NUREG/BR-0006, Rev. 7

 

Instructions for 

Completing Nuclear 

Material Transaction 

Reports 

(DOE/NRC Forms 741 and 740M) 

Effective Date: January 1, 2009 

Office of Nuclear Material Safety and Safeguards 
NUREG/BR-0006, Rev. 7 

Instructions for 

Completing Nuclear 

Material Transaction 

Reports 

(DOE/NRC Forms 741 and 740M) 

Effective Date: January 1, 2009 

Manuscript Completed: June 2008 

Date Published: June 2008 

Prepared by 

C. Graves 

B.G. Horn, NRC Project Manager 

Office of Nuclear Material Safety and Safeguards 
 iii NUREG/BR-0006, Rev. 7 

ABSTRACT

U.S. Nuclear Regulatory Commission (NRC) regulations require licensees who ship, receive, or 

adjust their physical inventory of source or special nuclear material (SNM) to document and 

report such activities. The reports are submitted using U.S. Department of Energy (DOE)/NRC 

Form 741. Licensees may need to provide additional information on some imports or exports of 

source or SNM. The additional information is reported using DOE/NRC Form 740M. This 

NUREG contains instructions for preparing these forms. 

Paperwork Reduction Act Statement 

The information collections contained in this NUREG are covered by DOE/NRC Forms 741 and 

740M, which the Office of Management and Budget (OMB) approved under approval 

numbers 3150-0003 and 3150-0057. 

Public Protection Notification 

If a means used to impose an information collection does not display a currently valid OMB 

control number, the NRC may not conduct or sponsor, and a person is not required to respond 

to, the information collection. 
NUREG/BR-0006, Rev. 7 iv 
 v NUREG/BR-0006, Rev. 7 

CONTENTS

Abstract.........................................................................................................................................iii 

Abbreviations ...............................................................................................................................vii 

1 Introduction .............................................................................................................................1 

1.1 Material Transaction Reports .........................................................................................1 

1.2 Regulatory Authority.......................................................................................................2 

1.3 Reporting/Distribution Requirements .............................................................................3 

1.4 Methods for Preparing and Submitting Data to the Nuclear Materials Management and 

Safeguards System........................................................................................................4 

1.5 Documentation and Distribution .....................................................................................4 

2 General Instructions................................................................................................................7 

2.1 Instructions for Completing DOE/NRC Form 741 Reports.............................................7 

2.1.1 Reporting Shipper's Data ......................................................................................7 

2.1.2 Reporting Receiver's Data...................................................................................18 

2.2 Preparation of DOE/NRC Form 741 in Computer-Readable Format ...........................20 

2.3 Distribution of DOE/NRC Form 741 .............................................................................20 

2.3.1 Shipper ................................................................................................................20

2.3.2 Receiver ..............................................................................................................20 

3 Instructions for Onsite Gains and Losses (M Action Code) ..................................................23 

3.1 Instructions for Completing DOE/NRC Form 741.........................................................23 

3.2 Preparation of DOE/NRC Form 741 in Computer-Readable Format ...........................25 

3.3 Distribution of DOE/NRC Form 741.......................................................................25

4 Instructions for Correcting a DOE/NRC Form 741 

(C, D, and M Action Codes or Z Process Code) ...................................................................26 

4.1 Originator .....................................................................................................................26 

4.2 Receiver .......................................................................................................................27 
NUREG/BR-0006, Rev. 7 vi 

CONTENTS (Continued) 

4.3 Use of the Z Process Code ..........................................................................................27 

4.4 Distribution of Corrections to DOE/NRC Form 741......................................................27 

5 Instructions for Completing DOE/NRC Form 740M ..............................................................29 

6 DOE Reporting Requirements for Proprietary Interests of the Government .........................31

7 References............................................................................................................................33

 Appendices

A Composition Codes ......................................................................................................AB1 

B Inventory Change Type Codes for Completing 

 Blocks 26c and 27c of DOE/NRC Form 741.................................................................BB1 

C Example Documentation of Shipper and Receiver Data 

 (Blocks 26 and 27) ........................................................................................................CB1 

D Glossary ........................................................................................................................DB1 

E DOE/NRC Form 740M, “Concise Note,” (Blank) and DOE/NRC Form 741, 

“Nuclear Material Transaction Report” (Blank)..............................................................EB1 

F Supplemental Instructions for Completing Blocks 17, 18, 19, 20, and 21 on 

 DOE/NRC Form 741 .....................................................................................................FB1 
 vii NUREG/BR-0006, Rev. 7 

ABBREVIATIONS

ANSI American National Standards Institute 

BI beginning inventory 

CFR Code of Federal Regulations

DOE U.S. Department of Energy 

EI ending inventory 

EURATOM European Atomic Energy Commission 

FA facility attachment 

g gram 

HEU highly enriched uranium 

IAEA International Atomic Energy Agency 

ICR inventory change report 

ICT inventory change type 

ID inventory difference 

kg kilogram 

KMP key measurement point 

LEU low-enriched uranium 

MBA material balance area 

MBR material balance report 

MT material type 

NMMSS Nuclear Materials Management and Safeguards System 

NRC U.S. Nuclear Regulatory Commission 

OMB Office of Management and Budget 

OMP other measurement point 

Pu plutonium 

RA rounding adjustment 

RIS reporting identification symbol 

SAMS Safeguards Management Software 

SNM special nuclear material 

SRD shipper-receiver difference 
NUREG/BR-0006, Rev. 7 viii 

ABBREVIATIONS (CONTINUED) 

TFA transitional facility attachment 

U uranium 

UF6 uranium hexafluoride 

UK United Kingdom 

WR former Soviet Union weapons material 
 1 NUREG/BR-0006, Rev. 7 

U.S. NUCLEAR REGULATORY COMMISSION INSTRUCTIONS FOR 

COMPLETING NUCLEAR MATERIAL TRANSACTION REPORTS

DOE/NRC Form 741, “Nuclear Material Transaction Report,” and 

DOE/NRC Form 740M, “Concise Note”

1 Introduction

The U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE) 

jointly use the Nuclear Materials Management and Safeguards System (NMMSS). This system 

is the U.S. national database used by DOE and the NRC for tracking certain nuclear material. 

Common reporting forms and formats are used to minimize the reporting burden on licensees1

required to provide nuclear material data to one or both agencies in accordance with current 

regulations or contractual obligations. In this manner, licensees can file one report to meet the 

reporting requirements of both the NRC and DOE. Compliance with specific reporting 

requirements is monitored by the agency that requires the specific data. NRC regulations 

require that licensees submit the reports in computer-readable form. A licensee may use any 

blank blocks on the paper DOE/NRC forms for other business purposes. 

DOE requires all NRC licensees to report to the NMMSS all receipts, transfers, and inventories 

of U.S. Government-owned, -loaned, or -leased material in their possession. Reports to the 

NMMSS for all U.S. Government-owned, -loaned, or -leased material must follow the 

U.S. Government’s reporting requirements as specified in DOE Orders Series 470 (DOE 

Order 470.4, “Safeguards and Security Program,” and DOE M 470.4-6, “Nuclear Material 

Control and Accountability”). 

1.1 Material Transaction Reports

DOE/NRC Form 741, “Nuclear Material Transaction Report,” is the means for submitting 

transaction data to the NMMSS. DOE/NRC Form 741 must be completed in accordance with 

the instructions in this NUREG and must be submitted in computer-readable format. NMMSS 

Report D-24, “Personal Computer Data Input for NRC Licensees,” gives instructions for creating 

the computer-readable submittal. 

Licensees use DOE/NRC Form 741 to report physical transfers of nuclear materials between 

facilities. The report is also used to convey information on transactions such as inventory 

corrections that otherwise increase or decrease obligation balances or nuclear material 

categories within a facility.

The NMMSS relies heavily on the quality of the data reported by the facilities involved in nuclear 

activities. The data submitted to the NMMSS are subject to evaluation according to the 

restrictions placed on nuclear activity by the policies of various governing agencies of the United 

 

1

 The term “licensee” here denotes an NRC or Agreement State licensee or an NRC certificate holder. 
NUREG/BR-0006, Rev. 7 2 

States. The NMMSS accepts the data after they are verified as acceptable within the 

restrictions of the system. 

NRC licensees must provide a DOE/NRC Form 741 to the NMMSS in a computer-readable 

format following the instructions in this NUREG and NMMSS Report D-24. Both the shipper and 

the receiver are required to submit DOE/NRC Form 741. The receiver should confirm that the 

quantity received is consistent with the shipper’s report. When statistically significant shipperreceiver differences (SRDs), as defined in Title 10, Section 74.31, “Nuclear Material Control and 

Accounting for Special Nuclear Material of Low Strategic Significance,” of the Code of Federal 

Regulations (10 CFR 74.31),10 CFR 74.43, “Internal Controls, Inventory, and Records,” or 

10 CFR 74.59, “Quality Assurance and Accounting Requirements,” are identified, they must be 

resolved and their root causes corrected. The regulatory intent is to require material control and 

accounting systems to promptly detect and resolve all significant SRDs. Comparisons of 

shippers’ and receivers’ reports are necessary both to confirm the acceptability of shippers’ and 

receivers’ values for establishing the book accounting amounts for received material and to 

detect unacceptable shippers= or receivers= values. Comparisons typically involve item 

verification, seal integrity, gross weights, nondestructive assay measurements (if appropriate), 

and destructive measurements (if appropriate).

1.2 Regulatory Authority

Title 10 of the Code of Federal Regulations sets forth reporting requirements for specified 

activities.

For reporting transactions for special nuclear material (SNM), NRC regulations 10 CFR 72.78, 

10 CFR 74.15, 10 CFR 75.34, 10 CFR 76.113, 10 CFR 76.115, 10 CFR 76.117, and 

10 CFR 150.16 require, in part, that each licensee who transfers or receives SNM of any origin 

must complete, in computer-readable format, a DOE/NRC Form 741. This should be done in 

accordance with instructions in this NUREG whenever the licensee or certificate holder transfers 

or receives a quantity of SNM of 1 gram or more contained uranium (U)235, U233, or plutonium. 

Reporting for plutonium (Pu)238 is to the nearest one-tenth of a gram of the Pu238 isotope. 

For reporting transactions for source material, NRC regulations 10 CFR 40.64, “Reports,” and 

10 CFR 150.16, “Submission to Commission of Nuclear Material Transfer Reports,” state, in 

part, that except as specified within those sections, each licensee must complete and distribute 

a DOE/NRC Form 741 when the licensee in any manner transfers, receives, or adjusts the 

inventory of source material of foreign obligations by 1 kilogram or more or imports or exports 

1 kilogram or more of uranium or thorium source material. In addition, a licensee who uses 

1 kilogram or more of any uranium or thorium source material in enrichment services, 

downblending uranium that has an initial enrichment of the U235 isotope of 10 percent or more, 

or in the fabrication of mixed-oxide fuels. The licensee must complete DOE/NRC Form 741 in 

computer-readable format in accordance with instructions in this NUREG and in NMMSS 

Report D-24. Optionally, if using XML format, licensees may report source material to three 

decimal places; however, both the shipper and receiver must report at the kilogram unit, unless 

they both agree to report at the three-decimal unit. If using three-decimal reporting, then the 

reporting unit is to the nearest thousandth of a kilogram. For example, both the shipper and 

receiver may report 1655 grams as 1.655 kilograms. However, for consistency, the licensee 

must continue to report to the same decimal place for that material type. When reporting source 
 3 NUREG/BR-0006, Rev. 7 

material to three decimal places, both the detail and obligation weight must be reported to the 

same decimal place. 

For reporting transactions for source material or SNM in accordance with an agreement with the 

International Atomic Energy Agency (IAEA), NRC regulation 10 CFR 75.31, “General 

Requirements,” requires licensees to complete and distribute DOE/NRC Form 741 for all source 

material or SNM inventory changes, including shipments, receipts, onsite gains and losses, and 

any other inventory adjustments. These reports must be in computer-readable format and must 

be based on the records kept in accordance with 10 CFR 75.22, 10 CFR 75.31, 10 CFR 75.32, 

10 CFR 75.33, 10 CFR 75.34, and 10 CFR 75.35. 

Licensees can comply with these reporting requirements by completing DOE/NRC Form 741 

and transmitting it in computer-readable format following the guidance in this NUREG and in 

NMMSS Report D-24. 

In addition, the submission of DOE/NRC Form 741 is normally required as a matter of contract 

or lease administration for all Government-owned nuclear material transferred (see DOE Orders 

Series 470 (DOE Order 470.4 and DOE M 470.4-6)). 

