility features, showing the 

access control points for the CAA (including a scale diagram). 

2. The isolation system such as physical barriers, container walls, or other features that 

demarcate the perimeter of the CAA and channel entry only through established access 

control points. 

3. The means and criteria used for controlling access to the CAA at established access 

control points. 

4. If more than one CAA is designated for the storage of the material, the types of material 

normally to be stored in, each area. 

5. The lighting level and uniformity of lighting provided to allow detection and surveillance 

of unauthorized penetration or activities within the CAA or in the immediate vicinity of 

the CAA (where security cabinets are used). 
Rev. 1 of RG-5.59, Page 16 

2. Detection Devices and Procedures at a Fixed Site 

This chapter provides guidance for meeting the requirement of paragraph 73.67(d)(3), which is as 

follows: 

(d)(3) Monitor with an intrusion alarm or other device or procedures the controlled access areas 

to detect unauthorized penetrations or activities. 

The purpose of this monitoring activity as stated in paragraph 73.67(a)(2) is to provide “early 

detection and assessment of unauthorized access or activities by an external adversary within the 

controlled access area...” and “early detection of removal of special nuclear material by an external 

adversary from a controlled access area.” This should be done to achieve the objective of minimizing the 

possibilities for unauthorized removal of special nuclear material “consistent with the consequences of 

such actions,” as stated in paragraph 73.67(a) of the effective rule. Thus, the earliness of detection 

afforded by the licensee’s physical protection system may vary depending on the nature and quantity of 

the material susceptible to unauthorized removal. Further discussion of the earliness of detection required 

for possible thefts of different types and quantities of special nuclear material of moderate strategic 

significance is provided in Section 2.1 of Part I of this guide. 

2.1 Earliness of Detection [73.67(a)] 

Determination of early detection of unauthorized access, activities, or removal of SNM from 

CAAs will be based on an assessment of the magnitude of the consequences associated with possible 

misuse of the type and quantity of material that could be removed in a given theft attempt. For SNM of 

moderate strategic significance, two distinct cases are considered: 

1. Theft of strategic special nuclear material (SSNM).5

 

2. Theft of low-enriched uranium (LEU).6

Thefts from a single facility of SSNM in quantities of moderate strategic significance are limited 

by definition to quantities that could not be used to construct a nuclear explosive device; thefts of similar 

quantities of material from several different facilities could, however, lead to the accumulation of an 

aggregate quantity that would permit such illicit use. (The consequences of a single theft of such material 

would have minimal impact on the public health and safety.) Therefore, detection of such thefts is 

required sufficiently early to ensure early notification to the NRC so that the NRC in turn can notify other 

licensees of the need to implement appropriate responses to prevent the accumulation by a single 

adversary of a formula quantity of material through multiple thefts from different facilities. The NRC 

believes that there are detection systems and procedures that would allow the licensee to detect a theft of 

SSNM within approximately 2 hours. 

The criteria for early detection of thefts of LEU enriched to more than 10 percent, but less than 20 

percent, in the isotope U-235 are the same as for thefts of LEU in quantities comprising SNM of low 

strategic significance. The reader should refer to Part II of this guide for information regarding 

appropriate monitoring procedures to achieve early detection for such material. 

 

5

 In this case, strategic special nuclear material means all SNM of moderate strategic significance other than lowenriched uranium. 

6

 Low-enriched uranium is uranium enriched above natural percentages but less than 20 percent in the U-235 isotope. 
Rev. 1 of RG-5.59, Page 17 

2.2 Detection Through Monitoring Controlled Access Areas [73.67(d)(3)] 

Intent 

Licensees possessing quantities of SNM of moderate strategic significance can provide a 

monitoring system capable of detecting a theft of material within approximately 2 hours of the actual 

removal of the material. Either detection devices or security procedures may be used to help detect 

unauthorized activities or penetration of CAAs. Most of the sites at which this material is stored or used 

are likely to be small research-oriented facilities such as nonpower reactors and educational institutions. 

At such facilities there are likely to be relatively small quantities of SNM available, and authorized access 

to it may be infrequent. 

Detection devices such as interior motion detector systems, balanced magnetic switches, etc., 

could be used to monitor such relatively small CAAs where the number of established access control 

points is very limited. 

Security procedures may also be used to protect against thefts of quantities of SNM of moderate 

strategic significance because watchman patrols inherently allow unguarded intervals during which an 

external adversary could conceivably obtain access to the CAA, remove a small quantity of material, and 

leave before being discovered. The inspection procedure may (1) be sufficiently frequent to ensure that 

an external adversary could not complete a successful theft of the material during the unguarded intervals, 

(2) provide for an indication of the CAA barrier having been tampered with (as with a seal or by 

observation of damage done to the barrier), or (3) provide for an item count inventory or other accounting 

for the material as part of the inspection. Some examples are given below: 

• After having left material unattended in an experimental setup in a classroom used as a temporary 

CAA, the instructor returns after several hours and verifies that the material is still in place. 

• A small quantity of material is stored in a security cabinet for several months at a time without 

authorized access. Every 2 hours a watchman comes around to inspect the cabinet to ensure that 

the lock is secure and the cabinet has not been tampered with. If a lock is used that is not 

designed to be resistant to surreptitious and forced entry, the watchman also inspects a tamperindicating seal to verify that the container has not been tampered with. 

• During periods when a nonpower reactor is left unattended, a watchman comes around every 2 

hours and checks that none of the fuel elements have been removed by unauthorized persons. If a 

person working during off-hours in the vicinity of the nonpower reactor is encountered, 

appropriate identification is requested. 

• While a nonpower reactor is being used, the supervisor ensures that he/she or his/her designee is 

not away from the reactor for a period longer than 30 minutes or a period he/she estimates would 

be minimally required for a person to obtain fuel elements in the core that are not self-protecting 

by virtue of their having been sufficiently irradiated. 

• During periods when excess fuel is left unattended in a storage closet at a nonpower reactor 

facility, an alarm system is activated that would annunciate if anybody tried to penetrate the 

closet without proper authorization. 

During periods when the material is being used under the direct supervision of authorized 

personnel, the monitoring requirement may be satisfied by virtue of the continuous surveillance exercised 

by such personnel. 
Rev. 1 of RG-5.59, Page 18 

Content 

For each of the CAAs designated for the protection of SNM of moderate strategic significance, 

provide the following information regarding the measures taken to fulfill the monitoring requirement of 

paragraph 73.67(d)(3): 

1. Describe any devices employed by specifying the type of device, its installed location, 

the type and location of annunciation, the intended area of coverage, and the tamperresistant features. Refer, if desired, to existing filed security plans, regulatory guides, or 

NUREG documents. 

2. Describe any procedures employed to monitor the CAA or portions thereof, including the 

categories of persons who will execute the procedures, the frequency of inspections or 

rounds of patrol, the basis for the determination of such frequencies, and the occasions 

when the procedures are intended to be implemented. Also indicate the features of the 

CAA (e.g., barriers, locks, seals) that will affect the way the procedures are used. 

3. Explain how the combination of procedures and devices used to monitor each CAA 

meets the criteria for early detection of theft by an external adversary relative to the type 

of material found in each CAA. 

3. Access Control at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraphs 73.67(d)(4), (d)(5), 

(d)(6), (d)(7), and (d)(10), which are as follows: 

(d)(4) Conduct screening prior to granting an individual unescorted access to the controlled 

access area where the material is used or stored, in order to obtain information on which 

to base a decision to permit such access, 

(d)(5) Develop and maintain a controlled badging and lock system to identify and limit access 

to the controlled access areas to authorized individuals, 

(d)(6) Limit access to the controlled access areas to authorized or escorted individuals who 

require such access in order to perform their duties, 

(d)(7) Assure that all visitors to the controlled access areas are under the constant escort of an 

individual who has been authorized access to the area, 

(d)(10) Search on a random basis vehicles and packages leaving the controlled access areas. 

An access control system is one that controls access to or egress from a CAA through normal 

routes for personnel, materials, or vehicles. 

3.1 Preauthorization Screening [73.67(d)(4)] 

Intent 

The intent of the requirement for preauthorization screening is to ensure that the licensee will 

have sufficient knowledge of an individual to determine his/her reliability and need for access prior to 

granting him/her authorized access to the CAA where the material is used or stored. The selection of 
Rev. 1 of RG-5.59, Page 19 

procedures for conducting this examination and the criteria employed to make these judgments are the 

responsibility of the licensee and, of course, should be consistent with all local, State, and Federal laws 

and regulations regarding the protection of the privacy and other rights of the individual. The screening 

process may be conducted in the same manner as other investigations customarily conducted by potential 

employers for similarly sensitive positions. There is no requirement for the licensee to arrange for an 

NRC clearance or similar clearance from any other government organization. Examples of procedures 

and criteria that may be employed in the screening process include holding or having recently held a 

government-sanctioned clearance; examination of past employment or educational records (to determine 

any unsatisfactory employment or school actions or incidents that would indicate any unreliability or 

previous breaches of trust between the individual and his/her employer); endorsements or references from 

previous employers, teachers, or colleagues that would support a decision for granting access or that 

would attest to the trustworthiness and reliability of the individual; and consideration of the individual’s 

present employment record indicating demonstrated trustworthiness and reliability over an extended 

period of employment with the licensee. (This may be considered in the nature of “grandfathering.”) 

Content 

Describe the procedures and criteria that will be used for obtaining sufficient information prior to 

making a decision on granting unescorted access authorization to an individual to CAAs where the 

material is used or stored. Identify the types of individuals who will be screened (e.g., process engineers, 

supervisory personnel, professors, instructors, graduate students) and who will perform the screening 

process. 

3.2 Badging System [73.67(d)(5)] 

Intent 

The purpose of the badging system is to facilitate the identification of authorized individuals and 

the control of access to or within the CAA where the material is used or stored. Information on the badge 

should be such that it is possible to clearly distinguish personnel authorized for access to the CAAs from 

those requiring an escort. Information on the badge should also uniquely identify the individual 

possessing the badge. This personalized information can be obtained through the use of photographs, 

personal vital statistics, signatures, or any means the licensee may wish to use that will uniquely identify 

the individual. 

Content 

Describe the badging system used to facilitate control of access to the CAAs. This description 

should include: 

1. The size, shape, color, material, and construction of badges. 

2. The distinguishing features of the badge that identify authorized individuals from 

escorted individuals. 

3. How the badges will be used for controlling access. (For example, will all individuals be 

checked prior to entering the CAAs, will periodic checks be made of individuals within a 

CAA to determine if they are authorized or under escort, or will the badge itself permit 

authorized entrance, e.g., a card key.) 

