ML20149A937
| ML20149A937 | |
| Person / Time | |
|---|---|
| Issue date: | 07/14/1997 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-BR-0006, NUREG-BR-0006-R03, NUREG-BR-6, NUREG-BR-6-R3, NUDOCS 9707140048 | |
| Download: ML20149A937 (74) | |
Text
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,,I United States Nuclear Regulatory Commission N,;;,/
Instructions for Completing
' Nuclear Material Transaction Reports and Concise Note Fonns (Forms DOE /NRC-741,741 A and 740M)
OI bPOL lssued by the Office of Nuclear Material Safety and Safeguards 9707140048 970714
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TABLE OF CONTENTS Page I.
PURPOSE AND SCOPE................................................
1 II.
GENERAL PROCEDURES...............................................
2 A.
DOE /NRC Form 741 Blocks....................................
2 B.
Distribution of DOE /NRC Form 741 or Facsimile...............
18 1.
Shipper................................................
18 2.
Receiver...............................................
18 II
I. PROCEDURE
FOR CONTINUATION PAGE..................................
19 IV.
PROCEDURE FOR ONSITE GAINS AND LOSSES ("M" ACTION CODE)..........
19 A.
DOE /NRC Form 741 Blocks.....................................
19 B.
Distribution of DOE /NRC Form 741 or Facsimile...............
21 V.
PROCEDURES FOR CORRECTIONS TO DOE /NRC FORM 741 OR FACSIMILE......
22 A.
Correction of Blocks 1 through 23...........................
22 B.
Correction of Blocks 24 or 25...............................
22 C.
24 D.
Distribution of Corrections to DOE /NRC Form 741 or Facsimile.
24 VI.
DOE Reporting Requirements for Proprietary Interests of the Government.......................................................
25 Appendix I
- Listing of Identification Codes for U.S. Customs Ports.
26 Appendix II - Composition and Nature of Transaction Codes............
39 Appendix III - Supplemental Instructions for Completing Blocks 24.J and 25.J of DOE /NRC Form 741......................
43 Appendix IV - Instructions for Completing DOE /NRC Form 740M for a Concise Note...........................................
50 Appendix V
- Invento ry Change Type Code s............................
54 Appendix VI - Sample Letter to Correct Header Information (Blocks 1 through 23) 62 Appendix VII - Examples of Documents Correcting Shipper and Receiver Data (Blocks 24 and 25)................................
64
e, i
N ADDITIONAL REFERENCES The Nuclear Materials Management and Safeguards System (NMMSS) reports listed below are referenced in the following pages.
To request the below listed manuals, telephone the NMMSS office in Oak Ridge, Tennessee, (615)S76-2297.
International Nuclear Facilities Codes Manual NMMSS Report 0-15 Transaction Composition Code Reference List NMMSS Report D-25 i
V
i INSTRUCTIONS TO NRC AND AGREEMENT STATE LICENSEES FOR REPORTING NUCLEAR MATERIAL TRANSFERS ON DOE /NRC FORM 741 - NUCLEAR MATERIAL TRANSACTION REPORT AND DOE /NRC FORM 740M - CONCISE NOTE U.S. NUCLEAR REGULATORY COMMISSION NUCLEAR MATERIAL TRANSACTION REPORT I.
PURPOSE AND SCOPE The U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (00E) jointly utilize a Nuclear Materials Management and Safeguards System (NMMSS).
Common reporting forms are used to minimize the reporting burden upon industry members required to provide nuclear material data to one or both agencies in accordance with prevailing regulations or contrac-tual obligations. In this manner, the licensee is able to file one report and meet the reporting requirements of both NRC and DOE, rather than hav-ing to file different reports for each Agency-required response.
Compliance with specific reporting requirements is monitored by the agency for which the specific data is required.
The decision to report should be based on the total material shipped or received prior to rounding.