1.3 Reporting/Distribution Requirements

Reports are required whenever nuclear material in the types and amounts stated in the 

preceding section moves between locations or operations that have been assigned different 

reporting identification symbols (RISs) and whenever SNM and source material inventories 

change. The nuclear material change data (including burnup, production, measured discards, 

category changes, and decay) must be documented and reported to the NMMSS before or at 

the same time as the physical inventory taking, unless the NRC has authorized another 

arrangement. 

The shipper initiates a DOE/NRC Form 741. If the licensee is involved in a transfer of material 

with a party that is not required to prepare a DOE/NRC Form 741, the licensee must prepare 

and submit both the shipper’s and the receiver’s section of DOE/NRC Form 741. The most 

common situation is when a domestic facility is involved in export/import activities. The 

domestic facility must obtain the information necessary to complete DOE/NRC Form 741 for the 

foreign facility for all imports of SNM and source material. In the case of exports, the shipper 

initiates a DOE/NRC Form 741 report, and the NMMSS will generate a DOE/NRC Form 741 

report using shipper information. However, if a significant SRD is identified between the U.S. 

shipper and foreign receiver (as defined in 10 CFR 74.31, 10 CFR 74.43, or 10 CFR 74.59 for 

SNM, or if there is an indication of loss, theft, or diversion of quantities of source material 

delineated in 10 CFR 40.64(c)(1)), the shipper is required to document the foreign party’s values 

in a DOE/NRC Form 741 report to the NMMSS. Submittal for a foreign facility does not indicate 

a responsibility for the other facility or its shipment/receipt of materials. 

Reports of physical shipments between RISs must document the actual movement of material. 

In addition, any reportable information associated with the material must also be reported. In 

particular, the obligation of material by a foreign entity must follow the physical movement of 

material between RISs. The transfer of obligations between RISs with no physical movement of 

material is reported by using action codes X and Y. 
NUREG/BR-0006, Rev. 7 4 

1.4 Methods for Preparing and Submitting Data to the Nuclear Materials 

Management and Safeguards System

The Safeguards Management Software (SAMS) is a miniature version of the NMMSS. This 

software allows the user to import and export data, make edit checks, generate various reports, 

and create material balance, inventory data, and transaction data. It has the capability to export 

data into the required NMMSS predefined computer-readable format outlined in NMMSS 

Report D-24. The SAMS program may be obtained from the NMMSS operator free of charge. 

Licensees can submit data to the NMMSS via the following three methods: 

(1) Telephonic Transfers 

 A licensee may submit DOE/NRC Form 741 electronically by using a modem. To 

establish an electronic connection with the NMMSS, licensees must contact the NMMSS 

security officer to request the establishment of a connection with the direct link. If the 

facility is a valid facility for the type of link requested (classified or unclassified), then the 

security officer will provide the requester with the appropriate forms to complete. 

 Upon receipt of the completed forms, the security officer will create a user identification 

and password and establish an account for the facility. The user identification and 

password will then be forwarded to the user facility along with a password 

acknowledgment form. The licensee will sign the acknowledgment form and return it to 

the security officer, who will then activate the user identification and password. 

(2) Data Submittals on Computer Media 

NMMSS Report D-24 provides instructions on packaging, data format requirements, 

acceptable media types, and the mailing address for the submittal of data on computer 

media. 

(3) New and Modified Methods of Transferring Electronic Data 

The NRC may authorize new and modified methods of transferring electronic DOE/NRC 

Form 741 data to the NMMSS. Licensees may confirm authorization to use additional 

methods for the transfer of these data by contacting the NMMSS operator. 

1.5 Documentation and Distribution

The completed DOE/NRC Form 741, in computer-readable format, must be submitted to the 

NMMSS operator. Licensees can confirm the address and mechanism for providing data to the 

NMMSS by calling the NMMSS operator. Specific submission instructions depend on whether 

the DOE/NRC Form 741 is classified or unclassified information. Sections 2.3, 3.3, and 4.4 of 

this NUREG contain additional distribution information. 

Any DOE/NRC Form 741 that is classified must be documented and handled in accordance with 

all pertinent security requirements. All other submissions that are not classified are considered 

to be proprietary material control and accounting information and may be requested to be 

withheld as defined by 10 CFR 2.390, “Public Inspections, Exemptions, Requests for 
 5 NUREG/BR-0006, Rev. 7 

Withholding.” Each person who is to receive a copy of the report must be verified as a qualified 

recipient before distribution. Licensees should confirm the address before sending documents 

to the NMMSS or other recipients. They should also formally provide classification guidance to 

the NMMSS operator after a decision to classify, declassify, or make any change in previously 

submitted guidance. To submit Safeguards Information, licensees should use Form 740M, 

“Concise Note,” stating that the submission is Safeguards Information and should be handled in 

accordance with 10 CFR 73.21, “Requirements for the Protection of Safeguards Information.” 
NUREG/BR-0006, Rev. 7 6 
 7 NUREG/BR-0006, Rev. 7 

2 GENERAL INSTRUCTIONS

2.1 Instructions for Completing DOE/NRC Form 741 Reports

 

If the DOE/NRC Form 741 report is documenting an onsite gain or loss, the licensee should 

review the instructions for block 6 (ACTION CODE) and the special instructions for the M action 

code in Section 3 of this NUREG before completing the form. 

The numbered instructions below correspond to the numbered blocks on the paper copy of 

DOE/NRC Form 741. Each shipper of reportable quantities of SNM or source material (refer to 

blocks 26n and 26q) must send a DOE/NRC Form 741 report to the NMMSS operator and a 

copy to the receiver’s business address no later than the close of business the next working 

day. 

In the case of spent fuel shipments, in accordance with 10 CFR 73.37, “Requirements for 

Physical Protection of Irradiated Reactor Fuel in Transit,” the date of shipment is Safeguards 

Information until 10 days after the shipment or the last shipment in a series of shipments is 

received. Therefore, DOE/NRC Form 741 should be identified as Safeguards Information, and 

a Concise Note Form 740M must be submitted stating that the submission is Safeguards 

Information and should be handled in accordance with 10 CFR 73.21. Concise Note 

Form 740M should also contain other pertinent information such as whether this is a single 

shipment or part of a series and the shipment number and total within the series. 

For disposals, the burial site operator must prepare and transmit DOE/NRC Form 741 to the 

NMMSS to document receipt and disposal. NRC regulations stipulate that the DOE/NRC 

Form 741 reports be submitted in computer-readable format. NMMSS Report D-24 gives the 

electronic formats for DOE/NRC Form 741. 

2.1.1 Reporting Shipper=s Data

Licensees should complete DOE/NRC Form 741 in accordance with the following instructions: 

1. SHIPPER’S RIS2

—Enter the shipper’s RIS. 

2. RECEIVER’S RIS2

—Enter the receiver’s RIS. 

3. TRANSACTION NUMBER—Enter a number for the same shipper-receiver combination. 

Numbers in the series must be consecutive (i.e., no skipped numbers). 

4. CORRECTION NUMBER—This block is used to identify a transaction that is an 

adjustment to a previously issued DOE/NRC Form 741. Leave this block blank for an 

original submission of a DOE/NRC Form 741. Use consecutive numbers, starting with 1, 

for adjustments. Refer to NMMSS Report D-24 for field sizes. For corrections requiring 

 

2

 NMMSS Reports D-2, D-3, and D-15 document RISs. 
NUREG/BR-0006, Rev. 7 8 

changes only to NMMSS data (and not to the other party’s data), use letters (A, B, etc.) 

instead of numbers. See Section 4 of this NUREG. 

5. PROCESS CODE—Enter process code A, C, D, or Z. 

• A refers to the initial entry of data. 

• C refers to the replacement of data. With the concurrence of the other party to 

the transaction, up to an entire data set may be replaced at any time before the 

close of the NMMSS processing period in which the initial submittal was made. 

• D refers to the deletion of data. An entire data set may be deleted at any time 

before the close of the NMMSS processing period in which the initial submittal 

was made, with the concurrence of the other party to the transaction. 

• Z refers to the receiver’s acceptance of other party’s correction. This processing 

code can be used only with action code D. Receivers reporting in accordance 

with 10 CFR Part 75, “Safeguards on Nuclear Material—Implementation of 

U.S./IAEA Agreement,” may not use the Z code. 

6. ACTION CODE—This block is used to identify the type of transaction being reported on 

DOE/NRC Form 741 as specified in 6a and 6b below. 

6a. SHIPPER—Enter one of the following action codes: 

A The shipper is reporting a transaction that has taken place between the stated 

parties. 

C The shipper is adjusting the initial DOE/NRC Form 741 for the shipment or a 

previous adjustment to the same initial report, acknowledging an adjustment 

originated by the receiver, or accepting and agreeing with the receiver’s

adjustment to DOE/NRC Form 741. See Section 4 of this NUREG. 

M The shipper is reporting a one-party transaction or an adjustment to a one-party 

transaction (e.g., an onsite gain or loss of material as the result of burnup, 

production, measured discards, category changes, etc.). DOE/NRC Form 742, 

“Material Balance Report,” shows such inventory changes. See Section 3 of this 

NUREG. 

R The shipper is identifying a one-party transaction to delete an obligated amount 

of material from the facility=s inventory. This code is applicable only to former 

Soviet Union weapons (WR) material after the fresh low-enriched uranium (LEU) 

is irradiated in a reactor core. Use of this code implies a removal of WR material; 

therefore, the value should be entered as a positive number. 

X The shipper is reporting a transfer of obligation that involves no physical 

movement of material. No obligation transfers of WR material are permitted. No 

shipper (block 26) or receiver (block 27) detail data need be entered. 
 9 NUREG/BR-0006, Rev. 7 

6b. RECEIVER—Enter one of the following action codes: 

B The receiver is reporting that a shipment has been received and that the weights 

reported by the shipper on DOE/NRC Form 741 were accepted as final receipt 

values.

E The receiver is reporting that a shipment was received, that independent 

measurements were made, and that the values resulting from the independent 

measurements are being reported. 

D The receiver is adjusting the initial DOE/NRC Form 741 that documented the 

receipt of a shipment or a previous adjustment to the same initial report, or 

acknowledging an adjustment originated by the shipper, or accepting and 

agreeing with the shipper’s adjustment to DOE/NRC Form 741. See Section 4 of 

this NUREG. 

M The receiver is reporting a one-party transaction or an adjustment to a one-party 

transaction (i.e., an onsite gain or loss of material as the result of burnup, 

production, measured discards, etc.). DOE/NRC Form 742 shows such 

inventory changes. See Section 3 of this NUREG. 

N The receiver is reporting physical receipt of a shipment but will delay the quantity 

determinations for the shipment of material for more than 10 days but no more 

than 60 days for source and LEU, or no more than 45 days for highly enriched 

uranium (HEU). At the end of this time, the receiver will prepare a DOE/NRC 

Form 741 with a B or E action code to report the receiver’s quantity 

determinations. Use of this code (N) requires no entry of detailed data (block 27) 

by the receiver. 

Y The receiver is reporting an acceptance of transfer of obligation that involves no 

physical movement of material. No shipper (block 26) or receiver (block 27) 

detailed data need be entered. 

7. DOCUMENTATION—This block is for paper-copy submissions only. Enter the number 

of pages if the submission is classified. 

8. SHIPPER—Leave blank. 

9. RECEIVER—Leave blank. 

10. NUMBER OF DATA LINES—After completing block 26 (SHIPPER’S DATA), or block 27 

(RECEIVER’S DATA), enter the total number of detail lines in block 26 or 27. The 

shipper and receiver must report the same number of entries, and the material types 

must agree line for line. 

11. NATURE OF TRANSACTION— Leave blank. 

12. SHIPPED FOR ACCOUNT OF—Leave blank. 
NUREG/BR-0006, Rev. 7 10 

13. SHIPPED TO ACCOUNT OF—Leave blank. 

14. TRANSFER AUTHORITY—Leave blank. 

15. EXPORT OR IMPORT TRANSFERS—For all export or import transfers, enter the NRC 

export or import license number under which SNM or source material is being 

transferred. Where transfers are authorized by an NRC general license, enter GEN-LIC. 

In some cases, the transfer may be exempt from licensing, such as exports of IAEA 

safeguards samples; then enter LIC-EXEMPT. If several batches authorized by 

separate licenses are combined into one shipment, a separate DOE/NRC Form 741 

must be completed for the portion associated with each import/export license. 

16. MATERIAL TYPE AND DESCRIPTION—Leave blank. 

17. LINE NUMBER—Enter a sequential line number beginning with the number 1. Refer to 

the NMMSS Report D-24 for field sizes. 