4. The system used for issuing, controlling, and accounting for the badges. 
Rev. 1 of RG-5.59, Page 20 

3.3 Lock System [73.67(d)(5)] 

Intent 

Locks used to control access to CAAs should be resistant to manipulation or picking and should 

not be mastered. Examples of typical lock systems that fit this description are three-position dial-type 

combination locks, six-pin key locks, and card-key lock systems. The procedures for assigning keys and 

combinations to individuals is an integral part of the lock system and should be designed to ensure that 

only authorized personnel have access to such items. Locks and combinations should be changed when 

information is obtained that the lock system may have been compromised. Further information may be 

obtained in Regulatory Guide 5.12, “General Use of Locks in the Protection and Control of Facilities and 

Special Nuclear Materials.” 

Content 

Describe the locking system used to control access to the CAAs where material is used and 

stored. This description should include locations of all locks included in the system by type of lock, the 

pick-resistant and manipulation-resistant characteristics of each lock type used, personnel responsible for 

issuing keys or combinations and changing combinations or locks, criteria for changing combinations or 

locks, personnel authorized to be given keys or combinations, and descriptions of types of locks used 

(references may be made to Regulatory Guide 5.12 for this purpose). 

3.4 Personnel Entry Control System [73.67(d)(6)] 

Intent 

The success of other access control system components such as preauthorization screening, 

badging, and lock control is dependent upon effective control of personnel access into the CAA. Physical 

access may be controlled in a number of different ways depending on the actual configuration of the CAA 

and other site-specific factors. Some examples of these alternatives are: 

1. Control by Authorized Person. If the area to be controlled is sufficiently small and free 

of obstructions, an authorized person performing other activities in a CAA may effect 

physical access control by monitoring entry of unauthorized persons into the area. A sign 

posted at the entrance would help deter casual passersby. An example of this approach 

would be when laboratory instructors are conducting classes and, because they are 

familiar with each of their students, they could easily recognize unauthorized persons not 

belonging in the classes. 

2. Card-Key, Cipher, Combination, or Key-Lock Control System. A more sophisticated 

hardware-oriented system involves the use of a card-key, cipher, combination, or keylock system. Physical access control in this case consists of the use of physical barriers 

to deter unauthorized persons. A limited number of entrances that are controlled by 

authorized personnel using a card, key, cipher, combination, or key are provided. This 

system may be more useful when larger numbers of authorized personnel who would not 

necessarily be familiar with one another need to share the use of the CAA. 

3. Control by Security Organization. If security organization personnel are available 

physical access control may be accomplished by stationing a person at the entrance to the 

CAA to check identification and allow only authorized persons into the CAA. This 

alternative may be unjustifiably expensive unless the security organization member’s 
Rev. 1 of RG-5.59, Page 21 

salary can be justified on other grounds as well. A variation of this system requires 

persons seeking entrance to the CAA to obtain a key from a properly designated person 

or security organization for each use. 

Content 

Describe the system for limiting physical access to each CAA identified in Sections 1.1 and 1.2 of 

Part I to authorized personnel or those escorted by authorized personnel. Include in this description the 

names or titles of individuals granting access authorizations, the criteria to be used in granting 

authorizations, and the procedures used to ensure that only authorized or properly escorted persons are 

allowed access to the CAA. Reference may be made to Sections 3.1, 3.2, 3.3, 3.5, and 3.6 of this chapter 

as they apply to this section for the description of locks, barriers, or other hardware that are used to 

control access. 

3.5 Escort System [73.67(d)(7)] 

Intent 

The requirement that an escort system be established is in recognition of the fact that the licensee 

may wish to allow access to certain persons or classes of persons on a temporary or infrequent basis or on 

short notice, thus making the routine process for granting access authorizations impractical or 

inexpedient. Typical arrangements for escorted access may include escorts for maintenance or repair 

personnel, laboratory classes, public tours, guests, and visitors as required. 

Content 

Describe the system that will be used to escort individuals in the CAAs. In its security plan, the 

licensee should ensure that only properly authorized individuals will be allowed to escort individuals. 

This description should include: 

1. Criteria to be used for granting escorted access, 

2. Criteria to be used for escorting others, 

3. Procedures for escorting individuals into CAAs (e.g., students under the supervision of 

laboratory instructor, public tours), 

4. The number of escorted individuals per escort, and 

5. The responsibilities of the escort (e.g., periodic surveillance of all individuals under 

escort, accounting for all material prior to leaving the CAA, remaining in general area 

during the time unauthorized individuals are present).. 

3.6 Search [73.67(d)(10)] 

Intent 

The primary intent of the search requirement is to deter and possibly detect attempted thefts of 

SNM. The search procedures developed by the licensee should take into consideration the environs 

where the material is used or stored, the physical characteristics of the material itself, and the frequency 

of accounting for the material. In some cases, this will require that all vehicles and packages leaving the 
Rev. 1 of RG-5.59, Page 22 

CAAs be searched in a random manner. The frequency of random searches should be determined by the 

ease with which the material can be stolen and the length of time it would take to detect a theft. In other 

cases, only packages that equal or exceed the size of the material being used or stored would have to be 

searched, taking into consideration the difficulty with which the material could be broken into smaller, 

more easily concealed parts. 

Content 

Describe the system to be used for randomly searching vehicles or packages that leave the CAA. 

Include in the description information as to: 

1. The scope of the search. This should identify the criteria that will be used for searching 

vehicles and packages (e.g., whether all packages and vehicles are subject to search or 

just those packages or vehicles that are larger than the smallest configuration of material 

being used or stored). 

2. The randomness of the search. The scheme for selecting the packages or vehicles to be 

searched should be identified (e.g., subjecting each package or vehicle to a search, using 

a random number generator for determining whether a candidate package or vehicle is to 

be searched, searching a minimum percentage of all packages or vehicles leaving the 

CAA each day). 

4. Security Organization at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraph 73.67(d)(8), which 

states: 

(d)(8) Establish a security organization or modify the current security organization to consist of 

at least one watchman7

 per shift able to assess and respond to any unauthorized 

penetrations or activities in the controlled access areas. 

Intent 

The intent of this requirement is to ensure that, in the event of a security incident, someone will 

be available to assess alarms or other unauthorized penetrations or activities and, if warranted, notify the 

NRC, the local law enforcement authorities, and the responsible person in licensee management. Early 

detection and notification of any missing material will help facilitate its prompt recovery. In some cases, 

the licensee may assign additional duties to members of the security organization where procedure 

oriented options are chosen to satisfy physical protection requirements (e.g., periodic patrols and 

inspections of CAAs for storage of SNM). Security organization members are not required to be fully 

dedicated full-time employees of the licensee. They may include unarmed campus security personnel 

(watchmen), contract guards, members of the local law enforcement agency (if sufficiently close to the 

site), etc. No formal or comprehensive training program is required for security organization personnel. 

However, the licensee should be prepared to demonstrate that each security person understands the 

particular duties assigned to him/her and is fully qualified and trained to perform them. 

 

7

 A “watchman” is defined in paragraph 73.2(d) of 10 CFR Part 73 as “an individual, not necessarily uniformed or armed 

with a firearm, who provides protection for a plant and the special nuclear material therein in the course of performing 

other duties.” 
Rev. 1 of RG-5.59, Page 23 

Content 

Describe the security organization that will be responsible for assessing and responding to 

security incidents. Indicate the other responsibilities of the security organization such as: 

1. Conducting periodic physical security checks of CAAs, 

2. Maintaining liaison with the local law enforcement agency, 

3. Notifying the local law enforcement agency of any unauthorized penetrations or activities 

in the CAAs, and 

4. Notifying licensee management of any unauthorized penetrations or activities in the 

CAAs. 

5. Communications at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraph 73.67(d)(9), which 

states: 

(d)(9) Provide a communication capability between the security organization and appropriate 

response force. 

Intent 

The intent of this regulation is to ensure that a communication capability exists between the 

licensee and the designated response force. It is implied that, prior to setting up a communication 

capability, procedures and responsibilities will have been established between the response force and the 

licensee. (See Chapter 6, “Response Procedures at a Fixed Site,” of Part I.) The type of communication 

system chosen by a licensee should: 

1. Provide for full duplex voice communication capability, 

2. Be easily accessible to the licensee’s security organization, and 

3. Be reliable and available for immediate use at any time. 

Some communication systems that would provide these capabilities include a dedicated telephone 

system, a nondedicated public telephone system, radio, or any combination thereof. 

Content 

Describe the communication system that is used between the security organization and the 

appropriate response force. This description should include information on: 

1. Type of communication system, 

2. Location of voice terminals in relationship to CAAs, 

3. Availability of communication system on a 24-hour basis, and 

4. Reliability of communication system. 
Rev. 1 of RG-5.59, Page 24 

6. Response Procedures at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraph 73.67(d)(11), which 

states: 

(d)(11) Establish and maintain response procedures for dealing with threats of thefts or thefts of 

such materials. 

Intent 

The intent of this regulation is to help the licensee to identify those security incidents that could 

result in the loss of SNM of moderate strategic significance and to develop response procedures to 

prevent or reduce the likelihood of such a loss. Some types of incidents that should be considered and for 

which response procedures should be developed are: 

1. Situations that could possibly lead to theft of SNM (e.g., civil strife), 

2. Discovery that the security system has been breached, and 

3. Discovery that some SM is missing. 

Content 

Identify those events for which response procedures will be developed. Also, describe the type of 

response to be accomplished for each event identified and the duties and responsibilities of the security 

organization and management involved in the response. Ensure that the NRC will be notified 

immediately in the event of theft or attempted theft of the material. Describe what local law enforcement 

assistance is available, their response capabilities, and any agreements made with them to respond in the 

case of theft of the material. 

7. Material Transportation Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(1), which are 

as follows: 

(e)(1) Each licensee who transports, exports, or delivers to a carrier for transport special nuclear 

material of moderate strategic significance shall: 

(i) Provide advance notification to the receiver of any planned shipments specifying 

the mode of transport, estimated time of arrival, location of the nuclear material 

transfer point, name of carrier and transport identification, 

(ii) Receive confirmation from the receiver prior to the commencement of the 

planned shipment that the receiver will be ready to accept the shipment at the 

planned time and location and acknowledges the specified mode of transport, 

(iii) Check the integrity of the container and locks or seals prior to shipment, and 

(iv) Arrange for the in-transit physical protection of the material in accordance with 

the requirements of paragraph 73.67(e)(3) of this part unless the receiver is a 

licensee and has agreed in writing to arrange for the in-transit physical 

protection. 
Rev. 1 of RG-5.59, Page 25 

7.1 Advance Notification to Receiver [73.67(e)(11(1)] 

Intent 

The intent of this paragraph is to require the shipper to preplan the transportation of material and 

inform the receiver of his plans prior to shipment. This is the first of the several transportation 

requirements that will allow the receiver to take delivery of the material as planned or to help ensure 

traceability of any missing material. 