NRC Regulations (40.64, 150.17) require NRC and Agreement State specific licensees to complete and distribute DOE /NRC Form 741 for:
Any source material (depleted uranium, natural uranium, or thorium) inventory changes, including shipments, receipts, onsite gains or losses or any other inventory adjustment, involving one kilogram or more of foreign origin source material.
Imports and exports are to be reported regardless of origin.
NRC Regulation (75.31) requires NRC and Agreement State specific licensees to complete and distribute DOE /NRC Form 741 for:
Any source material (depleted uranium, natural uranium, or thorium) inventory changes, including shipments, receipts. onsite gains or losses or any other inventory adjustment, involving one kilogram or more of source material of any origin.
NRC Regulations (74.15, 75.34, 150.16) require NRC and Agreement State specific licensees to complete and distribute DOE /NRC Form 741 for:
Any special nuclear material (SNM) inventory changes, including ship-ments, receipts, burnup, production, onsite gains or losses, inven-tory dif ference, or any other inventory adjustment, involving one gram or more of contained uranium-235, uranium-233, or plutonium, or any combination thereof.
Submission of DOE /NRC Form 741 is normally required as a matter of contract or lease administration for all DOE-owned nuclear material transferred, 1
l.
regardless of quantity (see DOE Orders, series 5600).
A facsimile of DOE /NRC Form 741 may be used.
' Reports are required whenever nuclear material in the above types and
-amounts moves between locations or operations'that have been assigned different Reporting Identification Symbols:(RIS) by the NRC and/or DOE, and-for the reporting of SNM and source material inventory changes.
The frequency for reporting nuclear material loss data (including burnup, pro-duction, measured discards,* and decay) is as follows:
HEU and LEU fuel fabrication plants every 2 months Power and research reactors; all others every 6 months Source material once per year The form is initiated by the shipper except where a licensee receives mate-rial from or ships material to someone who is not required to prepare a 00E/ NRC Form 741 (for example, from or to a foreign source.) In these instances, the receiver / shipper must obtain all information from the for-eign exporter / importer (either directly or through an agent of the exporter or of the licensee) necessary to complete the shipper's or receiver's par-tion of DOE /NRC Form 741; record both shipper's and receiver's information on-DOE /NRC Form 741; attach a DOE /NRC Form 740M, Concise Note, if required as described in Appendix IV.
Distribute the form according to Section II.B, IV.B or V.D.
CLASSIFIED REPORTS - DOCUMENTATION AND DISTRIBUTION Any DOE /NRC Form 741 which is classified " SECRET" must be documented in accordance with all pertinent security requirements and the RIS assigned to each person who is to receive a copy of the report must be entered under
" Distribution of Copies." The RIS of Martin Marietta Energy Systems, Inc.
ORGDP/ Records Dept., P.O. Box 2003, Oak Ridge, Tennessee 37831, is QFA.
II.
GENERAL PROCEDURES A.
DOE /NRC Form 741 Blocks The numbered instructions which follow correspond to the numbered blocks on DOE /NRC Form 741 to be completed.
The numbers in parentheses within the various blocks should be disregarded as they are used for data proc-essing purposes and signify the data retained by the NMMSS.
Each shipper of reportable quantities of special nuclear material or source material shall dispatch a DOE /NRC Form 741 with the shipment, a copy to Martin Marietta Energy Systems, Inc. and a copy to the receiver's business address on the same day the material is shipped or, in any case, no later than the close of business the next working day.
In the case of spent fuel shipments, and in accordance with 10 CFR 73.37, the date of shipment is " Safeguards Information" until ten (10) days after the shipment or the last shipment in a series of shipments is received.
Therefore, the Form 741 should be stamped " Safeguards Information" and handled according to 10 CFR 73.21.
- NOTE:
Burials are reported when shipped.
2
.i The DOE /NRC Form 741 should be completed in accordance with the following
-instructions:
1.
SHIPPER'S RIS - If you are the shipper, enter your RIS in the
" Shipper's RIS" block.