18. COUNTRY OF OBLIGATION—Enter the two-character country or entity designation 

from Table 1 in Appendix F for the line numbers entered in block 17. See Appendix F to 

this NUREG for further instructions. 

19. MATERIAL TYPE—Enter the material type to which the obligation is attached. Refer to 

Table 2 in Appendix F. The only material types to be reported are 10, 20, 50, 70, 81, 

and 88. 

20. OBLIGATED ELEMENT WEIGHT—Enter the weight of the obligated amount of the 

element. Refer to NMMSS Report D-24 for field sizes. See Appendix F for further 

instructions. Positive or negative values should be entered to appropriately account for 

material addition or removal, respectively. Reports with an action code of A, B, E, R, X, 

or Y must be reported with a positive weight. All others can be reported with a positive 

or negative weight. The sum of obligated material for a material type cannot exceed the 

sum of the weight value listed in the detail lines. 

21. OBLIGATED ISOTOPE WEIGHT—FOR ENRICHED URANIUM ONLY—Enter the 

weight of the obligated amount of the isotope. Refer to NMMSS Report D-24 for field 

sizes. For in-place activity, positive or negative values should be entered to 

appropriately account for material addition or removal, respectively. Reports with an 

action code of A, B, E, R, X, or Y must be reported with a positive weight. All others can 

be reported with a positive or negative weight. The sum of obligated material for a 

material type cannot exceed the sum of the weight value listed in the detail lines. 

22. ACTION DATE—Follow the instructions below for blocks 22a through 22e. 

22a. SHIPMENT (entry required by shipper)—Enter the date the nuclear material is shipped. 

22b. SHIPPER’S CORRECTION (entry required by shipper)—If the document is an 

acknowledgment of or a correction to a previously issued transaction report, enter the 

date the correction is recorded or the acknowledgment made, as appropriate. However, 

dates on acknowledgments must not precede the action date listed on the receiver’s 

correction. Additionally, be aware that if a date preceding the current unreconciled 
 11 NUREG/BR-0006, Rev. 7 

period is used, the effect of the correction will be reflected in the current period, not the 

prior period(s) covered by postdated documents. 

22c. RECEIPT (entry required by receiver)—Enter the date the nuclear material is received. 

22d. RECEIVER’S MEASUREMENT (entry required by receiver)—This entry is required only 

if the receiver’s action code is E. Enter the date the nuclear material is measured by the 

receiver. 

22e. RECEIVER’S CORRECTION (entry required by receiver)—If the document is an 

acknowledgment or a correction to a previously issued transaction report, enter the date 

the correction is recorded or the acknowledgment made, as appropriate. However, 

dates on acknowledgments must not precede the action date listed on the receiver=s 

correction. Additionally, be aware that if a date preceding the current unreconciled period 

is used, the effect of the correction will be reflected in the current period, not the prior 

period(s) covered by postdated documents. 

Note that in the case of all imports (and for some exports, see Section 1.3), licensees 

must complete a separate DOE/NRC Form 741 to document the foreign party action, 

including action dates in blocks 22a and 22c, as applicable. 

23a. MISCELLANEOUS—Leave blank. 

23b. CONCISE NOTE ATTACHED— Leave blank. 

23c. UK REPORTABLE—Facilities reporting material transfers involving facilities in the 

United Kingdom must indicate in this block whether the shipment is reportable or 

nonreportable to IAEA. Check YES for reportable or NO for nonreportable. 

Note that typically all licensee shipments to/from the United Kingdom are reportable. 

24. TOTAL GROSS WEIGHT—Enter the total gross weight of the shipment rounded to the 

nearest kilogram. An approximate or estimated gross weight rounded to the nearest 

kilogram is acceptable. Make no entry for M action code transactions, receipts, 

obligation transfers, and correction documents. 

25. TOTAL VOLUME (WASTE TRANSFERS ONLY)—For transfers of nuclear material to 

nuclear waste sites (i.e., receiver RIS begins with the letter V), enter the volume of the 

material to be buried, stated in cubic feet rounded to the nearest cubic foot. An entry in 

block 25 is not required for transfers to nuclear laundry services. 

26. SHIPPER’S DATA—Enter the shipper’s data in block 26. Enter the receiver’s data in 

block 27. Receivers should review the additional instructions for block 27 before 

completing the form. 

Shipper and receiver measurement data are entered on DOE/NRC Form 741 for each 

batch of material. For licensees reporting pursuant to the requirements of 

10 CFR Part 75, or if the transfer is an import or an export, a batch is a portion of nuclear 

material that is handled as a unit for accounting purposes at a key measurement point 

(KMP) and whose composition and quantity are defined by a single set of specifications 
NUREG/BR-0006, Rev. 7 12 

or measurements. The batch may be in bulk form or contained in a number of separate 

items. If the shipment is an export or is being reported pursuant to 10 CFR Part 75, fuel 

assemblies or loose rods or fuel pins must be listed separately with the identifying label 

serving as a unique batch name. Fuel assemblies can be reported as “average” 

enrichment as long as the appropriate accounts (material types 10, 20, 81, etc.) are 

properly adjusted. Material being transferred may be listed on one line of DOE/NRC 

Form 741 if the material is all of the same material type, composition, ownership, and 

weight percent of isotope (except as noted in the next paragraph). Material differing in 

any of these data elements must be listed on separate lines. 

Two or more lines may be necessary to describe a single batch (e.g., spent fuel 

assemblies, mixed-oxide fuel). If a batch consists of several types of nuclear material, 

several consecutive lines should be used to describe the batch. The batch name should 

be repeated on all lines used to describe a single batch. In block 26e, the number of 

items is also repeated on all lines with the same batch name. 

The above general rules for grouping or batching material for reporting purposes are 

also applicable to licensees reporting imports or exports pursuant to 10 CFR Part 40, 

“Domestic Licensing of Source Material,” 10 CFR Part 74, “Material Control and 

Accounting of Special Nuclear Material,” or 10 CFR Part 75. Batch names are optional 

for other transactions reported pursuant to 10 CFR Part 40 or 10 CFR Part 74. 

26a. BACK REFERENCE NUMBER—Enter the appropriate back-reference number 

adjustments to previously completed DOE/NRC Form 741 documents. 

Licensees must enter the back-reference numbers for action codes C and D and for 

action code M when reporting adjustments. Licensees must report both the backreference change digit and the back-reference line number. 

The back-reference change digit represents the change digit of the document being 

corrected for a nullifying entry and the change digit of the document now being 

completed for a correcting entry. For example, if the DOE/NRC Form 741 being 

corrected is the original, or if the line being entered represents an addition only, enter 0 

(zero). 

The back-reference line number represents the line number of the line being corrected 

for a nullifying entry and the line number of the corresponding nullifying line for a 

correction entry. If the line being entered represents an addition only or represents a net 

change, enter zeros. 

26b. LINE NUMBER—In providing detailed measurement data, enter a line number beginning 

with 1 for the first line of detailed shipper’s data and increase the line number by one for 

each additional line of detailed shipper’s data entered on the form. When two or more 

lines of measurement data refer to a single batch, repeat the unique batch name for 

each line of the batch data. For example, repeat the batch name when different material 

types of multienrichment fuel rods are entered on separate lines or when uranium 

hexafluoride (UF6) product material and UF6 heel material in a cylinder are reported on 

separate lines. 
 13 NUREG/BR-0006, Rev. 7 

26c. TYPE OF INVENTORY CHANGE—All changes to inventory that meet the reporting 

criteria must be reported on DOE/NRC Form 741. 

Appendix B explains the inventory change type (ICT) codes and indicates whether they 

are to be entered in block 26c. Enrichment facilities may use the two-digit numerical 

value for indicating a change type or proceed as directed by the NRC. When shipping to 

a V RIS, the shipper must use ICT code 74. A measured discard can be documented as 

an onsite transfer, discard to a pond/lagoon, or transferred to a holding area. 

Discharges to lagoon and movement to holding areas are documented with a suffix 

attached to the RIS: 

• Use L when material is discarded into a pond or lagoon. 

• Use H when material is transferred to a holding area (refer to the term “holding 

account” in the glossary in Appendix D) at the facility pending possible shipment 

offsite for disposal 

Note that use of a holding or lagoon account requires establishment of account and prior 

approval by the NRC. 

The shipper should enter its RIS in block 1 (SHIPPER’S RIS) and the same RIS in the 

block 2 (RECEIVER’S RIS), but append an L or H to the receiver’s RIS as appropriate. 

For example, if a facility with RIS XYZ discards material to a lagoon, the transaction on 

DOE/NRC Form 741 would be from XYZ to XYZL. 

26d. IDENTIFICATION (ITEM/BATCH NAME)—Enter a name or number, or a combination of 

both, that identifies the batch of material being shipped. If the licensee is reporting 

pursuant to 10 CFR Part 75, or if the transfer is an import or export, the shipper or 

receiver enters a name that identifies a unique portion of nuclear material handled as a 

unit for accounting purposes. For fuel pins and rods, the batch name should be the 

identification numbers of the fuel pin or rod. 

In the case of an import, the receiver must use the same batch name as the shipper, 

provided that the shipper’s batch name conforms to the above specifications. If it does 

not, submit a concise note in accordance with the instructions (Section 5) explaining the 

difference. When two or more lines of measurement data refer to a single batch, repeat 

the unique batch name for each line of the batch data. For example, repeat the batch 

name when different material types of multienrichment fuel rods are entered on separate 

lines or when UF6 product material and UF6 heel material in a cylinder are reported on 

separate lines. 

26e. NUMBER OF ITEMS—Enter the number of similar items of which the line entry consists 

(e.g., cylinders, packs, drums, bird cages, bottles, tank vessels). When reporting fuel 

pins, rods, or plates, report the number of separate fuel pins, rods, or plates involved. 

When reporting fuel assemblies, report the number of complete assemblies represented 

on the line entry. In the case of transfer of bulk material, enter the number 1. Leave 

blank if an M action code is used. 

26f. PROJECT NUMBER—Leave blank. 
NUREG/BR-0006, Rev. 7 14 

26g. MATERIAL TYPE—Enter the appropriate SNM or source material type code from the list 

below. 

U.S. Code

(Domestic transfers)

IAEA Code

(Imports/Exports)

Description

10 D Depleted uranium 

20 EG Enriched uranium 

50 P Plutonium 

70 EK U233

81 N Normal uranium 

833 Pu Pu238

88 T Thorium 

89 To be obtained 

from IAEA 

Uranium in cascade 

26h. COMPOSITION/FACILITY CODE—Enter the appropriate code describing the physical 

form (unencapsulated, encapsulated, etc.) and the chemical form of the material. See 

Appendix A. 

If the installation has been notified by letter from the NRC, as provided in 10 CFR 75.11, 

“Installation Information,” that it has been identified under the U.S./IAEA Safeguards 

Agreement, enter the appropriate code from the list developed during the formulation 

and negotiation of the facility attachment (FA) or transitional facility attachment (TFA) 

provided pursuant to 10 CFR 75.8, “Facility Attachments.” 

Note: In accordance with 10 CFR 75.11, any change in facility operations or processes 

that would result in any changes in, additions to, or deletions from the list should be 

communicated to the NRC in writing, to the extent provided in the license conditions, at 

least 70 days in advance of the changes so that new composition codes can be 

assigned. 

26i. OWNER CODE—This code identifies the ownership of the material at the time it was in 

the shipper’s possession. Enter the appropriate code from the following. 

G U.S. Government-owned 

J Not U.S. Government-owned 

Refer to the glossary in Appendix D to this document for further description of 

U.S. Government-owned material. 

 

3 Report as Pu238 if the contained Pu238 is greater than 10 percent of total plutonium by weight; otherwise, 

report as plutonium. 
 15 NUREG/BR-0006, Rev. 7 

26j. KEY MEASUREMENT POINT (KMP)—This data element applies only to licensees 

reporting pursuant to the requirements of 10 CFR Part 75. All other licensees must 

leave this block blank. This block is for reporting on a facility where nuclear material is in 

a form that may be measured to determine material flow or inventory. Codes for KMPs 

are identified in the FAs or TFAs developed for those facilities described in the 

instructions for block 26h. 

26k. MEASUREMENT IDENTIFICATION (see 26j)—This block applies only to licensees 

reporting pursuant to the requirements of 10 CFR Part 75 and to those facilities identified 

in the instructions for 26h. All other licensees must leave this block blank. This block 

indicates where and when the material was measured. It consists of three parts. 