Content 

The licensee should ensure in his security plan that, prior to each shipment of material, the 

receiver will be notified of the impending shipment and provided the following types of information: 

1. Mode of transport (e.g., truck, plane, train, or ship), 

2. Estimated time of arrival, 

3. Location where custody of the material will be transferred to the receiver, 

4. Name of carrier, and 

5. Transport identification (e.g., truck, train, or flight number; ship name). 

7.2 Receiver Confirmation [73.67(e)(1)(ii)] 

Intent 

The intent of this requirement is that, prior to shipment, the shipper will be assured that the 

receiver is ready to accept the shipment at the planned time and location and has acknowledged the mode 

of transport. 

Content 

Describe what procedures will be used to ensure that shipment of material does not take place 

until the receiver acknowledges the planned shipment and mode of transport and states that he will be 

ready to accept the shipment at the planned time and location. 

7.3 Inspection [73.67(e)(1)(iii)] 

Intent 

The intent of this paragraph is to provide a means for confirming the integrity of a shipment 

through inspections just prior to commencement and during the shipment by ensuring that the material 

containers and any associated locks or seals are intact at the time the shipment commences. 

Content 

Describe the procedures to be used to ensure that the integrity of the shipment containers and 

associated locks or seals is checked just prior to shipment. 
Rev. 1 of RG-5.59, Page 26 

7.4 Responsibility for In-Transit Physical Protection [73.67(e)(1)(iv)]

Intent 

The intent of this paragraph is to make clear that the licensee shipping the material is responsible 

for arranging for the physical protection of the material in transit if the receiver is not a licensee. If both 

the shipper and receiver are licensees, the shipper may allow the receiver to accept this responsibility 

wholly or in part, provided there is appropriate documentation specifying their respective responsibilities. 

Where no such documentation exists, both the shipper and receiver are held jointly responsible. (See 

Section 8.3 of Part I of this guide.) 

Content 

In its security plan, the shipper should either acknowledge responsibility for the in-transit 

physical protection of SNM of moderate strategic significance or ensure that a written agreement from the 

receiver licensee has been received in which the receiver accepts either full responsibility or shared 

responsibility for the in-transit physical protection of this material in accordance with paragraph 

73.67(e)(3) of 10 CFR Part 73. 

8. Receiver Requirements--Transportation 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(2), which are 

as follows: 

(e)(2) Each licensee who receives special nuclear material of moderate strategic significance 

shall: 

(i) Check the integrity of the containers and seals upon receipt of the shipment, 

(ii) Notify the shipper of receipt of the material as required in Section 70.54 of Part 

70 of this chapter, and 

(iii) Arrange for the in-transit physical protection of the material in accordance with 

the requirements of paragraph 73.67(e)(3) of this part unless the shipper is a 

licensee and has agreed in writing to arrange for the in-transit physical 

protection. 

8.1 Inspection [73.67(e)(2)(i)] 

Intent 

This requirement is intended to determine whether the material’s container has been 

compromised en route and whether any material has been removed so that immediate recovery procedures 

may be initiated if required. 

Content 

Describe the procedures to be used to ensure that the integrity of the containers and seals will be 

checked upon receipt of the shipment of material. 
Rev. 1 of RG-5.59, Page 27 

8.2 Notification to Shipper [73.67(e)(2)(ii)] 

Intent 

This requirement is intended to provide the shipper with knowledge of when responsibility for the 

shipment has been assumed by the receiver and when the shipper’s responsibility is ended. 

Content 

Ensure that the receiver will send a completed copy of standard Form NRC-741, “Nuclear 

Material Transaction Report,” to the shipper within 10 days of receiving a shipment of material as 

required in § 70.54 of 10 CFR Part 70. 

8.3 Responsibility for In-Transit Physical Protection [73.57(e)(2)(iii)] 

Intent 

The intent of this paragraph is to make clear that the licensee receiving the material is responsible 

for arranging for the physical protection of the material in transit if the shipper is not a licensee. If both 

the shipper and receiver are licensees, the receiver may allow the shipper to accept this responsibility 

either wholly or in part provided there is appropriate documentation specifying their respective 

responsibilities. Where no such documentation exists, both the shipper and receiver are held jointly 

responsible. (See Section 7.5 of Part l of this guide.) 

Content 

In its security plan, the receiver should either acknowledge responsibility for the in-transit 

physical protection of SNM of moderate strategic significance or ensure that a written agreement from the 

shipper has been received in which the shipper accepts either full responsibility or shared responsibility 

for the in-transit physical protection of this material in accordance with paragraph 73.67(e)(3) of 10 CFR 

Part 73. 

9. In-Transit Physical Protection Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(3), which are 

as follows: 

(e)(3) Each licensee who arranges for the in-transit physical protection of special nuclear 

material of moderate strategic significance or who takes delivery of this material free on 

board (f.o.b.) the point at which it is delivered to a carrier for transport shall: 

(i) Arrange for telephone or radio communications between the transport and the 

licensee or its designee: (A) to periodically confirm the status of the shipment, 

(B) for notification of any delays in the scheduled shipment, and (C) to request 

appropriate local law enforcement agency response in the event of an emergency. 

(ii) Minimize the time that the material is in transit by reducing the number and 

duration of nuclear material transfers and by routing the material in the most safe 

and direct manner, 
Rev. 1 of RG-5.59, Page 28 

(iii) Conduct screening of all licensee employees involved in the transportation of the 

material in order to obtain information on which to base a decision to permit 

them control over the material, 

(iv) Establish and maintain response procedures for dealing with threats of thefts or 

thefts of such material, 

(v) Make arrangements to be notified immediately of the arrival of the shipment at 

its destination, or of any such shipment that is lost or unaccounted for after the 

estimated time of arrival at its destination, 

(vi) Initiate immediately a trace investigation of any shipment that is determined to be 

lost or unaccounted for after a reasonable time beyond the estimated arrival time. 

(vii) Notify immediately the Director of the appropriate Nuclear Regulatory 

Commission Regional Office listed in Appendix A to this part of the action being 

taken to trace the shipment. 

9.1 Communications [73.67(e)(3)(i)] 

Intent 

The primary intent of this requirement is to ensure that procedures are established or facilities 

made available to permit communications to take place between the transport and the licensee or its 

designee for the purposes of (1) periodically confirming the status of the shipment while it is in progress, 

(2) notifying the licensee of delays along the shipment route that may affect the shipment’s established 

schedule, and (3) requesting assistance from local law enforcement authorities (LLEAs). These 

communications need not be direct between the licensee and the transport. 

1. Confirmation of Shipment Status 

Communications for confirming the status of a shipment should be timed to reflect the expected 

changes in shipment status indicated by the shipment’s scheduled itinerary. For general motor freight 

(involving less-than-truckload quantities), direct communications between the transport and the licensee 

may be impractical. This requirement may then be satisfied by periodically telephoning the carrier to 

obtain updated reports on the shipment’s progress based on calls the carrier receives from drivers on a 

regular basis. The frequency with which the licensee should check the status of a shipment should 

normally be at least every 10 to 14 hours. This corresponds to the frequency with which the drivers 

normally would call in. Similar indirect communications may be used to satisfy this requirement in the 

case of air shipments, but they should be more frequent to reflect the shorter air travel times between 

terminals. When direct radio or telephone communications are practical between the licensee and the 

transport, the frequency of calls should normally be approximately every 12 hours. 

2. Notification of Shipment Delays 

Notifications to the licensee should be made by the carrier or transport personnel whenever 

unforeseen conditions arise that threaten to delay the shipment significantly beyond the estimated arrival 

time at the next point on the shipment’s itinerary. This notification may be made by conventional 

telephone lines or by radio. Installation of radiotelephone lines or comparable equipment is not required. 

These communications need not be direct between the transport and the licensee or its designee. The 

transport personnel may relay the information to the licensee through the carrier’s offices. 
Rev. 1 of RG-5.59, Page 29 

3. Requests for LLEA Assistance 

Procedures or facilities are also required to facilitate the transport personnel in obtaining 

assistance from LLEAs. Use of radiotelephone or citizens’ band radio equipment for this purpose is 

acceptable but not required. The transport personnel may alternatively use conventional telephone lines. 

Requests for assistance should be in accordance with the response procedures developed to comply with 

paragraph 73.67(e)(3)(iv). 

Content 

Describe the communications facilities and procedures to be used to ensure that communications 

are established to achieve the three purposes enumerated in paragraph 73.67(e)(3)(i). The names and 

telephone numbers of responsible individuals should be given where appropriate. Refer to established 

response procedures (Section 9.4 of Part I of this guide) as necessary. 

9.2 Minimum Transit Times [73.67(e)(3)(ii)] 

Intent 

This requirement is intended to have the shipper or receiver make a reasonable effort to ship the 

material by the fastest and most direct method possible. It is not intended to require use of dedicated 

transports or other expensive modes of travel. 

Content 

Describe the procedures and considerations that apply in the transportation planning process to 

ensure that a determined effort will be made to minimize transit times. 

9.3 Preauthorization Screening [73.67(e)(3)(iii)] 

Intent 

The intent of the requirement for preauthorization screening is to ensure that the licensee will 

have sufficient knowledge of an individual to determine his/her reliability and need for access prior to 

granting him/her authorized access to the material in transit. The selection of procedures for conducting 

this examination and the criteria employed to make judgments are the responsibility of the licensee and, 

of course, should be consistent with all local, State, and Federal laws and regulations regarding the 

protection of the privacy and other rights of the individual. The screening process may be conducted in 

the same manner as are other investigations customarily conducted by potential employers for similarly 

sensitive positions. There is no requirement for the licensee to arrange for an NRC clearance or similar 

clearance from any other government organization. Examples of procedures and criteria that may be 

employed in the screening process include holding or having recently held a government-sanctioned 

clearance; examination of past employment records (to determine any unsatisfactory employment or 

incidents that would indicate any unreliability or previous breaches of trust between the individual and 

his/her employer); endorsements or references from previous employers or colleagues that would support 

a decision for granting access or that would attest to the trustworthiness and reliability, of the individual; 

and consideration of the individual’s present employment record indicating demonstrated trustworthiness 

and reliability over an extended period of employment with the licensee. (This may be considered in the 

nature of “grandfathering.”) 
Rev. 1 of RG-5.59, Page 30 

Content 

Describe the procedures that will be used for obtaining sufficient information prior to making a 

decision on granting unescorted access authorization to those licensee employees who will be directly 

involved in the transportation or in the planning and movement control of the material. Identify by title or 

name those employees who will be screened and those who will perform the screening process. 