In the case of an export, enter your IAEA material balance area code (MBA) in parentheses following your domestic RIS.1 If you are the receiver of an import, enter the shipper's IAEA MBA code in parentheses following L
the shipper's four-character foreign facility RIS.2 2.
-RECEIVER'S RIS - If you are the shipper of a domestic transfer, enter the receiver's RIS in the " Receiver's RIS" block.
In the case of an import, enter your IAEA material balance area code (MBA) in parentheses following your domestic RIS.1 If you are the shipper of an export, enter the receiver's IAEA MBA code following the foreign receiver's four-character foreign facility RIS.2 3.
TRANSACTION NUMBER - Enter a consecutive number for the same shipper-receiver combination in the " Transaction No." block.
Numbers in the series should be consecutive; i.e., no skipped numbers.
4.
CORRECTION NUMBER - This block is used to identify a transaction which is an adjustment to a previously issued transfer document (741). Leave blank on the original submission of a 741.
Use number 1-9, consecutively, for adjustments.
See Section V.
S.
PROCESSING CODE - For NRC use only.
6.
RESERVED - For NRC use only.
J-l 7,
ACTION CODE - This block is used to identify the type of transac-tion event being reported on the 741.
Enter one of the following:
" SHIPPER" block -
l A - shipper is reporting its statement describing a transaction that has taken place between the stated parties, i
l C - shipper is adjusting the initial report (741) of the ship-ment or a previous adjustment to the same initial report, or acknowledging an adjustment originated by the receiver, or L
accepting and agreeing with the receiver's adjustment to the 741.
See Section V.
lIAEA MBA codes for all U.S. facilities can be derived by prefixing your l ~
domestic RIS with the letter "U", e.g., the domestic RIS "XYZ" would become "UXYZ".
2The IAEA MBA codes for foreign facilities and the Four-character foreign facility codes can be derived by referring to the INTERNATIONAL NUCLEAR.
FACILITIES CODES MANUAL (NMMSS Report D-15).
l 3
1 e
e M
reporting a one party transaction or an adjustment to a one-party transaction, i.e., an onsite gain or loss of material due to burn up, production, measured discards, etc., such as the inventory changes shown on material balance reports (00E/NRC Form 742).
See Section IV.
" RECEIVER" block -
B receiver is reporting that a shipment has been received and that-the weights reported by the shipper on the 741 were accepted without further measurement oy the receiver.
E receiver is reporting that a shipment was received and that independent measurements were made and that the values resulting from the independent measurements are being reported.
D receiver is adjusting the initial report (741) of the receipt of the 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 adjust-ment to the 741.
.See Section V.
M reporting a one party transaction or an adjustment to a one-party transaction, i.e., an onsite gain or loss of material due to burn-up, production, measured discards etc., such as the inventory changes shown on material balance reports (DOE /NRC Form 742).
See Section IV.
N receiver is reporting physical receipt of a shipment but will be delaying the quantity determinations for the shipment of material for 10 to 30 days (at which time a 741 with a "B" or "E" action code is prepared to report the receiver's quantity' decision).
U receiver is reporting physical receipt of a shipment of scrap or irradiated material but will be delaying the quantity determinations for the shipment of material for more than 30 days but less than 60 days (at which time a 741 with a "B" or "E" action code is prepared to report the receiver's quantity decision).
8.
DATA CODE - For NRC use only.
9.
NAME AND ADDRESS OF SHIPPER -
A.
Enter shipper's organization name and address.
B.
Enter shipper's license number.
C.
Enter an Attention Line, if necessary.
D.
Enter shipper's telephone number.
4
10.
NAME AND ADDRESS OF RECEIVER -
A.
Enter receiver's name and address.
B.
Enter receiver's license number, if applicable.
C.
Enter an Attention Line, if necessary.
q D.
Enter receiver's telephone number.
11.
NUMBER OF DATA LINES -
Af ter completion of Block 24, " Shipper's Data," enter the total number of detail line entries of shipper's data in this block.
12.