26k1. BASIS—Enter the pertinent code from the following: 

N if the batch data are based on measurements made in an IAEA material balance 

area (MBA) other than the reporting MBA 

L if the batch data are based on measurements made in another IAEA MBA and 

have been previously reported by the reporting MBA in a DOE/NRC Form 741 or 

a DOE/NRC Form 742C, “Physical Inventory Listing” 

M if the batch data are based on measurements made in the reporting IAEA MBA 

and the data were not previously reported 

T if the batch data are based on measurements in the reporting IAEA MBA and 

have been previously reported for that MBA on a DOE/NRC Form 741 or a 

DOE/NRC Form 742C 

26k2. OTHER MEASUREMENT POINT (OMP)—For batch data designated code M in 

block 26k1, enter the code of the KMP where measurements were made if it is different 

from the KMP indicated in block 26j. If it is the same, leave the block blank. 

26k3. MEASUREMENT METHOD—If two or more measurement methods employed at the 

same KMP have a different measurement uncertainty, enter the code for the 

measurement method used, as identified in the FA. 

26l. GROSS WEIGHT—Enter the gross weight of the line entry in kilograms of material 

shipped plus tare weight (packaging and shipping container). 

26m. NET WEIGHT—Enter the weight of the material shipped, excluding tare weight, in grams 

for SNM and kilograms for source material. 

26n. ELEMENT WEIGHT—Enter the weight of the contained SNM or source material 

rounded to the quantities reported below. 
NUREG/BR-0006, Rev. 7 16 

Material Reporting Units

Plutonium or uranium 

enriched in U235 or U233

nearest whole gram 

Pu238 nearest 1/10 gram 

Source material nearest kilogram4

If the quantity to be entered is equal to or greater than 0.5 of the reporting unit, the 

quantity should be rounded up to the next whole reporting unit. If the quantity to be 

entered is less than 0.5 of the reporting unit, the quantity should be rounded down to the 

next whole reporting unit. 

26o. ELEMENT LIMIT OF ERROR—Limits of error need be reported only by licensees who 

are authorized to possess at any time and location SNM in a quantity exceeding 

1 effective kilogram and authorized to use SNM for activities other than those involved in 

the operation of a nuclear reactor licensed pursuant to 10 CFR Part 50, “Domestic 

Licensing of Production and Utilization Facilities”; who are involved in a waste disposal 

operation; or who are authorized to possess sealed sources. 

Complete when the total shipment contains more than 50 grams of U235, U233, or 

plutonium, or any combination of these. Enter the limit of error for each element entry 

using the same weight units as in block 26n, except where the line entry represents (1) a 

sealed plutonium-beryllium source, (2) samples that have all been determined by other 

means to contain less than 10 grams U235, U233, or plutonium, and (3) reactor-irradiated 

fuels involved in research, development, and evaluation programs in facilities other than 

irradiated-fuel reprocessing plants. 

Limits of error are to be at the 95-percent confidence level, propagated by the 

uncertainties of the weight measurement, the chemical analysis, and the sampling 

method. Limits of error are not applicable to source material. Licensees making onsite 

transfers between two different RISs or within the same RIS are exempt from supplying 

limits of error data for the transfers. Transfers between a license-exempt operation and 

a licensed operation at the same location are not considered onsite transfers, and limits 

of error are required. 

26p. WEIGHT % ISOTOPE—Enter the weight percent of the isotope U235 if the uranium is 

enriched or depleted in U235. If plutonium, enter the weight percent of the isotope Pu240. 

If Pu238, enter the weight percent of the isotope Pu238. Report weight percent to at least 

two, but not more than four, decimal places, depending on the accuracy of the 

measurement method employed (for example, XX.XXXX%). For U233, enter the parts 

per million of U232. This block does not apply to natural uranium and thorium. Use 

separate lines to report material of different enrichments. The plutonium and U235

content of irradiated fuel must be determined and reported upon removal of the spent 

 

4

 Optionally, if the reporter is using XML format, source material may be reported to three decimal places. 

When using three-decimal reporting to report source material, then the reporting unit is to the nearest 

thousandth of a kilogram (i.e., 1655 grams will be reported as 1.655 kilograms). 
 17 NUREG/BR-0006, Rev. 7 

fuel from the reactor core. Reactor operators may report the total nonfissile isotope 

instead of Pu240 in this block for spent fuel if the computer codes the operator uses have 

this limitation. 

26q. ISOTOPE WEIGHT—Enter the isotope weight. If enriched uranium or U233, enter weight 

to the nearest gram of U235 or U233 as appropriate. If plutonium, enter the sum of Pu239

and Pu241 to the nearest gram. If Pu238, enter the weight of the isotope Pu238 to the 

nearest one-tenth of a gram. For depleted uranium, enter the isotope weight to the 

nearest kilogram. Make no entry for other source material. 

If the quantity to be entered is equal to or greater than 0.5 of the reporting unit, the 

quantity should be rounded up to the next whole reporting unit. If the quantity to be 

entered is less than 0.5 of the reporting unit, the quantity should be rounded down to the 

next whole reporting unit. 

26r. ISOTOPE LIMIT OF ERROR—Limits of error need be reported only by licensees who 

are authorized to possess at any one time and location SNM in a quantity exceeding 

1 effective kilogram and authorized to use such SNM for activities other than those 

involved in the operation of a nuclear reactor licensed pursuant to 10 CFR Part 50, who 

are involved in a waste disposal operation, or who are authorized to possess sealed 

sources. 

Complete when the total shipment contains more than 50 grams of U235, U233, or 

plutonium, or any combination of these. Enter the limit of error for each isotope entry 

using the same weight units as in block 26n, except where the line entry represents (1) a 

sealed plutonium-beryllium source, (2) samples that have all been determined by other 

means to contain less than 10 grams U235, U233, or plutonium, and (3) reactor-irradiated 

fuels involved in research, development, and evaluation programs in facilities other than 

irradiated-fuel reprocessing plants. 

Limits of error are to be at the 95-percent confidence level, propagated by the 

uncertainties of the weight measurement, the chemical analysis, and the sampling 

method. Limits of error are not applicable to source material. Licensees making onsite 

transfers between two different RISs or within the same RIS are exempt from supplying 

limits of error data for the transfers. Transfers between a license-exempt operation and 

a licensed operation at the same location are not considered onsite transfers, and limits 

of error are required. 

26s. SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED—If submitted on paper, 

the report must be signed by an authorized representative of the licensee. Otherwise, 

enter the date submitted. Each licensee must establish internal procedures to ensure 

that the information provided in the report is accurate and that the report has been 

prepared and issued only by authorized licensee personnel. 

Proprietary information must be included when necessary to provide an adequate 

response. An application to withhold such information from public disclosure may be 

made and will be dispositioned in accordance with the provisions of 10 CFR 2.390. If 

any of this information is of particular sensitivity, a request may be made that such 

information not be transmitted to IAEA. Such a request must refer to and conform with 

10 CFR 75.12, “Communication of Information to IAEA.” 
NUREG/BR-0006, Rev. 7 18 

2.1.2 Reporting Receiver’s Data 

Each receiver of reportable quantities of SNM or source material must acknowledge receipt of 

shipments in accordance with the following instructions: 

$ If the receiver plans to accept the shipper’s measurement data without making 

independent measurements (B action code), the receiver must, within 10 days of receipt 

of the material, submit a DOE/NRC Form 741. There are two options for filling out the 

form: 

(1) Complete blocks 1 through 25 and enter a zero (0) in block 10. 

(2) Complete blocks 1 through 25, enter the shipper’s values in block 26, and repeat 

the shipper=s values in block 27. 

Facilities reporting pursuant to 10 CFR Part 75 must use the second option. They 

should dispatch the form in accordance with the instructions in Section 2.3.2. 

$ If the receiver makes independent measurements (E action code), the receiver must do 

the following within 10 days of receipt of the material: 

(1) Complete blocks 1 through 25, enter the shipper’s values in block 26, and 

complete blocks 27a through 27s of DOE/NRC Form 741. 

(2) Dispatch the form in accordance with the instructions in Section 2.3.2. 

$ If the receiver intends to make independent measurements within 60 days for source 

material or LEU, or 45 days for HEU (N action code), unless the NRC authorizes an 

exemption, the receiver shall do the following, within 10 days of receipt of the material: 

(1) Complete blocks 1 through 23 

(2) Dispatch the form in accordance with the instructions in Section 2.3.2. 

(3) After independent measurements are made, follow the instructions for reporting a 

B or E action code. If measurements are delayed, complete them and report 

them on DOE/NRC Form 741 within 60 days for source material and LEU and 

within 45 days for HEU after the receipt of each shipment, except in the case of 

receipts of scrap and irradiated material. 

In the case of a scrap processor receiving several shipments of scrap that are 

accumulated and processed together, the recovered quantity of material must be 

prorated to the specific transmittal documents and line entries to maintain the one-to-one 

correspondence between shipper’s and receiver’s data. 

27. RECEIVER’S DATA—Fill in the receiver’s data blocks as follows. 

 

Enter shipper and receiver measurement data on DOE/NRC Form 741 for each batch of 

material. For licensees reporting pursuant to 10 CFR Part 75 requirements or if the 
 19 NUREG/BR-0006, Rev. 7 

transfer is an import or an export, a batch is a portion of nuclear material that is handled 

as a unit for accounting purposes at a KMP and whose composition and quantity are 

defined by a single set of specifications or measurements. The batch may be in bulk 

form or contained in a number of separate items. If the shipment is an export or is being 

reported pursuant to 10 CFR Part 75, list fuel assemblies or loose rods or fuel pins 

separately with the identifying label serving as a unique batch name. Report fuel 

assemblies as “average” enrichment as long as the appropriate accounts (material types 

10, 20, 81, etc.) are properly adjusted. Material being transferred may be listed on one 

line of DOE/NRC Form 741 if the material is all of the same material type, composition, 

ownership, and weight percent of isotope (except as noted in the next paragraph). List 

material differing in any of these data elements on separate lines. 

Two or more lines may be necessary to describe a single batch (e.g., spent fuel 

assemblies, mixed-oxide fuel). If a batch consists of several types of nuclear material, 

use several consecutive lines to describe the batch. Repeat the batch name on all lines 

used to describe a single batch. In block 27e, also repeat the number of items on all 

lines with the same batch name. 

The above general rules for grouping or batching material for reporting purposes also 

apply to licensees reporting imports or exports pursuant to 10 CFR Part 40 or 

10 CFR Part 74. Batch names are optional for other transactions reported pursuant to 

10 CFR Part 40 or 10 CFR Part 74. 

27a. BACK REFERENCE NUMBER—Must match the shipper’s value. See 26a. 

27b. LINE NUMBER—Must match the shipper’s value. See 26b. 

27c. TYPE OF INVENTORY CHANGE—Must match the shipper’s value. See 26c. 

27d. IDENTIFICATION (ITEM/BATCH NAME)—See 26d. 

27e. NO. OF ITEMS—See 26e. 

27f. PROJECT NUMBER—See 26f. 

27g. MATERIAL TYPE—Must match the shipper’s value. See 26g. 

27h. COMPOSITION/FACILITY CODE—See 26h. 

27i. OWNER CODE—Describes the material ownership at the time it comes into the 

receiver’s possession. See 26i. 

27j. KEY MEASUREMENT POINT—See 26j. 

27k. MEASUREMENT IDENTIFICATION—See 26k. 

27l. GROSS WEIGHT—See 26l. 

27m. NET WEIGHT—See 26m. 
NUREG/BR-0006, Rev. 7 20 

27n. ELEMENT WEIGHT—See 26n. 

27o. ELEMENT LIMIT OF ERROR—See 26o. 

27p. WEIGHT % ISOTOPE—See 26p. 

27q. ISOTOPE WEIGHT—See 26q. 

27r. ISOTOPE LIMIT OF ERROR—See 26r. 

27s. SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED—See 26s. 

2.2 Preparation of DOE/NRC Form 741 in Computer-Readable Format

NMMSS Report D-24 provides instructions for preparing DOE/NRC Form 741 in computerreadable format as required for submittals. 

2.3 Distribution of DOE/NRC Form 741

2.3.1 Shipper

Each shipper of reportable quantities of SNM or source material must dispatch a DOE/NRC 

Form 741, as described below, no later than the close of business the next working day after the 

shipment. In the case of spent fuel shipments, in accordance with 10 CFR 73.37, the date of 

shipment is Safeguards Information until 10 days after the shipment or the last shipment in a 

series of shipments is received. Therefore, the DOE/NRC Form 741 should be identified as 

Safeguards Information and handled according to 10 CFR 73.21. 