9.4 Response Procedures [73.67(e)(3)(iv)]

Intent 

The intent of this regulation is to help the licensee to identify those transportation incidents for 

which notification might be expected and that might affect the security of the SNM in transit and to plan 

response procedures for such situations. For example, if the shipper is informed by the carrier that 

adverse weather conditions have temporarily prevented further progress of the shipment, the licensee 

should inform the receiver of a new estimated time of arrival. 

Content 

Identify those events for which response procedures will be developed. Also, describe types of 

response to be accomplished for each event identified and the duties and responsibilities of members of 

the security organization and management for dealing with the response. Ensure that the NRC will be 

notified immediately in the event of theft or attempted theft of the material. 

9.5 Notification [73.67(e)(3)(v)] 

Intent 

The intent of this requirement is to ensure that the licensee responsible for the physical protection 

of SNM in transit will have a firm basis for deciding whether or not to initiate response procedures in the 

event a shipment becomes overdue or is lost. 

Content 

Describe the arrangements and procedures that will be used for notifying the licensee who 

arranges for the physical protection of material in transit of the arrival of the shipment at its destination or 

of any such shipment that is lost or unaccounted for after the estimated time of arrival at its destination. 

9.6 Lost Material Notification [73.67(e)(3)(vi)] 

Intent 

The intent of this requirement is to ensure that, in the event a shipment becomes overdue at its 

destination or at a scheduled stop on its itinerary and no reasonable explanation has been received by the 

licensee from the carrier regarding its status, a trace investigation will be initiated. 

Content 

Describe what procedures will be used to trace any shipment that is lost or has not arrived at a 

particular point on the shipment’s itinerary or at its final destination by the estimated arrival time. 
Rev. 1 of RG-5.59, Page 31 

9.7 NRC Notification [73.67(e)(3)(vii)]

Intent 

The intent of this requirement is to ensure that after a reasonable amount of time has elapsed with 

no explanation of the cause for the shipment’s being overdue, the NRC will be immediately notified that 

the shipment is missing or unaccounted for and advised of the actions being taken to locate the missing 

shipment. The amount of time considered reasonable before these tracing and notification procedures are 

initiated should not exceed 1 hour in any case. 

Content 

Ensure that all material determined to be lost or unaccounted for will be reported immediately to 

the appropriate NRC Regional Office in accordance with S 73.71. Ensure that notification includes 

specifying what actions are being taken to trace the shipment and that the shipper or receiver, as 

appropriate, will also be notified. 

10. Transfer and Control Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(4), which 

reads as follows: 

(e)(4) Each licensee who arranges the physical protection of strategic special nuclear material in 

quantities of moderate strategic significance while in transit or who takes delivery of this 

material free on board (f.o.b.) the point at which it is delivered to a carrier for transport, 

shall, in addition to the requirements of (e)(1), (e)(2) and (e)(3) above: 

(i) Make all shipments of the material either (A) in dedicated transports with no 

intermediate stops to load or unload other cargo and with no carrier or vehicle 

transfers or temporary storage in transit, or (B) under arrangements whereby the 

custody of the shipment and all custody transfers are acknowledged by signature, 

and 

(ii) Maintain the material under lock, or under the control of an individual who has 

acknowledged acceptance of custody of the material by signature. 

10.1 Carrier Transfers [73.67(e)(4)(i)] 

Intent 

The intent of this requirement is to ensure continuity in the assignment and acceptance of 

personal responsibility for shipments of strategic special nuclear material (high-enriched uranium and 

plutonium). The requirements of paragraph 73.67(e)(4) do not apply to LEU. This continuity may be 

provided by (1) shipping the material in a dedicated transport vehicle so that the material would be under 

the continuous control of the same individual(s) for the duration of the shipment or (2) arranging for each 

individual who assumes custody of the shipment to indicate acceptance of personal responsibility for the 

material by signature. 

Shipment of the material in a dedicated transport means there should be no intermediate stops to 

load or unload other cargo and no carrier or vehicle transfers or temporary storage en route. However, 
Rev. 1 of RG-5.59, Page 32 

material other than the SNM being shipped may be carried in the transport’s cargo compartment provided 

it does not detract from the security of the shipment. 

For shipments by general freight, this requirement may be satisfied by arranging for “signature 

security service” with a high surveillance feature, which is provided by many air and motor freight 

carriers. 

Content 

Indicate how this requirement would be met for each of the modes of shipment to be employed. 

Indicate how this requirement would continue to be met in emergency situations by reference to the 

emergency response plans included in Section 9.4 of the plan. If signature service is to be employed, 

describe the type of service that will be provided by the particular carrier chosen for the shipment. If a 

dedicated transport is to be used to satisfy this requirement, affirm that the same individual(s) will 

maintain responsibility for the shipment from the point of origin to its destination. 

10.2 Control of Shipments [73.67(e)(4)(ii)]

Intent 

The intent of this requirement is to ensure that SSNM is not misrouted or mishandled by 

unauthorized individuals during the course of a shipment and to facilitate early detection and recovery of 

the material in case of loss or theft. This can be achieved by maintaining the material under lock or under 

the control of a responsible individual whenever the material is not secured in a locked compartment. 

Maintaining the shipment in a locked compartment would normally be possible only for 

shipments in dedicated transports. In this case, the cargo compartment should be locked upon 

embarkation and unlocked only after arrival at the shipment’s destination. If the locked cargo 

compartment is left unattended for an extended period that might allow the unauthorized removal of the 

material, the individual(s) responsible for the shipment should establish upon returning to the transport 

that the compartment has remained continuously under lock. This can be done by examining the cargo 

compartment lock for signs of tampering, examining seals on the cargo compartment, or opening the 

compartment and ensuring that the material is intact. 

For general freight shipments, during which the cargo compartment may be opened frequently to 

load or unload other cargo, locking of the compartment may not be practical on a continuous basis. When 

the shipment is not maintained under lock, the material is required to be in a sealed cargo compartment or 

maintained under the control of an individual who has indicated by signature his/her acceptance of 

responsibility for the shipment. This individual should be the same person who has signed for custody of 

the shipment in compliance with paragraph 73.67 (e)(4)(i). For air shipments in which the cargo 

compartments are not locked, an individual responsible for the shipment is not required to accompany the 

shipment during flight provided a responsible individual maintains control of the shipment during the 

entire time the shipment remains at each air terminal. During unscheduled stops at air terminals not on 

the shipment’s itinerary, the shipment may be considered to be under the control of the flight crew 

provided the shipment is not offloaded and a member of the flight crew remains with the aircraft at all 

times. 

Maintaining the shipment under control means (1) ensuring the shipment is properly routed at 

transfer points, (2) keeping the material under lock or under surveillance, which would include 

periodically (normally at least every 2 hours) checking the shipment to ensure it has not been misplaced 

or tampered with, and (3) ensuring that the licensee or its designee is notified immediately if the shipment 
Rev. 1 of RG-5.59, Page 33 

is determined to be missing. The licensee should ensure that the signature security service or other 

service provided by the carrier under normal or special arrangements includes all three of these elements 

of control. 

Content 

Indicate the periods during which the shipment will be maintained under lock and those during 

which it will be maintained under the control of a responsible individual. Describe the instruments to be 

used for documenting acknowledgment of custody of the material by individuals assigned responsibility 

for controlling the shipment. Also, describe the arrangements made with carriers to ensure that the 

individuals they assign to maintain control of the material do so in accordance with the three elements of 

control described above. Refer to the emergency response procedures developed in accordance with 

paragraph 73.67(e)(3)(iv) as necessary. 

11. Export Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(5), which 

reads as follows: 

(e)(5) Each licensee who exports special nuclear material of moderate strategic significance 

shall comply with the requirements specified in § 73.67(c), (e)(1) and (e)(3) and.(e)(4). 

Use Chapters 7, “Material Transportation Requirements,” 9, “In-Transit Physical Protection 

Requirements,” and 10, “Transfer and Control Requirements,” of Part I of this guide to describe the 

security procedures that will be used to protect the material up to the point where the receiver accepts 

physical protection responsibility for the shipment. 

12. Import Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(6), which 

reads as follows: 

(e)(6) Each licensee who imports special nuclear material of moderate strategic significance 

shall: 

(i) Comply with the requirements specified in § 73.67(c), (e)(2), (e)(3) and (e)(4), 

and 

(ii) Notify the exporter who delivered the material to a carrier for transport of the 

arrival of such material. 

12.1 Security Requirements [73.67(e)(6)(i)] 

Use Chapters 8, “Receiver Requirements—Transportation,” and 9, “In-Transit Physical 

Protection Requirements,” of Part I of this guide to describe the security procedures that will be used to 

protect the material from the first point at which the shipment is picked up inside the United States. 
Rev. 1 of RG-5.59, Page 34 

12.2 Notification [73.67(e)(6)(ii)] 

Intent 

The intent of this requirement is to ensure that the exporter is notified that the material has arrived 

safely. 

Content 

Describe the procedures to be used for notifying the exporter of the material that the shipment has 

been received. 

13. Orders To Delay SSNM Shipments 

This chapter provides guidance on meeting the requirements of paragraph 73.67(e)(7) and 

S 73.72 (as it may apply to shipments of special nuclear material of moderate strategic significance). 

These requirements read as follows: 

(e)(7) If, after receiving advance notice pursuant to S 73.72 from a licensee planning to import, 

export, transport, deliver to a carrier for transport in a single shipment, or take delivery at 

the point where it is delivered to a carrier, special nuclear material of moderate strategic 

significance containing in any part strategic special nuclear material, it appears to the 

Commission that two or more shipments of special nuclear material of moderate strategic 

significance, constituting in the aggregate an amount equal to or greater than a formula 

quantity of strategic special nuclear material, may be en route at the same time, the 

Commission may order one or more of the shippers to delay shipment according to the 

following provisions: 

(i) The shipper shall provide to the Commission, upon request, such additional 

information regarding a planned shipment as the Commission considers pertinent 

to the decision on whether to delay such shipment. 