NATURE OF TRANSACTION -
DOE-0wned Material - Complete this block for DOE-owned special nuclear material or source material under DOE contracts or lease or loan agreements, material sold for or to DOE, material transferred pursuant to an enriching service agreement, or material donations to or from D0E.
Privately Owned Material - This block may be used to reflect a non-DOE transaction involving privately owned material.
To do so, it is imperative that blocks 12, 24.1 and 25.I be in agreement.
See Appendix II for a list of transaction codes to be entered here.
13.
SHIPPED FOR ACCOUNT OF -
I DOE-0wned Material - Complete this block if the special nuclear material or source material is DOE owned.
Enter the RIS (Block 13b), and name and address of the person having lease or financial responsibility for the material.
If the name and address are the same as block 9, state "same."
Privately Owned Material - This block may be used to reflect a non-DOE transaction involving privately owned material.
Enter the name and address of the person owning the material.
If the same as block 9, state "same."
14.
SHIPPED TO ACCOUNT OF -
DOE-0wned Material - Complete this block if the material being transferred is DOE owned.
Enter the RIS (Block 14b), name and address of the person assuming lease or financial responsibility for the material.
If the name and address are the same as block 10, state "same."
Privately Owned Material - This block may be used to reflect a non-00E transaction involving privately owned material.
Enter 5
1 the name and address of the person assuming lease or. financial responsibility for the material.
If the same as block 10, state'"same."
15.
TRANSFER AUTHORITY -
DOE-Owned Material - If the material is 00E owned, enter such transfer authority as may be appropriate, e.g., DOE Contract Number, Lease. Agreement Number, Nuclear Material (NM) order number, or purchase order number.
If the transfer is being made as a result of the NM Draft (Form DOE-437), enter the draft number.
Privately Owned Material - Optional.
16.
EXPORT OR IMPORT TRANSFERS -
A.
For all export or import transfers, enter the NRC export or import license number, respectively, under which special nuclear material or source material is being transferred.
Where transfers are authorized by a general license, enter
" Gen-Lic".
There may also be cases where the transfer is exempt from licensing.
If so, enter "Lic-Exempt".
If several batches authorized by separate licenses are combined into one shipment, a separate DOE /NRC Form 741 must be filed for each license involved.
B.
For all export or import transfers, enter the U.S. Port of Exit / Entry code designating where the shipment exited or entered the United States.
Appendix I to these instruc-tions contains a listing of all United States Customs Ports and their assigned four digit codes.
17.
MATERIAL TYPE AND DESCRIPTION -
Enter the type of special nuclear material (Pu, Pu-238, U-233, or uranium enriched in the isotope U-235 and if <20% or >20%),
or source material (depleted uranium, natural uranium, thorium),
together with its physical and chemical form.
Enter whether 4
material being transferred is irradiated.
18.
TRANSPORTATION PROFILE - No entry required.
19.
PACKAGE IDENTIFICATION - No entry required.
20.
ACTION DATE -
A.
Entry required by shipper.
Enter the date the nuclear material is shipped.
If an import, also enter the IAEA country code in parentheses (see International Nuclear Facility Codes Manual, NMMSS Report D-15) for the foreign shipper in the space immediately following the word " ship-ment."
If an export, enter the U.S. IAEA country code in parentheses (i.e., "U") in the space immediately following 6
'..i...
23.
TOTAL VOLUME (Waste Transfers Only) -
For transfers of nuclear material to or from nuclear waste sites (i.e., if the shipper or 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.
Does not apply j
to transfers to nuclear laundry services.
24.
SHIPPER'S DATA -
Shipper and receiver measurement data are entered on Form DOE /
)
NRC Form 741 for each " batch" of material.
For licensees report-ing pursuant to 10 CFR Part 75 requirements or if the transfer is an import or an export, " batch" is defined as a portion of nuclear material handled as a unit for accounting purposes at a key measurement point and for which the 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.
Material being transferred with all the below data elements identical may be listed on one line of Form DOE /
NRC Form 741 (except as noted below).
Material differing in regard to any of these data elements must be listed on separate lines:
j Country Control Number.