When submitting Safeguards Information, a Concise Note Form 740M must be submitted 

stating that the submission is Safeguards Information and should be handled in accordance with 

10 CFR 73.21. 

Burials are reported when shipped. The burial site operator must prepare a DOE/NRC 

Form 741 and transmit it to the NMMSS to document receipt and disposal. 

The completed DOE/NRC Form 741 is distributed as follows: 

$ Provide a copy, in a mutually agreeable format, to the other party in the transaction. 

$ Submit one copy in computer-readable format to the NMMSS. See Section 1.5 for 

documentation and distribution of classified and unclassified reports. 

$ Retain one copy for the file. 

2.3.2 Receiver

The receiver should distribute the completed DOE/NRC Form 741 as follows: 

$ Submit one copy in computer-readable format to the NMMSS. See Section 1.5 for 

documentation and distribution of classified and unclassified reports. 
 21 NUREG/BR-0006, Rev. 7 

$ Return one copy, in a mutually agreeable format, to the shipper. 

$ Retain one copy for the file. 
NUREG/BR-0006, Rev. 7 22 
 23 NUREG/BR-0006, Rev. 7 

3 INSTRUCTIONS FOR ONSITE GAINS AND LOSSES 

(M ACTION CODE)

3.1 Instructions for Completing DOE/NRC Form 741

When using action code M, the licensee should complete DOE/NRC Form 741 in accordance 

with the following instructions: 

1. SHIPPER’S RIS—Enter the RIS. 

2. RECEIVER’S RIS—Same as in block 1. 

3. TRANSACTION NUMBER—See the instructions for block 3 in Section 2.1.1 or contact 

the NMMSS operator for other options. 

4. CORRECTION NUMBER—See the instructions for block 4 in Section 2.1.1. 

5. PROCESSING CODE—See the instructions for block 5 in Section 2.1.1. 

6. ACTION CODE—Enter M in 6a or 6b or both. 

7. DOCUMENTATION—Enter the number of pages if the submission is classified. This 

block is for paper-copy submissions only. 

8. NAME AND ADDRESS OF SHIPPER—Leave blank. 

9. NAME AND ADDRESS OF RECEIVER—Leave blank. 

10. NUMBER OF DATA LINES—Enter the total number of detail line entries on the form. 

11. NATURE OF TRANSACTION—Leave blank. 

12. SHIPPED FOR ACCOUNT OF—Leave blank. 

13. SHIPPED TO ACCOUNT OF—Leave blank. 

14. TRANSFER AUTHORITY—Leave blank. 

15. EXPORT OR IMPORT TRANSFERS—Leave blank. 

16. MATERIAL TYPE AND DESCRIPTION—Leave blank. 

17. LINE NUMBER—See the instructions in Section 2.1.1 for block 17. 

18. COUNTRY OF OBLIGATION—See the instructions in Section 2.1.1 for block 18. 

19. MATERIAL TYPE—See the instructions in Section 2.1.1 for block 19. 
NUREG/BR-0006, Rev. 7 24 

20. OBLIGATED ELEMENT WEIGHT—See the instructions in Section 2.1.1 for block 20. 

21. OBLIGATED ISOTOPE WEIGHT—FOR ENRICHED URANIUM ONLY—See the 

instructions in Section 2.1.1 for block 21. 

22. ACTION DATE—Enter the date of the activity in at least one of blocks 22a through 22e. 

If more than one block is completed, all dates must be the same. 

23. MISCELLANEOUS—Leave blank. 

24. TOTAL GROSS WEIGHT—Leave blank. 

25. TOTAL VOLUME—Leave blank. 

26. SHIPPER’S DATA

 

26a. BACK REFERENCE NUMBER—See the instructions in Section 2.1.1 for this block. 

26b. LINE NO.—See the instructions in Section 2.1.1 for this block. 

26c. TYPE OF INVENTORY CHANGE—See Section 2.1.1. 

26d. IDENTIFICATION (ITEM/BATCH NAME)—See Section 2.1.1. 

26e. NO. OF ITEMS—See Section 2.1.1. 

26f. PROJECT NUMBER—Leave blank. 

26g. MATERIAL TYPE—See Section 2.1.1. 

26h. COMPOSITION/FACILITY CODE—See Section 2.1.1. 

26i. OWNER CODE—See Section 2.1.1. 

26j. KEY MEASUREMENT POINT—See Section 2.1.1. 

26k. MEASUREMENT IDENTIFICATION—See Section 2.1.1. 

26l. GROSS WEIGHT—See Section 2.1.1. 

26m. NET WEIGHT—See Section 2.1.1. 
 25 NUREG/BR-0006, Rev. 7 

26n. ELEMENT WEIGHT—See Section 2.1.1. 

26o. ELEMENT LIMIT OF ERROR—See Section 2.1.1. 

26p. WEIGHT % ISOTOPE—Leave blank for ICT codes MF and EQ unless the material is 

enriched uranium. For ICT codes LN and TN, report the same weight percent of isotope 

as for the beginning of the inventory period. See the instructions in Section 2.1.1 for this 

block. 

26q. ISOTOPE WEIGHT—See Section 2.1.1. 

26r. ISOTOPE LIMIT OF ERROR—Leave blank. 

26s. SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED—See Section 2.1.1. 

27. RECEIVER’S DATA—See the instructions in Section 2.1.2 for block 27. 

3.2 Preparation of DOE/NRC Form 741 in Computer-Readable Format

NMMSS Report D-24 provides instructions for preparing DOE/NRC Form 741 in computerreadable format as required for submittals.

3.3 Distribution of DOE/NRC Form 741 

Distribution of the completed DOE/NRC Form 741 should be as follows: 

$ Submit one copy in computer-readable format to the NMMSS. (See Section 1.5 for 

documentation and distribution of classified and unclassified reports.) 

$ Retain one copy for the file. 
NUREG/BR-0006, Rev. 7 26 

4 INSTRUCTIONS FOR CORRECTING A DOE/NRC FORM 741 

(C, D, AND M ACTION CODES OR Z PROCESS CODE)

Adjustments are independent actions. Either the shipper or the receiver may initiate an 

adjustment to a DOE/NRC Form 741 reporting the original shipment or receipt of material or an 

adjustment to any previous adjustment to the original. The other party is required to 

acknowledge that an adjustment was made but not required to make the same adjustment to its 

records. 

4.1 Originator

The originator of the “corrected copy” must do the following: 

$ Complete blocks 1 through 25, as appropriate, referring to the copy of DOE/NRC 

Form 741 being corrected. 

$ Insert in block 26a or 27a of the “did-read” (Was) line, as appropriate, a back-reference 

code. If the line of data has not been previously corrected, use a zero (0). If previously 

corrected, the first digit is the correction number (block 4) from the DOE/NRC Form 741 

being corrected. If the line of data has been corrected several times, use the most 

recent correction number. The next two digits are the line number (block 26b or 27b) on 

the DOE/NRC Form 741 being corrected. The “did-read” line can only reference a line 

on the original document or a “should-read” line. No two or more “did-read” lines can 

back-reference the same line. 

$ Complete the “did-read” line, blocks 26b through j and n through r or 27b through j and n 

through r, as appropriate, by duplicating the entire line being corrected from the 

DOE/NRC Form 741 being corrected and indicating the opposite sign (positive or 

negative) from the original one used in reporting the number of items (block e), element 

weight (block n), element limit of error (block o), isotope weight (block q), and isotope 

limit of error (block r). 

$ Insert in block 26a or 27a of the “should-read” (Should-Be) line, as appropriate, a backreference code that references the corresponding “did-read” line. The first digit is the 

correction number of the document being completed. The next two digits are the line 

number of the corresponding “did-read” line. The “should-read” line can only reference a 

“did-read” line. No two or more “should-read” lines can back-reference the same line. 

Repeat this procedure until all lines requiring adjustment have been backed out and the correct 

information has been entered. 

The “did-read” and “should-read” for each line being adjusted should be paired 

(i.e., consecutive). 

One or more changes can be made to each line. Only incorrect lines should be included in a 

correction report. 
 27 NUREG/BR-0006, Rev. 7 

If adding a line to the original document, the back-reference should be (000) (block 26a or 27a), 

and pairing is not done. 

If a line previously reported is split into two or more lines, one of the “should-be” lines should 

back-reference the “did-read” line, and all others should be considered new additions (000). 

If a line is to be voided, use only a “did-read line” (no pairing). Appendix C provides examples 

of an initial report and subsequent correction reports. 

4.2 Receiver

Within 10 days, the facility receiving the corrected DOE/NRC Form 741 must do one of the 

following: 

$ Submit a DOE/NRC Form 741 acknowledging the adjustment (which will close a 

transaction but will not affect the acknowledging party=s values). 

$ Submit a DOE/NRC Form 741 accepting the adjustment or reporting the facility’s own 

adjustment. This closes a transaction and applies the accepted or reported adjustment 

to the acknowledging party=s values. 

There is no requirement for both parties to make the same quantity adjustments. However, if 

both parties choose to adjust on the same corrected DOE/NRC Form 741, they must both report 

the same number of entries, and the material types must agree line for line. 

4.3 Use of the Z Process Code

If the receiving party agrees to all changes for an action code C document, the receiving party 

may use process code Z and action code D. A DOE/NRC Form 741 should be used to report 

data in blocks 1, 2, 3, 4, and 22. The Z code should be entered in block 5b and action code D 

entered in block 6b, and block 22 should be completed. A licensee reporting pursuant to 

10 CFR Part 75 may not use the Z process code. 

4.4 Distribution of Corrections to DOE/NRC Form 741

The originator should do the following: 

$ Submit one copy, in a mutually agreeable format, to the other party in the transaction. 

$ Submit one copy in computer-readable format to the NMMSS. (See Section 1.5 for 

documentation and distribution of classified and unclassified reports.) 

$ Retain one copy for the originating facility’s file. 

Upon receipt of a correction, a licensee should distribute a completed DOE/NRC Form 741 

reporting an acknowledgment, acceptance, or correction as follows: 
NUREG/BR-0006, Rev. 7 28 

$ Submit one copy to the NMMSS. (See Section 1.5 for documentation and distribution of 

classified and unclassified reports.) 

$ Return one copy to the originator. 

$ Retain one copy for the facility’s file. 
 29 NUREG/BR-0006, Rev. 7 

5 INSTRUCTIONS FOR COMPLETING 

DOE/NRC FORM 740M

These instructions apply to all licensees who have been notified by letter from the NRC, as 

provided in 10 CFR 75.11, that their installations have been identified under the U.S./IAEA 

Safeguards Agreement. FAs or TFAs for such installations may specify circumstances under 

which concise notes must be submitted to the IAEA as attachments to other reports. These 

facilities should use DOE/NRC Form 740M to explain to the foreign state where the IAEArequired data items appear. 

Licensees who are reporting what is determined to be Safeguards Information must submit a 

concise note, as discussed in Section 1.5. 

These instructions also apply to importers who for any reason cannot use the same batch name 

as the shipper. If the shipper fails to supply a batch name, the importer should supply a batch 

name and attach a concise note to that effect. 

In some cases, it may be desirable to provide additional explanatory information with reports. 

DOE/NRC Form 740M is used to submit this information. A DOE/NRC Form 740M may be 

attached to DOE/NRC Form 741, to DOE/NRC Form 742, to DOE/NRC Form 742C, or to a 

standalone concise note for facilities reporting under 10 CFR Part 75. 

The numbered blocks of DOE/NRC Form 740M should be completed as follows: 

 

1. NAME AND ADDRESS—Leave blank. 

2. ATTACHMENT TO—Place an X in the appropriate box to indicate that this explanatory 

information will be attached to a DOE/NRC Form 741 

When attaching the concise note to DOE/NRC Form 742 or 742C, enter the number 1 

for the first concise note attached to the particular DOE/NRC Form 742 or 742C. When 

issuing an additional concise note for a particular DOE/NRC Form 742 or 742C, enter 

the next sequential number (2–9) of the concise note. 

3. RIS—Enter the RIS to which the explanatory information in this report applies. 

4. REPORTING PERIOD—Complete this block only when the concise note is attached to a 

DOE/NRC Form 742 or a DOE/NRC Form 742C. Enter the beginning and ending dates 

of the reporting period as shown on Form 742. 

5. TRANSACTION DATA—Complete this block only when the concise note is attached to a 

DOE/NRC Form 741 or if a standalone concise note is submitted. Copy the requested 

data from DOE/NRC Form 741. All entries in this block must be identical to those on 

DOE/NRC Form 741. Fill in the blocks as follows. 

5A. SHIPPER=S RIS—Enter the RIS of the shipper. 

5B. RECEIVER=S RIS—Enter the RIS of the receiver. 
NUREG/BR-0006, Rev. 7 30 

5C. TRANSACTION NUMBER—Enter the unique transaction number. 