(ii) The receiver of each shipment, or the shipper if the receiver is not a licensee, 

shall notify the Director of the appropriate Nuclear Regulatory Commission 

Regional Office listed in Appendix A by telephone, no later than 24 hours after 

arrival of such shipment at its final destination, or after such shipment has left the 

United States as an export, to confirm the integrity of the shipment at the time of 

receipt or exit from the United States. 

(iii) The Commission shall notify the affected shippers no later than two days before 

the scheduled shipment date that a given shipment is to be delayed. 

(iv) Shipments of special nuclear material of moderate strategic significance which 

are protected in accordance with the provisions of §§ 73.20, 73.25, and 73.26 

shall not be subject to orders to delay shipment nor considered to constitute a 

portion of an aggregate formula quantity of strategic special nuclear material for 

the purposes of determining whether any shipments must be delayed. 
Rev. 1 of RG-5.59, Page 35 

§ 73.72 Requirement for advance notice of shipment of special nuclear material. 

(a) Each licensee who plans to import, export, transport, deliver to a carrier for transport in a 

single shipment, or take delivery, at the point where it is delivered to a carrier, the 

following materials, shall notify the Director of the appropriate Nuclear Regulatory 

Commission Regional Office listed in Appendix A by U.S. Mail, postmarked at least 7 

days in advance of the shipping date: (1) formula quantities of strategic special nuclear 

material, or (2) special nuclear material of moderate strategic significance containing in 

any part strategic special nuclear material. 

(b) The following information shall be furnished in the advance notice: shipper, receiver, 

carrier(s), estimated dates and time of departure and arrival, transfer point(s), and 

mode(s) of shipment. 

(c) The Director of the appropriate Nuclear Regulatory Commission Regional Office shall 

also be notified by telephone 7 days in advance of the shipping date that an advance 

shipping notice has been sent by mail, and of any changes to the shipment itinerary prior 

to the shipment date. Road shipments or transfers with one-way transit lines of 1 hour or 

less in duration between installations of a licensee are exempt from the requirements of 

this section. 

It is noted that shipments of SNM of moderate strategic significance consisting entirely of 

uranium enriched in the isotope U-235 to 10 percent or more but less than 20 percent are not subject to 

these requirements. 

Of the requirements detailed above, only paragraph 73.67(e)(7)(ii) and § 73.72 should be 

addressed in the licensee’s physical security plan. This is discussed in Section 13.1. 

1. Criteria for Delaying Shipments 

Under the provisions of paragraph 73.67(e)(7) of the regulations, the NRC has authority to order 

delays in certain shipments of SNM of moderate strategic significance. It is the intention of the NRC to 

exercise this authority only when necessary to protect the public health and safety from the possible 

consequences of the theft of a formula quantity of SSNM. Since the number of affected shipments 

expected annually is quite low, shipment delays are expected to be ordered very rarely. In most cases, 

licensees will be able to clear shipment dates with the NRC staff far in advance so that potential conflicts 

in the scheduling of shipments can be avoided. However, shipment delays may be required on an 

emergency basis if a previous shipment is determined to be missing and cannot be accounted for before 

the next scheduled shipment is to depart. When a scheduling conflict that cannot be resolved voluntarily 

arises, the following criteria will be applied to determine which shipments will be delayed: 

a. Total time needed to complete the shipment, 

b. The impact of a schedule delay on the use of the SNM at the delivery site, 

c. Planned routing of the material, 

d. The relationship of the material to the national defense or to other essential programs in 

the nation’s interest, 
Rev. 1 of RG-5.59, Page 36 

e. The possible impacts on the shipper/carrier relationship with regard to availability of 

shipment vehicles and other special arrangements that would be difficult to reschedule, 

and 

f. How far in advance of the proposed shipment date the NRC was notified of the intent to 

make the shipment. 

2. NRC Requests for Additional Shipment Information 

In order to apply the decision criteria listed above, the NRC has the authority under paragraph 

73.67(e)(7)(i) to request additional information from licensees regarding a planned shipment of SSNM 

that may be subject to a possible delay order. Such information requests may be made at any time prior to 

a scheduled shipment either by telephone or in writing. 

3. NRC Notification of Shipment Delay Orders to Licensees 

Under paragraph 73.67(e)(7)(iii), the NRC will normally notify licensees that a shipment is to be 

delayed no later than 2 days before a shipment is scheduled to depart. In practice, it is expected that 

potential conflicts will be resolved much before the date of a planned shipment after appropriate NRC 

consultations with the prospective shippers. However, in an emergency the NRC may order delays in 

shipments or other responsible action at any time it may deem necessary or desirable to promote the 

common defense and security, protect health, or minimize danger to life or property. 

13.1 Notification of Receipt of SSNM [73.67(e)(7)(ii)] 

Intent 

The intent of this notification requirement is to ensure that the NRC is promptly informed of the 

receipt of a shipment of SSNM subject to paragraph 73.67(e)(7) or, in the case of export shipments, 

informed that the shipment has left the United States safely. Based on this information, the NRC can 

permit subsequent shipments subject to paragraph 73.67(e)(7)(ii) to commence with the knowledge that a 

formula quantity of SSNM will not be at risk in a small number of simultaneous shipments. This will 

also ensure that shipment delay orders will not have to be imposed unnecessarily for failure to confirm 

that a previous shipment is no longer at risk. Compliance with this requirement is not a substitute for 

compliance with other notification requirements under paragraph 73.67(e)(2)(Ii). 

Content 

Affirm that, in the case of a shipment of SNM of moderate strategic significance containing in 

any part SSNM, arrangements are made to obtain confirmation of the integrity of the shipment at the 

point where the material leaves the United States as an export or at its final destination. Describe the 

procedures for accomplishing this and notifying the NRC of the shipment’s status at the time of receipt or 

exit from the United States. Include the names or titles of individuals who will be responsible for 

ensuring that the required confirmation is made and the proper notification is provided to the NRC. 
Rev. 1 of RG-5.59, Page 37 

PART II SPECIAL NUCLEAR MATERIAL OF LOW 

STRATEGIC SIGNIFICANCE 

1. Use and Storage Area at a Fixed Site 

This chapter provides guidance on meeting the requirement of paragraph 73.67(f)(1), which is as 

follows: 

(f)(1) Store or use such material only within a controlled access area. 

A controlled access area (CAA) is defined in paragraph 73.2(z) as “any temporarily or 

permanently established area which is clearly demarcated, access to which is controlled and which affords 

isolation of the material or persons within it.” “Access control” means measures used to allow only 

specified personnel, materials, and vehicles ingress into and egress from a given area, while “isolation” 

refers to measures taken to deter persons, materials, or vehicles from entering or leaving a given area 

through other than established access control points. Thus, a CAA includes provisions for both isolation 

and access control. In some cases, isolation or access control systems may also serve the purpose of 

aiding in the detection of unauthorized penetration or activities1

 within the CAA. Therefore, these 

detection-related considerations are also alluded to in this chapter. 

In the discussion that follows, CAAs intended for the use and possible storage of SNM of low 

strategic significance are discussed separately from those intended solely for the storage of such SNM. 

Although there is no difference in the requirements for these two different applications of the CAA, it is 

recognized that the means used to isolate the material and to control access may differ markedly for use 

areas compared with storage areas and therefore warrant separate discussion. 

1.1 Areas for Use and Temporary Storage [73.67(f)(1)] 

This section discusses CAAs intended primarily for the use and temporary storage of SNM of low 

strategic significance. These may be temporarily established to meet transitory or intermittent SNM use 

requirements or they may be permanently established. Permanently established CAAs for use of SNM 

may also be used for storage for short intervals between periods of usage. “Use” means that the material 

is undergoing processing (e.g., fuel fabrication, irradiation in a reactor) or utilization of its properties in 

conjunction with experimental equipment (e.g., equipment used for research or educational laboratory 

experiments). Different isolation/access control measures may be used for periods during which the area 

is occupied versus unoccupied. 

1. Temporarily Established CAAs 

Temporarily established CAAs for the use of SNM need not have permanent barriers at their 

boundaries. Isolation of the material and persons using the material may be provided by office partitions, 

cordons, or other devices used to warn passersby of the restricted nature of the area. Access control can 

be effected through surveillance or supervision of the area by those who are using the SNM and who are 

responsible for the material. However, the provision of access control through personal supervision is 

suitable only for those situations in which the size of the CAA and the number of persons to be admitted 

are sufficiently small and in which the CAA is suitably configured to make such procedures practical. 

When material located in a temporarily established CAA is to be left unattended (i.e., because it 

is impractical to replace the material in a CAA designed for long-term storage of the material), access 

control and improved isolation for the temporary CAA may be provided to substitute for the discontinued 

personal supervision over the material. (In addition, provisions must also be made for satisfying the 
Rev. 1 of RG-5.59, Page 38 

monitoring requirement of paragraph 73.67(f)(2).) Improved isolation can sometimes be provided by 

increasing the penetration resistance of existing barriers (e.g., locking doors and windows, placing the 

material in a locked drawer or supply room). Access control may be provided by any of the measures 

suggested below for permanently established CAAs left unattended; some of these suggestions may be 

more suitable for temporary use than others. If no suitable barrier is available to provide isolation, 

material left unattended may be protected by a motion alarm covering the area immediately surrounding 

the material. This improved detection capability would be considered an acceptable substitute for the 

rudimentary isolation provided by temporary barricades, cordons, signs, and other less substantial means 

of isolation that may be used on a temporary basis. 

2. Permanently Established CAAs 

Permanently established CAAs for the use and temporary storage of SNM of low strategic 

significance would most likely provide isolation for the SNM through the use of permanent barriers. 

These could consist of fences; gates or freestanding walls for exterior areas; or exterior or interior 

building walls, locked doors, windows, bars, grillwork; or other barriers for interior areas. Such barriers 

are not required to meet the more stringent criteria for physical barriers used for the protection of formula 

quantities of strategic special nuclear material (SSNM).2

 However, good security management practice 

would, dictate that the barrier be substantial enough to deter casual passersby from unauthorized 

penetration. If the barriers are also designed to aid in detection, the criteria for penetration resistance or 

tamper indication in accordance with the specific monitoring procedures to be used also apply. 