5D. CORRECTION NUMBER—If the DOE/NRC Form 741 is a correction to a previous 

report, enter the correction number. 

5E. PROCESSING CODE—Insert the same code used in DOE/NRC Form 741. 

5F. ACTION CODE—If a Form 740M is used with a DOE/NRC Form 741, enter the same 

action code as on the DOE/NRC Form 741, block 7; otherwise, enter action code M. 

6. REPORTING DATE—Complete this block if the concise note is attached to a DOE/NRC 

Form 741 or 742C. Copy the date shown on DOE/NRC Form 741 or 742C. 

7. This block contains the actual explanatory data and other data necessary to link the 

explanatory data to the part or parts of the report to which the data apply. Complete this 

block as follows. 

7A. LINE NO.—Enter consecutive numbers beginning with 1 for each explanatory reference. 

7B. ENTRY REFERENCE—If the explanatory information entered on this line of the 

DOE/NRC Form 740M applies to the entire DOE/NRC Form 741, 742, or 742C, enter 

WHOLE REPORT. If the explanation applies to the data on a specific batch on a 

DOE/NRC Form 741 or 742C, copy the batch name exactly as it appears on the 

DOE/NRC Form 741 or 742C. If the explanation applies to a specific material balance 

category on a DOE/NRC Form 742, enter the two-digit number of the material balance 

category. Additionally, if the explanation applies to material balance categories 11, 30, 

42, 43, or 51, enter the RIS shown on the relevant line of DOE/NRC Form 742. If the 

explanation applies to categories 22 or 71, enter the two-character ICT as shown on the 

relevant line of DOE/NRC Form 742. If the DOE/NRC Form 740M action code is M, 

enter GENERAL. 

7C. TEXT OF CONCISE NOTE—Enter any 43 letters, numbers, or special characters per 

line. Up to 99 lines of text may be used for any one explanation. 

8. SIGNATURE—An authorized representative of the licensee must sign DOE/NRC 

Form 740M. See the instructions in Section 2.1.1 for block 26s. 

9. TITLE—Enter the title of the person signing the form. 

10. DATE—Enter the date the form is signed. 

DOE/NRC Form 740M should be put into computer-readable format following the additional 

guidance in NMMSS Report D-24. 

Copies of Form 740M must be attached to, and distributed with, the DOE/NRC Form 741, 742, 

or 742C to which the DOE/NRC Form 740M applies. 
 31 NUREG/BR-0006, Rev. 7 

6 DOE REPORTING REQUIREMENTS FOR PROPRIETARY 

INTERESTS OF THE GOVERNMENT

NRC licensees are responsible for routinely reporting to the NMMSS all DOE-owned, -loaned, 

or -leased material in their possession as prescribed in DOE Orders Series 470 (DOE 

Order 470.4 and DOE M 470.4-6). 
NUREG/BR-0006, Rev. 7 32 
 33 NUREG/BR-0006, Rev. 7 

7 REFERENCES

This report and its appendices reference the NMMSS documents listed below. To request 

these documents, telephone the NMMSS operator. 

NMMSS Report D-2, “The DOE Directory of Reporting Identification Symbols” 

NMMSS Report D-3, “The NRC Directory of Reporting Identification Symbols” 

NMMSS Report D-15, “International Nuclear Facilities Codes Manual” 

NMMSS Report D-24, “Personal Computer Data Input for NRC Licensees” 

NMMSS Report D-25, “Transaction Composition Code Reference List” 

American National Standards Institute Report D-50A-109, “ANSI Codes” 
 34 NUREG/BR-0006, Rev. 7 
 NUREG/BR-0006, Rev. 7

 

APPENDIX A

COMPOSITION CODES

 
NUREG/BR-0006, Rev. 7 
 A-1 NUREG/BR-0006, Rev. 7

 

COMPOSITION CODES

The codes listed below are for use in completing blocks 26h or 27h on DOE/NRC Form 741, 

“Nuclear Material Transaction Reports.” If an installation has been notified by letter from the 

U.S. Nuclear Regulatory Commission (NRC), as provided in Title 10, Section 75.11, “Installation 

Information,” of the Code of Federal Regulations (10 CFR 75.11), that it has been identified 

under the U.S./International Atomic Energy Agency Safeguards Agreement, the licensee should 

enter the appropriate code from the list developed during the formulation and negotiation of the 

facility attachment or transitional facility attachment (after the document has been provided 

under 10 CFR 75.8, “Facility Attachments”). 

In accordance with 10 CFR 75.11, any change in facility operations or processes that would 

result in any changes to, additions to, or deletions from the list should be communicated to the 

NRC in writing, to the extent provided in the facility’s license conditions, at least 70 days in 

advance of the changes so that new composition codes can be assigned. 

For additional composition codes, see Nuclear Materials Management and Safeguards System 

(NMMSS) Report D-25, “Transaction Composition Code Reference List,” and American National 

Standards Institute (ANSI) Report D-50A-109, “ANSI Codes.” 

UNENCAPSULATED (except scrap) 

Code

032 U3O8 (oxide product) 

048 UO3 (trioxide product) 

770 Carbides 

455 Other Oxides Product (for all oxides not otherwise identified) 

064 Tetrafluorides (tetrafluoride product) 

083 UF6 (hexafluoride product) 

095 Enriching Process 

102 Hexafluorides—in Enriching Process 

103 Hexafluoride Product 

107 Uranium in Cascades—Holdup 

120 UF6 Feed 

773 UF6 Heels 
NUREG/BR-0006, Rev. 7 A-2

363 In Reactor Product 

409 Nitrate Solutions Product 

786 Acetate Solutions Product 

701 Unalloyed Metal Product 

702 Alloyed Metal Product 

771 Samples and Standards 

637 Sintered Products 

UNENCAPSULATED SCRAP (for recovery)* + 

375 Irradiated Recyclable Fuel 

WASTE (for disposal) 

Waste material should be described by an appropriate scrap category.* 

ENCAPSULATED 

291 Fabricated Fuel Elements (pins, rods, plates) 

309 Fuel Assemblies (assembled items product) 

481 Sealed Sources (fabricated sources product) 

OTHER 

776 Other Products 

E04 Miscellaneous Noncombustibles (Uranium) 

Note: Uranium/thorium and plutonium/uranium mixed-oxide fuels should be reported either as 

fuel elements (code 291) or as fuel assemblies (code 309) as applicable. 

Report the different material types in the mixed-oxide fuels on separate lines. 

 

*

 ANSI codes for plutonium scrap may be used in lieu of these codes. 

+

 Where a number of dissimilar items of scrap are put into the same container, use the composition code for the 

predominant scrap category. 
 NUREG/BR-0006, Rev. 7 

APPENDIX B 

 INVENTORY CHANGE TYPE CODES FOR COMPLETING 

BLOCKS 26c AND 27c OF DOE/NRC FORM 741
NUREG/BR-0006, Rev. 7
B-1 NUREG/BR-0006, Rev. 7

INVENTORY CHANGE TYPE CODES FOR COMPLETING 

BLOCKS 26c AND 27C OF DOE/NRC FORM 741

All inventory change type codes on transaction reports consist of two alphabetic or numeric 

characters. The accounting entry type codes used on material balance reports (MBRs) consist of 

two digits. In the following pages, the number(s) in parentheses following the alphabetic code 

represent the MBR line to which the transaction entries correspond. The standard inventory 

changes and other entry types are listed below. In transaction reports, all transactions and 

operations are understood to be related to individual batches. In MBRs, corresponding the same 

codes denote consolidated entries (i.e., the sums of all individual operations with the same code 

over the material balance period). In addition, MBRs include entries related to inventory data and 

adjustments not reported on transaction reports. 

Gains or losses of material that occur based on the total inventory, or in which individual effects to 

inventories by country of obligation code cannot be determined, should be reported as a loss to all 

country obligation balances by applying a one to one ratio by percent of the country of obligation to 

the amount of inventory affected to the amount of inventory change. For example, if decay is 

reported for plutonium within a reactor and the plutonium balance represents several different 

country of obligation balances, the following calculations would determine the amount of decay to 

apply to each country of obligation code balance. 

Element Isotope

Amount of inventory for which decay applies 1,202,239 950,947 

Calculated decay for the period 998 998 

Balance by Country Obligation Code

OBLIGATION CODE ELEMENT ISOTOPE % Ratio to Total Inventory

33 200,000 158,196 200,000/1,202,239 = .166 x 100 = 17% 

34 509,321 402,863 509,321/1,202,239 = .424 x 100 = 42% 

32 492,918 389,888 492,918/1,202,239 = .410 x 100 = 41%

Total Pu Balance 1,202,239 950,947 100% 

Amount of decay to apply to each country of obligation code balance

33 998 x 17% = 169.66 rounded to the nearest gram = 170 

34 998 x 42% = 419.16 rounded to the nearest gram = 419 

32 998 x 41% = 409.18 rounded to the nearest gram = 409

998 

The following should also be used for the isotope balances: 
NUREG/BR-0006, Rev. 7 B-2

 

TRANS. MBR 

CODE LINE 

EXPLANATION REQUIREMENT FOR 

BLOCKS 26c AND 27c 

RF 

(11, 13, 30, 38, 39)

Nuclear material imported into the United 

States (receipt foreign). 

Make no entry 

RD 

(11, 13, 30, 38, 39)

Domestic receipt of nuclear material from 

another domestic reporting identification 

symbol (RIS) (receipt domestic). 

Make no entry 

RN 

(11, 13, 30, 38, 39)

Domestic receipt of nuclear material from 

activity not subject to 10 CFR Part 75. 

Make no entry 

NP 

(21)

Production of fissionable material in a reactor 

(Pu, U233). 

Entry required by 

licensee 

DU 

(76)

Reapplication of safeguards in nuclear 

material previously exempted therefrom 

pursuant to Article 38 of the US/IAEA 

Safeguards Agreement after being exempted 

based on use (licensees subject to 

10 CFR Part 75 only). 

Entry required only after 

notification by the NRC 

DQ 

(76)

Reapplication of safeguards in nuclear 

material previously exempted therefrom 

pursuant to Article 38 of the Agreement after 

being exempted based on quantity (licensees 

subject to 10 CFR Part 75 only). 

Entry required only after 

notification by the NRC 

SF 

(42, 43, 51, 58, 59)

Export of nuclear material out of the United 

States. 

Make no entry 

SD 

(42, 43, 51, 58, 59)

Domestic transfer of nuclear material from 

another domestic RIS. 

Make no entry 

SN 

(42, 43, 51, 58, 59)

Domestic transfer of nuclear material from a 

facility subject to 10 CFR Part 75 to a waste 

management facility. 

Entry required 

SN 

(42, 43, 51, 58, 59)

Domestic transfer of nuclear material from a 

facility subject to 10 CFR Part 75 to a facility 

other than a waste management facility. 

Make no entry 

LN* Consumption of nuclear material because of its Entry required by 

(73) transformation into other elements or licensee 

 isotope(s) as a result of nuclear reactions 

 (burnup).

*Note: When calculating weight percent isotope in the case of burnup or decay, report the 

same weight percent isotope for decay and burnup as the weight percent of the beginning 

inventory for the period. 
B-3 NUREG/BR-0006, Rev. 7

TRANS. MBR 

CODE LINE 

EXPLANATION REQUIREMENT FOR 

BLOCKS 26c AND 27c 

TN* Consumption of nuclear material because of Entry required by 

(72) transformation into other elements or licensee 

 isotope(s) as a result of nuclear reactions 

 (decay). 

*Note: When calculating weight percent isotope in the case of burnup or decay, report the 

same weight percent isotope for decay and burnup as the weight percent isotope of the original 

inventory for the perio . d

LD 

(74)

Normal operational loss/measured discard; 

(i.e., loss of a measured or estimated (on the 

basis of measurement) quantity of nuclear 

material from processing which has been 

disposed of in such a way that it is not 

suitable for further nuclear use). 

Entry required by 

licensee 

TW 

(74)

Transfer to the retained waste category of 

measured nuclear material which is deemed 

to be irrecoverable, to be stored at the 

material balance area (MBA) and to be 

deleted from the inventory of the MBA. 

Entry required by 

licensee 

FW 

(51)

Retransfer of material that has been stored at 

the MBA as retained waste to the nuclear 

material inventory. This applies whenever 

material in the retained waste category is 

removed from storage either for processing 

at the MBA or for retransfer from the MBA. 