Access control for permanently established CAAs during periods they are occupied can be 

provided by personal supervision. However, when these areas are unoccupied or when the size, 

configuration, or numbers of persons intended to be admitted to the area make personal supervision 

impractical, other means of access control may be called for. Some of the additional access control 

measures that may be used for permanently established CAAs in these situations are: 

• Stationing a watchman at CAA access control points, 

• Limiting distribution of keys, keycards, or combinations to locks on doors and gates, 

• Using a coded badging system to identify authorized personnel at CAA access control points, 

• Controlling locked CAA doors and gates by use of remote surveillance (e.g., intercom or CCTV) 

by personnel stationed at a centrally located access control facility, or 

• Controlling access of personnel, material, and vehicles into CAAs by other means. 

It is expected that large facilities (e.g., fuel processing facilities) will have more complex 

isolation and access control systems than small facilities (e.g., research facilities) in order to achieve 

comparable levels of protection. 

Content 

Describe the CAAs where the material will be used. Indicate under what conditions CAAs will 

be established on a temporary basis. State whether each CAA will also be used for storage. For each 

CAA identified, provide the following information: 

1. A description of the area and its features relative to other facility features, showing the 

normal routes of ingress to each CAA (Including a scale diagram). 
Rev. 1 of RG-5.59, Page 39 

2. Descriptions of physical barriers, cordons, walls, partitions, or other means of providing 

isolation of the CAA, and channeling entry through established access control points into 

the CAA. 

3. The means and criteria used for controlling access into the CM at established access 

control points. 

4. If more than one CAA is designated, the types of material normally used in each CAA; 

for temporarily established CAAs, the types of activities normally performed within each 

area. 

1.2 Areas for Permanent Storage [73.67(f)(1)] 

Intent 

CAAs normally used only for storage of SNM are described in this section. Such CAAs may be 

very limited in size since they need only contain the material itself, and access to them is expected to be 

infrequent. Where small amounts of material are involved, the CAA may consist of relatively small 

containers such as security cabinets, safes, and locked closets or supply rooms. 

Isolation for CAAs intended only for storage usually will be provided by the penetration-resistant 

features of the perimeter barriers or container walls of the CAAs. Such barriers and container walls are 

not required to meet the more stringent criteria for physical barriers used for the protection of formula 

quantities of SSNM. However, good security management practice would dictate that the barrier be 

substantial enough to deter casual passersby from unauthorized penetration. If the barriers are also 

designed to aid in detection, the criteria for penetration resistance or, tamper indication in accordance 

with the specific monitoring procedures to be used also apply. 

In determining the level of isolation and access control for such CAAs, the minimum time 

required for extricating SNM from its storage location in relationship to the licensee’s time of detection 

and assessment may need to be taken into account (e.g., fuel assemblies stored in shipping casks or nonself-protecting fuel residing in nonpower reactor cores). The bulkiness, massiveness, and difficulty of 

movement or disassembly of fresh fuel elements or other forms of low-enriched uranium (LEU) in large 

quantities such as shipping casks or assemblies may pose sufficient difficulty to persons attempting 

unauthorized removal within a reasonable time period (relative to CAA monitoring procedures) that they 

may be considered to provide isolation. Control of access to special equipment and vehicles capable of 

handling and transporting such items may also be included as integral elements of the access control 

program for the CAA. 

Access control procedures for CAAs designated exclusively for storage are expected to be similar 

to those described in the previous section for periods when use-type CAAs are unoccupied. 

It is expected that large facilities (e.g., fuel processing facilities) will have more complex 

isolation and access control systems than small facilities (e.g., research reactors) in order to achieve 

comparable levels of protection. 

An illumination level is recommended for the CAA that is sufficiently uniform and bright to 

detect penetration of or tampering with the CAA containment (in the case of a security cabinet) or 

unauthorized penetration of or activities within the CAA (in the case of a vault-type room or its 

equivalent). 
Rev. 1 of RG-5.59, Page 40 

Content

(This section needs to be completed only for CAAs designated exclusively for storage of SNM. 

CAAs designated for both use and storage are to be described as recommended in Section 1.1 of Part II of 

this Standard Format.) 

Describe the CAAs where the material will be stored, if different from those previously described 

for use. For each such CAA, provide the following information: 

1. A description of the area and its features relative to other facility features showing the 

access control points for the CAA (including a scale diagram). 

2. The physical barriers, container walls, or other features, that demarcate the perimeter of 

the CAA and channel entry through only established access control points. If access 

control is provided by virtue of the bulkiness, massiveness, and difficulty of disassembly 

of a container or object serving as a CAA, describe the facts relied upon to support such a 

determination. 

3. The means and criteria used for controlling access to the CAA at established access 

control points. 

4. If more than one CAA is designated for the storage of the material, the types of material 

normally to be stored in each area. 

2. Detection Devices and Procedures at a Fixed Site 

This chapter provides guidance for meeting the requirement of paragraph 73.67(f)(2), which is as 

follows: 

(f)(2) Monitor with an intrusion alarm or other device or procedures the controlled access areas 

to detect unauthorized penetrations or activities. 

The purpose of this monitoring activity as stated in paragraph 73.67(a)(2) is to provide “early 

detection and assessment of unauthorized access or activities by an external adversary within the 

controlled access area...” and “early detection of removal of special nuclear material by an external 

adversary from a controlled access area.” This should be done to achieve the objective of minimizing the 

possibilities for unauthorized removal of special nuclear material “consistent with the consequences of 

such actions,” as stated in paragraph 73.67(a) of the effective rule. Thus, the earliness of detection 

afforded by the licensee’s physical protection system may vary depending on the nature and quantity of 

the material susceptible to unauthorized removal. Further discussion of the earliness of detection required 

for possible thefts of different types and quantities of special nuclear material of low strategic significance 

is provided in Section 2.1 of Part II of this guide. 

2.1 Earliness of Detection [73.67(a)] 

The criteria used for determining the earliness of detection for unauthorized access, activities, or 

removal of SNM from CAAs will depend on an assessment of the magnitude of the consequences 

associated with possible misuse of the type and quantity of material that could be removed in a given theft 

attempt. For SNM of low strategic significance, three distinct cases are considered: 

1. Gross theft of low-enriched uranium (LEU)6

 
Rev. 1 of RG-5.59, Page 41 

2. Minor theft of LEU. 

3. Theft of strategic special nuclear material (SSNM) (i.e., SNM of low strategic 

significance other than LEU). 

Gross theft of LEU refers to the theft of LEU in a sufficiently large quantity that it could yield 

upon further enrichment or other processing enough material of the type and quantity needed to construct 

a clandestine fission explosive (CFE) device. This quantity may vary depending on the enrichment and 

physical and chemical form of the feed material but may roughly be estimated as an amount containing 

about 75 kilograms of the isotope U-235. Because the most serious consequences to the public health and 

safety could occur from a theft of this magnitude, a system that would detect a theft sufficiently early to 

allow for prompt recovery is called for. The NRC believes that, because of the large quantity of material 

involved and with proper detection systems and procedures, the licensee would be capable of detecting a 

gross theft of LEU between the time of the actual theft and the time it is transported off site. 

Minor theft of LEU refers to thefts involving much smaller quantities of LEU such as could be 

removed by one or two persons in a private vehicle or on one’s person. These minor thefts are significant 

only to the extent that they could be repeated periodically to eventually accumulate an aggregate quantity 

similar to that which might be obtained in a gross theft. The required degree of earliness of detection of 

such thefts is related to the time that would be needed by the adversary to obtain a gross amount through 

repeated thefts. If the amount taken in each of a series of daily thefts is very small, the ultimate time of 

detection could be as long as 6 months--the interval between material inventories as required by Part 70. 

For larger quantities that could be removed in a single theft, but still much less than would constitute a 

gross theft, it would be reasonable to expect that one in a series of such thefts would be detected before a 

gross amount could be removed. 

Licensees who possess less than gross quantities of LEU need not provide for early detection of a 

single theft of a gross quantity, but the capability for detecting multiple thefts is as important as it is for 

those licensees possessing gross quantities. 

Thefts from a single facility of SSNM (SNM of low strategic significance other than LEU) are 

limited by definition to quantities that could not be used to construct a nuclear explosive device; thefts of 

similar quantities of SSNM from several different facilities could, however, lead to the accumulation of 

an aggregate quantity that would permit such illicit use. (The consequences of a single theft of such 

material would have minimal impact on the public health and safety.) Therefore, detection of such thefts 

is required sufficiently early to ensure early notification to the NRC. The NRC in turn can then notify 

other licensees of the need to implement appropriate response measures to prevent the accumulation by a 

single adversary of a formula quantity of material through multiple thefts from different facilities. The 

NRC believes that there are detection systems and procedures that would allow the licensee to detect a 

theft of SSNM within approximately 2 hours. 

2.2 Monitoring Controlled Access Areas [73.67(f)(2)] 

Intent 

Monitoring CAAs where the material is used will require a capability for early detection of (1) 

unauthorized penetration of the CAA perimeter, (2) unauthorized activities within the CAA, (3) 

unauthorized removal of SNM from the CAA, or (4) some combination of these, by an external 

adversary. For purposes of this guidance, an external adversary is any person not employed by the 

licensee or one of its contractors to report for work on a regular basis at the licensee’s site and who is not 

directly involved in the processing or other authorized use of the material in connection with his/her 
Rev. 1 of RG-5.59, Page 42 

assigned duties. For purposes of this definition, graduate and other students assigned by the licensee at an 

educational or research institution to assume responsibility for the regular handling of the material would 

not be considered an external adversary. 

The choice of particular safeguards measures to be included in the CAA monitoring system will 

depend on a number of different site-specific factors such as whether the measure is to function while the 

area is occupied or unoccupied, the size of the area, the types of functions performed in the area, the level 

of traffic into and out of the area, etc. Many of the available safeguards measures that may be employed 

in the CAA monitoring system are described in various regulatory guides and NUREG documents issued 

by the NRC. Specifically, the Fixed Site Physical Protection Upgrade Rule Guidance Compendium8

provides guidance on selection, installation, and implementation of monitoring devices and procedures 

relative to physical protection of formula quantities of SSNM. This guidance is also applicable to 

monitoring equipment and procedures for CAAs at fixed sites having less than formula quantities of SNM 

with regard to individual physical protection measures. It is recognized, however, that from a systems 

point of view, this body of guidance intended to support the Upgrade Rule may emphasize a much greater 

level of redundancy and diversity than would be required for the protection of SNM of moderate and low 

strategic significance.9

 The following paragraphs give illustrations of various monitoring systems that 

can be used to provide the earliness of detection discussed in Section 2.1 of Part II of this guide. 

1. Early Detection of Gross Theft of LEU 

Early detection of gross theft of LEU means detection during the attempted theft. This may be 

accomplished by using intrusion alarms or other monitoring devices in the following applications: 

• Fence or buried line perimeter detection systems at the CAA boundaries. 