Entry required by 

licensee 

EU 

(76)

Exemption of nuclear material from 

safeguards pursuant to Article 36 of the 

Agreement (licensees subject to 

10 CFR Part 75 only). 

Entry required only after 

notification by the NRC 

EQ 

(76)

Exemption of nuclear material from 

safeguards pursuant to Article 37 of the 

Agreement (licensees subject to 

10 CFR Part 75 only). 

Entry required only after 

notification by the NRC 

TU 

(76)

Termination of safeguards on nuclear 

material pursuant to Articles 13 and 35 of the 

Agreement (licensees subject to 

10 CFR Part 75 only). 

Entry required only after 

notification by the NRC 

LA 

(75) 

Irretrievable and inadvertent loss of a known 

quantity of nuclear material as the result of 

an operational accident. 

Entry required by 

licensee 
NUREG/BR-0006, Rev. 7 B-4

TRANS. MBR 

CODE LINE 

EXPLANATION REQUIREMENT FOR 

BLOCKS 26c AND 27c 

GA 

(75)

Nuclear material unexpectedly found to be 

present in the MBA, except when detected in 

the course of a physical inventory taking. 

Gains should be reported as a negative 

value. 

Entry required by 

licensee 

DI 

(N/A)

The difference between the batch quantity 

reported as received (always on shipper=s 

data) and the quantity of the same batch as 

measured by the operator of the receiving 

MBA (licensees subject to 10 CFR Part 75 

only). 

Make no entry 

RM 

(N/A)

The quantity by which the batch mentioned in 

the entry is diminished in cases of rebatching 

(licensees subject to 10 CFR Part 75 only). 

Licensee entry required, 

if applicable 

RP 

(N/A)

The quantity of material added from another 

batch to the batch mentioned in the entry 

(licensees subject to 10 CFR Part 75 only). 

Licensee entry required, 

if applicable 

EN 

ED 

NE 

ND 

DE 

DN 

EE 

(22, 71)

(22, 71) 

Category Change—The quantity of uranium 

that has changed category as a result of 

blending, enrichment, depletion, or burnup. 

The first letter denotes the original, the 

second letter the resulting category 

(E=enriched, N=natural (or normal), 

D=depleted uranium, EE=change of 

enrichment). The material type codes should 

be those for both the original and the 

resulting material. The weight data should be 

provided both for the originating and for the 

resulting category. 

These entries should be consolidated into the 

material balances for both categories. For 

any of these changes, line pairing is required; 

one line denotes the original material and the 

other denotes the resulting material. 

Enrichment facility may use the 22, 71 

combination to report changes in material 

type associated with enrichment activities for 

material types 10, 20, 81, and 89 or proceed 

as directed by the NRC. 

Entry required by 

licensee 

MF 

(77)

Inventory Difference—This should be 

calculated as the difference between the 

book inventory and the ending physical 

Entry required by 

licensee 
B-5 NUREG/BR-0006, Rev. 7

TRANS. MBR 

CODE LINE 

EXPLANATION REQUIREMENT FOR 

BLOCKS 26c AND 27c 

inventory. Reactors must not use this code. 

PB 

(N/A)

Beginning Physical Inventory—This should 

be equal to the ending physical inventory of 

the previous MBR relating to the same 

material. 

Entry required by 

licensee 

BA 

(83)

The algebraic sum of the beginning physical 

inventory and of the inventory changes over 

the period, adjusted to take account of the 

shipper-receiver differences. 

Entry required by 

licensee 

PE 

(N/A)

The sum of all measured and derived batch 

quantities of nuclear material on hand on the 

date of the physical inventory taking. 

These entries should be consolidated. 

Entry required by 

licensee 

RAXX 

(N/A)

Applicable to licensees subject to 

10 CFR Part 75 only. The quantity that must 

be added to the rounded sum to make it 

equal to the sum of the rounded terms. A 

rounding adjustment (RA) is made to an entry 

in the MBR of which the International Atomic 

Energy Agency (IAEA) has been informed 

differently through inventory change reports 

(ICRs) and physical inventory lists, in order to 

bring the MBR entry into agreement with the 

corresponding figures established on the 

basis of ICRs and physical inventory lists. In 

the case of the book inventory and the 

inventory difference (ID) or material 

unaccounted for (MF), the following formulas 

should be used respectively: 

RABA = PB + ICRMBR B DI B BA, and 

RAMF = BA B PE B MF 

where ICRMBR is the sum of the consolidated 

inventory changes as reported in the MBR, 

taken with the appropriate sign if they 

represent decreases. All other notations are 

as defined for this data element. 

No rounding adjustment is needed for the 

beginning physical inventory. 

The rounding adjustment should be coded 

Entry by licensee 

required only if 

applicable 
NUREG/BR-0006, Rev. 7 B-6

TRANS. MBR 

CODE LINE 

EXPLANATION REQUIREMENT FOR 

BLOCKS 26c AND 27c 

RAXX where XX stands for the code of the 

entry to which the rounding adjustment 

pertains (e.g., RALN means a rounding 

adjustment to the consolidated entry on the 

nuclear loss). 

34 

(30)

Receipts—Miscellaneous. Enter quantities of 

material received in two-party transactions 

where only receiver=s data or receipts of 

quantities of material falling below the 

reporting level are reported and now 

cumulatively total 1 gram or more for SNM or 

1 kilogram or more for source material. 

Examples include receipts of material (not 

reported elsewhere) from facilities that have 

not been assigned an RIS and receipts from 

licensees who are not required to document 

or report transactions. 

Licensee entry required 

37 Procurement by Others. Enter quantities of 

material purchased by the facility for its own 

account from in situ material that it had been 

holding or material that the facility is 

processing for another licensee. 

54 

(51)

Shipments—Miscellaneous. Enter quantities 

of material shipped in two-party transactions 

where only shipper’s data are reported or 

shipments of quantities of material falling 

below the reporting level are reported and 

now cumulatively total 1 gram or more of 

SNM or 1 kilogram or more for source 

material. Examples are shipments of 

material (not reported elsewhere) from 

facilities that have not been assigned a 

reporting identification symbol and shipments 

from licensees that are not required to 

document or report transactions. 

Licensee entry required 

65 Rounding Adjustment Entry required by 

licensee. Note: A 

negative value adds to 

the site inventory. 
 NUREG/BRB0006, Rev. 7 

APPENDIX C 

EXAMPLE DOCUMENTATION OF SHIPPER AND RECEIVER DATA 

(BLOCKS 26 AND 27) 
NUREG/BR B0006, Rev. 7 
C-1 NUREG/BRB0006, Rev. 7 

EXAMPLE DOCUMENTATION OF SHIPPER AND RECEIVER DATA

(BLOCKS 26 AND 27)

EXAMPLE 1a—INITIAL REPORT

On March 31, 2008, shipper YYY transferred to receiver XXX four fabricated fuel elements 

containing the following: 

Line Element Isotope

1 FAB FUEL ELE-1 377699 g 18111 g 

2 FAB FUEL ELE-2 42114 g 1344 g 

3 FAB FUEL ELE-3 377855 g 18122 g 

4 FAB FUEL ELE-4 41992 g 1340 g 

EXAMPLE 1b—RECEIVERS REPORT

On April 1, 2008, receiver XXX acknowledged receipt of the shipment and accepted the 

shipper’s weights without further measurement. 

EXAMPLE 1c —CORRECTION 1

On April 16, 2008, the shipper corrected the element weights for lines 1 and 4 to reflect the 

adjusted element and isotope weights as well as obligated enriched uranium. 

EXAMPLE 1d —RECEIVERS CORRECTION 1

On April 23, 2008, the receiver acknowledged receipt of the correction and reported the 

corrections to NMMSS. 

EXAMPLE 2m (ACTION CODE M)

On March 31, 2008, facility XXX reported on-site inventory adjustments of fission, decay and 

production that changed their inventory of enriched uranium and plutonium. 

Example 2m-a Correction (ACTION CODE M) 

On March 31, 2007, facility XXX reported a correction to their on-site production of plutonium. 

This change also changes the quantity of obligated plutonium at the facility. 

EXAMPLE 3a—EXPORT OF A FUEL ASSEMBLY

On March 31, 2008, facility YYY reported the export of one fuel assembly to a foreign facility. 

EXAMPLE 4a—INITIAL REPORT OF AN IMPORT 

On March 31, 2008, facility XXX submitted a report documenting the shipment of three fuel 

assemblies from a foreign facility YYY. 
NUREG/BR B0006, Rev. 7 C-2 

EXAMPLE 4b—RECEIVERS REPORT OF AN IMPORT

On March 31, 2008, facility XXX submitted a report documenting the receipt of three fuel 

assemblies from a foreign facility YYY. 

EXAMPLE 5a –INITIAL REPORT OF SHIPMENT TO BURIAL SITE

On March 31, 2008, facility XXX submitted a report documenting the shipment of uranium waste 

to a burial site. 

EXAMPLE 5b –RECEIVERS REPORT OF A SHIPMENT TO BURIAL SITE

On April 5, 2008, facility VVV submitted a report documenting the receipt of uranium waste to 

the burial site. 

List of Examples: 

Example 1a: DOE/NRC Form 741—Initial report 

Example 1b: DOE/NRC Form 741—Receivers report 

Example 1c: DOE/NRC Form 741—Correction 1 (shipper adjusting lines 1 and 4 of the initial 

transaction) 

Example 1d: DOE/NRC Form 741—Correction 1 (receiver adjusting lines 1 and 4 of the initial 

transaction) 

Example 2m: DOE/NRC Form 741— Initial report (action code M) 

Example 2m-a:DOE/NRC Form 741—Correction 1 (action code M) 

Example 3a: DOE/NRC Form 741—Initial report (export from the USA) 

Example 4a: DOE/NRC Form 741—Initial report (shipment to the USA) 

Example 4b: DOE/NRC Form 741—Receivers report (shipment to the USA) 

Example 5a: DOE/NRC Form 741—Initial report (shipment to a burial site) 

Example 5b: DOE/NRC Form 741—Receivers report (shipment to a burial site) 
C-3 NUREG/BRB0006, Rev. 7 
NUREG/BR B0006, Rev. 7 C-4 
C-5 NUREG/BRB0006, Rev. 7 
NUREG/BR B0006, Rev. 7 C-6 
C-7 NUREG/BRB0006, Rev. 7 
NUREG/BR B0006, Rev. 7 C-8 
C-9 NUREG/BRB0006, Rev. 7 
NUREG/BR B0006, Rev. 7 C-10 
C-11 NUREG/BRB0006, Rev. 7 
NUREG/BR B0006, Rev. 7 C-12 
C-13 NUREG/BRB0006, Rev. 7 

 
NUREG/BR B0006, Rev. 7 C-14 
 NUREG/BRB0006, Rev. 7 

APPENDIX D

GLOSSARY
NUREG/BR-0006, Rev. 7 E-4 
 NUREG/BR D-1 B0006, Rev. 7 

GLOSSARY

AccountabilityCThe determination of, and current record maintenance of, special nuclear 

material and source material quantities associated with transfers, measured discards, 

inventories, and inventory differences that might result from theft, diversion, or other unidentified 

loss mechanisms. 

Agreement StateCA State that has signed an agreement with the U.S. Nuclear Regulatory 

Commission under which the State regulates the use of byproduct, source, and small quantities 

of special nuclear material in that State. 

Book inventoryCThe algebraic sum of the most recent physical inventory of the material balance 

area and of all inventory changes that have occurred since the physical inventory was taken. 

Concise noteCAdditional nuclear material transaction, material balance, or inventory data 

supplied, in free text format, by facilities engaged in the import and/or export of nuclear 

materials, by facilities selected under the provisions of the agreement between the United 

States and the International Atomic Energy Agency (IAEA) for the application of safeguards in 

the U.S./IAEA Safeguards Agreement, or by a facility that would like to transmit any additional 

explanatory nuclear material information. 

EURATOMCAs of January 2008, an organization consisting of the member countries Austria, 

Belgium, Bulgaria, Cyprus, the Czech Republic, Denmark, Estonia, Finland, France, Germany, 

Greece, Hungary, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, Poland, 

Portugal, Romania, the Slovak Republic, Slovenia, Spain, Sweden, and the United Kingdom. 

Foreign obligated nuclear materialCSource material or special nuclear material that is subject to 

the terms and conditions of an agreement that the U.S. Government has entered into with 

another government or group of governments. 

Highly enriched uranium (HEU)CUranium enriched to 20 percent or greater in the isotope 

uranium-235. 

Holding accountCTypically identified by four-character reporting identification symbols (RISs) 

ending in the letter H assigned by the U.S. Nuclear Regulatory Commission. Some enrichment 

facilities have holding accounts identified by three-character RISs beginning with the letter V. 