• Door and window alarms (e.g., balanced magnetic switches) for CAAs within buildings and 

alarms on emergency exit doors equipped with crash bars. 

• Volumetric interior motion detection systems for unoccupied CAAs or portions of CAAs within 

buildings. 

In many cases, security procedures may be employed as substitutes for some or all of the devices 

that could be employed to fulfill the monitoring requirement for the CAA. Security procedures may be 

especially attractive in protecting against the theft of gross quantities of LEU located outside buildings 

where intrusion alarms may more easily be circumvented by an external adversary. Typical security 

procedures that may be employed for detection of attempts at unauthorized removal of gross quantities of 

LEU include the following: 

• Periodic patrols of CAA perimeters and areas within the CAA by watchmen. 

• Surveillance (escorting) of no licensee vehicles capable of transporting gross quantities of LEU 

away from the site. 

 

8

 The compendium was issued in conjunction with the Physical Protection Upgrade Rule. It is intended to assist the 

licensee in the development and implementation of safeguards physical protection and transportation protection plans. 

Copies are available for inspection at the Commission’s Public Document Room, 1717 H Street NW., Washington, 

D.C. 

9

 Tamper-safing of devices intended for use at facilities having less than formula quantities of SSNM need protect only 

against the external adversary; to the extent such a distinction can be made for a given device, this represents a 

relaxation in tamper-safing requirements relative to protection of formula quantities. 
Rev. 1 of RG-5.59, Page 43 

• Continuous (without interruption) or continual (intermittent) surveillance of the CAA, or a given 

portion of the CAA that contains a gross quantity of LEU, by designated supervisory or other 

licensee employees. (These surveillance responsibilities could be undertaken in addition to the 

employee’s normal functions provided they can both be discharged adequately.) 

• Periodic inspections to confirm continued integrity of barriers, gates, loading bay doors, etc., 

through which unauthorized removal of gross quantities of LEU could be effected. 

• Inspection of large vehicles leaving CAAs to ensure they are not used for unauthorized removal 

of a gross quantity of LEU. 

Where procedures involve periodic patrols or inspections, the amount of time that would be 

required for an adversary to complete the removal of a gross quantity of LEU may be used to govern the 

interval between inspections. For example, if a given number of a certain type of container of LEU would 

have to be individually loaded onto a truck in order to effect removal of a gross quantity of LEU and the 

time required for such loading is determined to be in excess of 2 hours, then a 2-hour guard patrol of the 

given area would be considered to meet the earliness-of-detection guideline for the subject material. 

A combination of these and perhaps other measures could satisfy the early detection criterion for 

gross theft of LEU if it could be shown that an external adversary could not obtain unauthorized access to 

the SNM without being detected by at least one intrusion alarm component. 

2. Early Detection of Minor Theft of LEU 

The criteria for early detection of minor theft of LEU can be satisfied by a monitoring program 

that provides a sufficiently high probability of detection of one in a series of minor thefts so it is 

implausible that an adversary would be able to obtain in the aggregate a gross quantity of LEU. Such a 

capability could be provided in whole, or in part; by the same monitoring program designed to detect 

gross theft. Additional measures that might be included in the monitoring program to protect against 

minor theft include the following: 

• Exit searches of nonlicensee vehicles capable of transporting hand-carried quantities of LEU (on 

a random or general basis). 

• Administrative control of materials removed from controlled areas where easily concealed or 

hand-carried items containing LEU are available. 

• Item count inventories more frequent than those currently required under Part 70. 

• Procedures directing regular employees to be aware of unauthorized persons in their work areas 

and to report the presence of such persons to supervisory or security personnel. (A coded 

badging program would support this measure.) 

• Escorting of visitors and other unauthorized persons entering CAAs. 

• Watchman patrols to detect unauthorized persons within the CAA. 

• SNM doorway monitors at all personnel access control points. 

These are not required measures but illustrations of how the monitoring program for detecting 

gross theft of LEU may be extended to include the capability for early detection of minor theft of LEU. 
Rev. 1 of RG-5.59, Page 44 

One or more of these measures may be employed, but probably not all of them would be needed for any 

one installation. 

3. Early Detection of Theft of SSNM (SNM of low strategic significance other than LEU) 

For facilities where it is necessary to protect against thefts of SNM of low strategic significance 

other than LEU (SSNM), earliness of detection is discussed in Section 2.1 of this chapter. The physical 

protection system in this case may differ considerably from that designed to protect LEU. The sites are 

likely to be small research-oriented facilities such as nonpower reactors and educational institutions. 

Also, there is likely to be much less material available, and authorized access to it may be less frequent. 

Detection devices such, as interior motion detector systems, balanced magnetic switches, etc., could be 

used to monitor relatively small CAAs where the number of established access control points is very 

limited. 

Procedures may also be used to protect against thefts of SNM in this subcategory. Since 

watchman patrols inherently allow unguarded intervals during which an external adversary could 

conceivably obtain access to the CAA, remove a small amount of material, and leave before being 

discovered, the inspection procedure may (a) be sufficiently frequent to ensure an external adversary 

could not complete a successful theft of the material during the unguarded intervals, (b) provide for an 

irrevocable indication of the CAA barrier having been tampered with (as with a seal or by observation of 

damage done to the barrier), or (c) provide for an item count inventory or other accounting for the 

material as part of the inspection. Some examples are given below: 

• After having left material unattended in an experimental setup in a classroom used as a temporary 

CAA, the instructor returns after 2 hours and verifies that the material is still in place. 

• A small quantity of material is stored in a security cabinet for several months at a time without 

authorized access. Every 2 hours a watchman comes around to inspect the cabinet to ensure that 

the lock is secure and the cabinet has not been tampered with. If a suitable combination or other 

pick-resistant lock is not used, the watchman also inspects a tamper-indicating seal to verify that 

the container, has not been tampered with. 

• During periods when a nonpower reactor is left unattended, a watchman comes around every 

2 hours and checks that none of the fuel elements have been removed by unauthorized persons. If 

a person working during off-hours in the vicinity of the reactor is encountered, appropriate 

identification is requested. 

• While a nonpower reactor is being used, the supervisor ensures that he/she or his/her designee is 

not away from the reactor for a period longer than 30 minutes, a period he/she estimates would be 

minimally required for a person to secure fuel elements in the core that were not self-protecting 

by virtue of their having been sufficiently irradiated. 

• During periods when excess fuel is left unattended in a storage closet at a nonpower reactor 

facility, an alarm system is activated that would annunciate if anybody tried to penetrate the 

closet without proper authorization. 

During periods when the material is being used under the direct supervision of authorized 

personnel, the monitoring requirement is satisfied by virtue of the continuous surveillance by the 

authorized personnel. 
Rev. 1 of RG-5.59, Page 45 

Content 

For each of the CAAs described previously (see Chapter 1 of Part II of this guide), provide the 

following information regarding the measures taken to fulfill the monitoring requirement of paragraph 

73.67(f)(2): 

1. Describe any devices employed by specifying the type of device, its installed location, 

the type and location of annunciation, its intended area of coverage, and its tamperresistant features. Refer, if desired, to existing filed security plans, regulatory guides, or 

NUREG documents. 

2. Describe any procedures employed to monitor the CAA or portions thereof, including the 

categories of persons who will execute the procedures, the frequency of inspections or 

rounds of patrol, the basis for the determination of such frequencies, and the occasions 

upon which the procedures are intended to be implemented. Also indicate the features of 

the CAA (e.g., barriers, locks, seals) that will play a role in the way the procedures are 

used. 

3. Explain how the combination of procedures and devices used to monitor each CAA 

meets the criteria for early detection of theft by an external adversary relative to the type 

of material found in each CAA. 

3. Security Response at a Fixed Site 

This chapter provides guidance on meeting the requirement of paragraph 73.67(f)(3), which is as 

follows: 

(f)(3) Assure that a watchman or offsite response force will respond to all unauthorized 

penetrations or activities. 

Intent 

The intent of this requirement is to ensure that, in the event of a security incident, someone will 

be available to assess alarms or any unauthorized penetrations or activities and, if warranted, notify the 

NRC, the local law enforcement authorities, and the responsible person in licensee management. Early 

detection and notification of any missing material will help facilitate its prompt recovery. For the purpose 

of this regulation, an offsite response force can be a local law enforcement agency or a contract guard 

service. 

Content 

Describe the security organization that will be responsible for assessing and responding to any 

unauthorized penetrations or activities. Ensure that at least one guard, watchman, or member of an offsite 

response force will respond to all unauthorized penetrations or security incidents at the CAAs. 
Rev. 1 of RG-5.59, Page 46 

4. Response Procedures at a Fixed Site 

This chapter provides guidance on meeting the requirements of paragraph 73.67(f)(4), which 

states: 

(f)(4) Establish and maintain response procedures for dealing with threats of thefts or thefts of 

such material. 

Intent 

The intent of this regulation is to help the licensee to identify those security incidents that could 

result in the loss of SNM of low strategic significance and to develop response procedures to prevent or 

reduce the likelihood of such a loss. Some types of incidents that should be considered and for which 

response procedures should be developed are: 

1. Situations that could possibly lead to theft of SNM (e.g., civil disturbance). 

2. Discovery that the security system has been breached. 

3. Discovery that some SNM is missing. 

Content 

Identify those events for which response procedures will be developed. Also describe the type of 

response to be accomplished for each event identified and the duties and responsibilities of the security 

organization and management involved in the response. Ensure that the NRC will be notified 

immediately in the event of theft or attempted theft of the material. Describe what local law enforcement 

assistance is available, their response capabilities, and any agreements made with them to respond in the 

case of theft of the material. 

5. Material Transportation Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(g)(1), which are 

as follows: 

(g)(1) Each licensee who transports or who delivers to a carrier for transport special nuclear 

material of low strategic significance shall: 

(i) Provide advance notification to the receiver of any planned shipments specifying 

the mode of transport, estimated time of arrival, location of the nuclear material 

transfer point, name of carrier and transport identification, 

(ii) Receive confirmation from the receiver prior to commencement of the planned 

shipment that the receiver will be ready to accept the shipment at the planned 

time and location and acknowledges the specified mode of transport, 

(iii) Transport the material in a tamper-indicating sealed container, 

(iv) Check the integrity of the containers and seals prior to shipment, and 

(v) Arrange for the in-transit physical protection of the material in accordance with 

the requirements of § 73.67(g)(3) of this part, unless the receiver is a licensee and 

has agreed in writing to arrange for the in-transit physical protection. 
Rev. 1 of RG-5.59, Page 47 

5.1 Advance Notification [73.67(g)(1)(i)] 

Intent 

The intent of this paragraph is to require the shipper to preplan the transportation of the material 

and inform the receiver of his plans prior to shipment. This is the first of several transportation 

requirements that will allow the receiver to take delivery of the material as planned or to help ensure 

traceability of any missing material. 