Regardless of the RIS, these accounts usually acquired inventory from the shipment of licensed 

material from the primary RIS in use at the licensee. Typically, a small number of licensees 

have used these accounts for nuclear materials not expected to be immediately processed, 

reprocessed, or disposed. However, the licensed nuclear materials in holding accounts are still 

in the licensee’s possession and must be included in inventories reported to the Nuclear 

Materials Management and Safeguards System. 

Inventory difference (ID)CThe arithmetic difference between a book inventory and the 

corresponding physical inventory that closes the material balance period. It is calculated by 

subtracting the ending inventory (EI) and removals from inventory (R) from the beginning 

inventory (BI) and additions to inventory (A) during the period between physical inventories. 

Mathematically, ID can be expressed in the following way: 
NUREG/BR-0006, Rev. 7 D-2 

ID = (BI + A - R) - EI 

where (BI + A - R) is the book inventory. 

Inventory reconciliationCThe adjustment of the book record quantity of both elements and fissile 

isotopes to reflect the results of a physical inventory. In a broad sense, inventory reconciliation 

involves the activities of calculating (1) the inventory difference (ID) for the material balance 

period in question, (2) the uncertainty value associated with the ID, (3) the active inventory for 

the period, and (4) any bias adjustment and/or prior period adjustment associated with the ID 

value. 

Low-enriched uranium (LEU)CUranium enriched below 20 percent in the isotope uranium-235. 

Material balance periodCThe time span to which a material or physical inventory pertains. 

Nuclear Materials Management and Safeguards System (NMMSS)CThe national database and 

information system for select nuclear materials controlled by the U.S. Government. This system 

was created to support national safeguards and management objectives in domestic and 

international programs. The system stores data on nuclear material transactions and 

inventories and produces a wide range of printed reports for use by the U.S. Department of 

Energy and the U.S. Nuclear Regulatory Commission and their licensees. The system is used 

to satisfy the nuclear materials information requirements of agreements between the United 

States and foreign entities. In addition, the system provides the reporting interface between 

facilities selected under the provisions of the U.S./International Atomic Energy Agency 

Safeguards Agreement. 

Physical inventoryCA physical determination of the quantity of nuclear material on hand at a 

given time. The methods of physical inventory and the associated measurements vary, 

depending on the material to be inventoried and the process involved. A book inventory 

between physical inventory takings can be determined based on the physical inventory quantity 

from the prior period together with all subsequent inventory changes associated with the 

determination of that book inventory. The primary purpose of a physical inventory is to confirm 

the absence of (or to detect) a loss, theft, or diversion of special nuclear material. 

Report period—Period inclusive of defined dates (e.g., October 1, 2005, through September 30, 

2006). Reports for a reporting period, such as inventory, material balance, and related 

transactions reports, must assure that no dates are undocumented between the previous and 

current submittals. 

Reporting identification symbol (RIS)CA unique combination of three or four letters that is 

assigned to each reporting organization by the U.S. Department of Energy or the U.S. Nuclear 

Regulatory Commission for the purpose of identification in the Nuclear Materials Management 

and Safeguards System database. 

Shipper-receiver difference (SRD)CThe difference between what a shipper claims a shipment of 

special nuclear material contained and what the receiver claims it received, in cases where both 

the shipper’s and receiver’s values are based on measurement. 
 NUREG/BR D-3 B0006, Rev. 7 

Source materialCUranium or thorium, or any combination thereof, in any physical or chemical 

form; or ores that contain by weight 0.05 percent or more of uranium, thorium, or any 

combination thereof. Source material does not include special nuclear material. 

Special nuclear material (SNM)CPlutonium, uranium-233, and uranium enriched in the 

isotope 233 or 235. 

U.S. Government ownedCNuclear material that, while used by a licensee as part of its activities, 

is actually an asset owned by a Federal Government agency such as the U.S. Department of 

Energy. These materials may be bulk materials, discrete radiation sources, or finished products. 

Such materials may represent a lease or loan arrangement with a Government agency. 

Government-owned materials are typically represented by the owner code G on shipping 

information (i.e., DOE/NRC Form 741) and inventory documentation (i.e., DOE/NRC 

Forms 742 and 742C). One way a licensee can make a determination that nuclear material in its 

possession is Government owned is to review the licensee’s DOE/NRC Form 741 documentation 

listing the original receipt of the material. If such material is Government owned, the owner 

code G will appear on the licensee’s portion of the form. 
NUREG/BR-0006, Rev. 7 D-4 
 NUREG/BR-0006, Rev. 7 

APPENDIX E 

DOE/NRC FORM 740M, “CONCISE NOTE,” (BLANK) AND 

DOE/NRC FORM 741, “NUCLEAR MATERIAL TRANSACTION REPORT” 

(BLANK) 
NUREG/BR-0006, Rev. 7 
 E-1 NUREG/BR-0006, Rev. 7 
NUREG/BR-0006, Rev. 7 E-2
 NUREG/BR-0006, Rev. 7 

APPENDIX F 

SUPPLEMENTAL INSTRUCTIONS FOR COMPLETING 

BLOCKS 17, 18, 19, 20, AND 21 ON DOE/NRC FORM 741 
NUREG/BR-0006, Rev. 7 
 F-1 NUREG/BR-0006, Rev. 7 

SUPPLEMENTAL INSTRUCTIONS FOR COMPLETING 

BLOCKS 17, 18, 19, 20, AND 21 ON DOE/NRC FORM 741

1. Introduction 

Special procedures must be used to implement some of the reporting requirements of the 

U.S. Bilateral Agreements for Peaceful Nuclear Cooperation. These Agreements for 

Cooperation are one means to satisfy Section 123 of the Atomic Energy Act of 1954 and allow 

the U.S. nuclear industry to trade with foreign countries/entities. The agreements require that the 

United States track and report foreign obligated nuclear materials and nuclear material produced 

from obligated material from these countries/entities. A foreign obligation is a commitment by 

one government to another to treat nuclear materials, nonnuclear materials, and equipment and 

components in a manner consistent with the agreement signed by the two governments. 

In addition to these Agreements for Cooperation, the United States is also required (pursuant to 

the U.S./Russian agreement concerning the disposition of highly enriched uranium extracted 

from nuclear weapons) to track and report to Russia the imports, exports, and use of former 

Soviet Union downblended highly enriched uranium. Although not a U.S. Bilateral Agreement for 

Peaceful Nuclear Cooperation, this agreement contains similar reporting requirements and will 

be tracked as such. Facilities that are importers and/or exporters of nuclear material should also 

comply with the agreement. 

The exchange of obligations can occur only between like materials (i.e., material type (MT) 10, 

50, 70, 81, E-1, E-2, E-3, or E-4) within the following constraints: 

$ No exchange of material from one MT to another is allowed unless the U.S. Government 

provides written prior approval. For example, downblending of E-3 enriched uranium that 

results in a lower category (i.e., E-3 of obligated material to become E-1 material) 

requires written prior approval of the U.S. Government. 

$ The obligated material must be exchanged for similar material unless the 

U.S. Government provides written prior approval. For example, nonirradiated material 

may not be swapped for irradiated nuclear material unless the U.S. Government provides 

written prior approval. 

$ Obligation exchanges involving a licensee of the U.S. Nuclear Regulatory Commission 

(NRC) and an entity of the U.S. Department of Energy require the NRC’s written prior 

approval. 

$ Obligation exchanges between two parties must be for the same material quantities. 

Additionally, the obligations exchanged must match (i.e., the obligation “shipped or 

removed” by one participant is “received or added” by the second party to the 

transaction). 
NUREG/BR-0006, Rev. 7 F-2

2. Imports 

For U.S. facilities importing nuclear material with foreign obligations, the relevant obligation 

information will be supplied by the appropriate Government agency. The notification will provide 

the information necessary to complete blocks 17–21, if applicable: 

• For imports, the foreign obligation information can be (1) the country/entity from which the 

nuclear material was shipped and/or (2) the country/entity attaching “third-party 

obligations.” In most cases, for imports from a country that has made the entire shipment 

subject to the agreement, the total import quantity will be obligated. If only a portion of 

the shipment is subject to an agreement (third-party obligation), the documentation will 

clearly specify that amount. 

• For the completion of blocks 17–21, the Government notification will supply (1) the 

country/entity of obligation, (2) the MT, and (3) the amount obligated. (See Table 1 below 

for country/entity codes. See Table 2 below for reportable obligated MTs and quantities.) 

Table 1 

Obligation Code Country/Entity

31 Australia

32 Canada 

33 EURATOM 

34 Japan 

35 People’s Republic of China 

37 Switzerland 

38 Argentina 

39 Brazil 

40 Chile 

81 Australia/Japan 

82 Canada/Japan 

83 EURATOM/Japan 

84 Australia/EURATOM/Japan 

85 Canada/EURATOM/Japan 

86 China/Japan 

87 Australia/Canada 

88 Australia/EURATOM/Canada 

91 Australia/EURATOM 

92 Canada/EURATOM 

WR Former Soviet Union Weapons 

material 

Note: For any other obligation codes, contact the Nuclear Materials Management and 

Safeguards System (NMMSS) for further instructions. 
 F-3 NUREG/BR-0006, Rev. 7 

Table 2 

Reportable MTs and Source and 

Special Nuclear Material 

Type Domestic Code

Normal uranium MT 81 

Depleted uranium MT 10 

Thorium MT 88 

Plutonium MT 50 

Enriched uranium MT 20 

Uranium-233 MT 70 

• Licensees should complete the obligation information as follows: 

Block 17: LINE NUMBER—The shipper will enter a sequential number beginning with 

the number 1 for each obligated country or material. If there is more than one separate 

obligation or more than one obligated MT, enter the appropriate numbers in the 

subsequent lines. 

Block 18: COUNTRY OF OBLIGATION—For each line, enter the code in Table 1 that 

represents the country/entity of obligation. 

Block 19: MATERIAL TYPE—For each line, enter the domestic code in Table 2 that 

represents the material obligated. 

Block 20: OBLIGATED ELEMENT WEIGHT—For each line, enter the weight obligated in 

the reportable quantity specified in Table 2. Positive or negative values should be 

entered to appropriately account for material addition or removal, respectively. 

Block 21: OBLIGATED ISOTOPE WEIGHT (FOR ENRICHED URANIUM ONLY)—For 

each line of enriched uranium, enter the obligated isotope weight in grams. (Obligated 

uranium-235 is restricted to uranium enriched to 5 percent or less, unless higher 

enrichment is authorized or approved by the U.S. Government.) Positive or negative 

values should be entered to appropriately account for material addition or removal, 

respectively. 

3. Domestic Transfers, Internal Transactions, and Exports 

For U.S. facilities shipping or exporting material with foreign obligations, or for the reporting of 

onsite gains and losses, the obligations on the material must be stated as such in blocks 17–21: 

• For domestic transfers, fill out blocks 17–21 as for imports (Section 2 above). However, 

the obligation information will not be supplied by a government notification. The 

U.S. shipper will assign the appropriate obligations on the material, if any, and complete 

the line number, country/entity of obligation, MT, and obligated weight, if applicable. The 
NUREG/BR-0006, Rev. 7 F-4

U.S. receiver will complete the matching obligation information as assigned by the 

shipper. 

• For internal transactions (e.g., burnup, decay, production, measured discards, accidental 

losses or gains, category changes, fission and transmutation, inventory differences), 

enter the line number, country/entity of obligation, MT, and obligated weights, if 

applicable, for the material. 

• The domestic facility must obtain the information necessary to complete DOE/NRC 

Form 741 for the foreign facility for all imports of special nuclear material and source 

material. In the case of exports, the shipper initiates a DOE/NRC Form 741 report, and 

the NMMSS will generate a DOE/NRC Form 741 report using shipper information. 

However, if a significant shipper-receiver difference is identified between the U.S. shipper 

and foreign receiver (as defined in Title 10, Section 74.31, “Nuclear Material Control and 

Accounting for Special Nuclear Material of Low Strategic Significance,” of the Code of 

Federal Regulations (10 CFR 74.31), 10 CFR 74.43, “Internal Controls, Inventory, and 

Records,” or 10 CFR 74.59, “Nuclear Material Control and Accounting for Special Nuclear 

Material of Low Strategic Significance,” for special nuclear material, or if there is an 

indication of loss, theft, or diversion of quantities of source material delineated in 

10 CFR 40.64 (c)(1)), the shipper is required to document the foreign party’s values in a 

DOE/NRC Form 741 report to the NMMSS. Submittal for a foreign facility does not 

indicate a responsibility for the other facility or its shipment/receipt of materials.