Content 

The licensee should ensure that, prior to each shipment of material, the receiver will be notified of 

the impending shipment and provided the following types of information: 

1. Mode of transport (e.g., truck, plane, train, or ship), 

2. Estimated time of arrival, 

3. Location where material is to be transferred to receiver, 

4. Name of carrier, and 

5. Transport identification (e.g., truck, train, or flight number; ship name). 

5.2 Receiver Confirmation [73.67(g)(1)(ii)] 

Intent 

The intent of this requirement is that, prior to shipment, the transporter will be assured that the 

receiver is ready to accept the shipment at the planned time and location and has acknowledged the mode 

of transport.. 

Content 

Describe what procedures will be used to ensure that shipment of material does not take place 

until the receiver acknowledges the planned shipment and mode of transport and readiness to accept the 

shipment at the planned time and location. 

5.3 Container [73.67(g)(1)(iii)] 

Intent 

The intent of this requirement is to provide a mechanism or system that will help the receiver 

detect any tampering with the material’s container that may have occurred during shipment. Regulatory 

Guide 5.15, “Security Seals for the Protection and Control of Special Nuclear Material,” provides 

guidance in this area. If the material is shipped in an exclusive-use carrier, it is acceptable to tamper-seal 

the carrier itself rather than each individual SNM container. 

Content 

Describe the types of seals that will be used to secure the material’s container during transport. 
Rev. 1 of RG-5.59, Page 48 

5.4 Inspection [73.67(g)(1)(iv)] 

Intent 

The intent of this paragraph is to require the shipper to check the integrity of the material 

container’s seals just prior to shipment so as to be assured that they have not been compromised. Then, 

upon receipt of the shipment, if the receiver discovers the container’s integrity has been compromised and 

the material is missing, the scope of the recovery operation can focus on the transportation route. 

Content

Describe the procedures to be used to ensure that the integrity of the containers or seals is 

checked just prior to shipment. 

5.5 Responsibility for In-Transit Physical Protection [73.67(g)(1)(v)] 

Intent 

The intent of this paragraph is to make clear that the licensee shipping the material is responsible 

for arranging for the physical protection of the material in transit if the receiver is not a licensee. If both 

the shipper and receiver are licensees, the shipper may allow the receiver to accept this responsibility 

wholly or in part provided there is appropriate documentation specifying their respective responsibilities. 

Where no such documentation exists, both the shipper and receiver are held jointly responsible. (See 

Section 6.3 of Part II of this guide.) 

Content 

In its security plan, the shipper should either acknowledge responsibility for the in-transit 

physical protection of SNM of low strategic significance or ensure that a written agreement from the 

receiver has been received in which the receiver accepts either full responsibility or shared responsibility 

for the in-transit physical protection of this material in accordance with paragraph 73.67(g)(3) of 10 CFR 

Part 73. 

6. Receiver Requirements—Transportation 

This chapter, provides guidance on meeting the requirements of paragraph 73.67(g)(2), which are 

as follows: 

(g)(2) Each licensee who receives quantities and types of special nuclear material of low 

strategic significance shall: 

(i) Check the integrity of the containers and seals upon receipt of the shipment, 

(ii) Notify the shipper of receipt of the material as required in § 70.54 of Part 70 of 

this chapter, and 

(iii) Arrange for the in-transit physical protection of the material in accordance with 

the requirements of paragraph 73.67(g)(3) of this part, unless the shipper is a 

licensee and has agreed in writing to arrange for the in-transit physical 

protection. 
Rev. 1 of RG-5.59, Page 49 

6.1 Inspection [73.67(g)(2)(i)] 

Intent 

This requirement is intended to determine whether the material’s container has been 

compromised en route and whether any material has been removed so that immediate recovery procedures 

can be initiated if required. 

Content 

Describe the procedures to be used to ensure that the integrity of the containers and seals will be 

checked upon receipt of the material shipment. 

6.2 Notification [73.67(g)(2)(ii)] 

Intent 

This requirement is intended to ensure that knowledge of the current location of all SNM is 

available and to formally inform the shipper that the material has been received. 

Content 

Ensure that a completed copy of Form NRC-741, “Nuclear Material Transaction Report,” will be 

sent to the shipper within 10 days after a material shipment has been received as required in § 70.54 of 10 

CFR Part 70. 

6.3 Responsibility for In-Transit Physical Protection [73.67(g)(2)(iii)]

Intent 

The intent of this paragraph is to make clear that the licensee receiving the material is responsible 

for arranging for the physical protection of the material in transit if the shipper is not a licensee. If both 

the shipper and receiver are licensees, the receiver may allow the shipper to accept this responsibility 

either wholly or in part provided there is appropriate documentation specifying their respective 

responsibilities. Where no such documentation exists, both the shipper and receiver are held jointly 

responsible. (See Section 5.5 of Part II of this guide.) 

Content 

In its security plan, the receiver should either acknowledge responsibility for the in-transit 

physical protection of SNM of low strategic significance or ensure that a written agreement from the 

shipper has been received in which the shipper accepts either full responsibility or shared responsibility 

for the in-transit physical protection of this material in accordance with paragraph 73.67(g)(3) of 

10 CFR Part 73. 

7. In-Transit Physical Protection Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(g)(3), which are 

as follows: 

(g)(3) Each licensee, either shipper or receiver, who arranges for the physical protection of 

special nuclear material of low strategic significance while in transit or who takes 
Rev. 1 of RG-5.59, Page 50 

delivery of such material free on board (f.o.b.) the point at which it is delivered to a 

carrier for transport shall: 

(i) Establish and maintain response procedures for dealing with threats of thefts or 

thefts of such material, 

(ii) Make arrangements to be notified immediately of the arrival of the shipment at 

its destination, or of any such shipment that is lost or unaccounted for after the 

estimated time of arrival at its destination, and 

(iii) Conduct immediately a trace investigation of any shipment that is lost or 

unaccounted for after the estimated arrival time and report to the Nuclear 

Regulatory Commission as specified in § 73.71 and to the shipper or receiver as 

appropriate. The licensee who made the physical protection arrangements shall 

also immediately notify the Director of the appropriate Nuclear Regulatory 

Commission Regional Office listed in Appendix A of the action being taken to 

trace the shipment. 

7.1 Response Procedures [73.67(g)(3)(i)] 

Intent 

The intent of this regulation is to help the licensee identify those transportation incidents that 

could affect the security of the SNM in transit for which notification might be expected and for which 

response procedures should be planned. 

Content 

Identify those events for which response procedures will be developed. Also describe the type of 

response to be accomplished for each event identified and the duties and responsibilities of the security 

organization and management involved in the response. Ensure that the NRC will be notified 

immediately in the event of theft or attempted theft of the material. 

7.2 Notification [73.67(g)(3)(ii)] 

Intent 

The intent of this requirement is to ensure that the licensee responsible for the physical protection 

of SNM in transit will have a firm basis for deciding whether or not to initiate response procedures in the 

event a shipment becomes overdue or is lost. 

Content 

Describe the arrangements and procedures that will be used for notifying the licensee who 

arranges for the physical protection of material in transit (1) of the arrival of the shipment at its 

destination or (2) of any such shipment that is lost or unaccounted for after the estimated time of arrival at 

its destination. 
Rev. 1 of RG-5.59, Page 51 

7.3 Lost Material Notification [73.67(g)(3)(iii)] 

The intent of this requirement is to ensure that, in the event a shipment becomes overdue and no 

reasonable explanation has been received from the carrier regarding its status, a trace investigation will be 

conducted to locate the missing SNM. At this time, the NRC should be notified that the material is 

missing and informed as to what steps are being taken to recover it. Although the licensee is responsible 

for notifying the NRC of any missing material and for initiating and assisting in the subsequent 

investigation, the law enforcement agencies bear the responsibility for physically recovering the material. 

Content 

Describe what procedures will be used to trace any shipment that is lost or has not arrived by the 

estimated arrival time. Ensure that all lost or missing material will be immediately reported to the 

appropriate NRC Regional Office along with what actions are being taken to trace the shipment, that the 

NRC will be notified as specified in § 73.71, and that the shipper or receiver, as appropriate, will also be 

notified. 

8. Export Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(g)(4), which 

reads as follows: 

(g)(4) Each licensee who exports special nuclear material of low strategic significance shall 

comply with the appropriate requirements specified in § 73.67(c), (g)(1) and (g)(3). 

Using Chapters 5, “Material Transportation Requirements,” and 7, “In-Transit Physical 

Protection Requirements,” of Part II of this Standard Format, describe the security procedures that will be 

used to protect the material up to the point where the receiver accepts physical protection responsibility 

for the shipment. 

9. Import Requirements 

This chapter provides guidance on meeting the requirements of paragraph 73.67(g)(5), which 

reads as follows: 

(g)(5) Each licensee who imports special nuclear material of low strategic significance shall: 

(i) Comply with the requirements specified in § 73.67(c), (g)(2) and (g)(3), and 

(ii) Notify the person who delivered the material to a carrier for transport of the 

arrival of such material. 

9.1 Security Requirements [73.67(g)(5)(i)] 

Using Chapters 6, “Receiver Requirements—Transportation,” and 7, “In-Transit Physical 

Protection Requirements,” of Part II of this Standard Format, describe the security procedures that will be 

used to protect the material from the first point where the shipment is picked up. 
Rev. 1 of RG-5.59, Page 52 

9.2 Notification [73.67(g)(5)(ii)] 

Intent 

The intent of this regulation is to ensure that the exporter is notified that the material has arrived 

safely. 

Content 

Describe the procedures to be used for notifying the exporter of the material that the shipment 

was received. 

VALUE/IMPACT STATEMENT 

A separate value/impact analysis has not been prepared for this regulatory guide. The guide was 

developed to provide a standard format and content for the physical security plans that licensees 

authorized to possess or transport special nuclear material of moderate strategic significance or 

10 kilograms or more of material of low strategic significance are required to submit by amendments to 

Part 73 of the Commission’s regulations published July 24, 1979 (44 FR 43280). A value/impact analysis 

prepared for the amendments was made available in the Commission’s Public Document Room at the 

time the amendments were published. This analysis is also appropriate to this regulatory guide.