DOE Project Number and Identification (if applicable).
Material Type.
Composition.
l Ownership.
l Weight % Isotope (if applicable).
' Note, however, that.two or more lines may be necessary to des-cribe a single batch (e.g., spent fuel assemblies, mixed oxide fuel).
If a batch consists of several types of nuclear material, several consecutive lines will be used to describe the batch.
The same name is repeated on all lines to describe all the condi-tions in a single batch.
The " Number of Items," block 24.D, is also repeated on all lines for the same batch name.
Although this is the formal definitien of a " Batch" under 10 CFR Part 75, the above general rules for grouping or batching mate-rial for reporting purposes are also applicable to licensees reporting imports or exports pursuant to 10 CFR Part 74 or Part 40.
For other transactions reported pursuant to 10 CFR Part 40 or Part 74 batch name entry and uniqueness are optional.
NOTE:
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 appro-priate accounts (MT 10, 20, 81, etc.) are properly adjusted.
8
the word " shipment."
In the case of an export, the shipper is' required to complete both items 20A and 20C.
B..
Entry required by shipper.
If the document is an acknowl-edgement or a correction to a previously issued transaction report, enter the date the correction is recorded or the acknowledgement is made, as appropriate.
C.
Entry required by receiver.. Enter the date the nuclear material is received.
In the case of an import, the receiver is required to complete both items 20C and 20A.
D.
Entry required by receiver.
Enter the date nuclear material is measured by receiver.
Required only if receiver's action code is "E."
E.
Entry required by receiver.
If the document is an acknowl-edgement or a correction to a previously issued transaction report, enter the date the correction is recorded or the acknowledgement made, as appropriate.
21.
A.
MISCELLANE0US -
This block provides space if needed for further clarifica-tion of.Other entries on the form, and for shipper-to-receiver communications.
B.
DOE /NRC FORM 740M ATTACHED - SHIPPER Check the appropriate box to indicate whether or not a concise note is attached.
(If you check "yes", see Appen-dix IV for instructions for preparing DOE /NRC Form 740M.)
If reporting a domestic transfer pursuant to 10 CFR Part 75, a Concise Note may be necessary.
If reporting an export pursuant to either 10 CFR Parts 40, 74, or 75, a Concise Note is required.
C.
DOE /NRC FORM 740M ATTACHED - RECEIVER Check the appropriate box to indicate whether or not a concise note is attached.
(If you check "yes", see Appen-dix IV for instructions for preparing DOE /NRC Form 740M.)
If reporting a domestic transfer pursuant to 10 CFR Part 75, a Concise Note may be necessary.
In the case of an import, a concise note may be necessary.
(See Appendix IV to determine if required and for instruction for preparing DOE /NRC Form 740M.)
22.
TOTAL GROSS WEIGHT -
Enter the total gross weight of the shipment rounded to nearest
. pound.
An approximate or estimated gross weight rounded to the nearest pound figure is acceptable.
I 7
+
e A.
Line Number - In providing detailed measurement data, enter a line number beginning with 01 (to 99) for the first line of detail 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:
(1) different material types of multi-enrichment fuel rods entered on separate lines, but with the same batch name; and, (2) when UFs product material and UFs heel material in a cylinder are reported on separate lines, the two lines must have the same batch name.
Refer to the instructions in Section IV'for action code M.
B.
Type of Inventory Change - All changes to inventory that meet the reporting criteria must be reported on DOE /NRC Form 741.
There are twenty-nine (29) ICT codes.
They can be categorized into several groups.
A large group of these will requ're no entry in this block by the licensee since the information required to determine the ICT is reported elsewhere on the form.
There is a group of seldom used codes that may occur in facilities covered by the note in G, such as de-exemption use, de-exemption quantity and exemption use, exemption quantity, and termination non-nuclear use, which will be addressed as they occur through direct contact between the licensee and the NRC.
There is a third group for on which entry in this block is mandatory.
Appendix V defines and categorizes each ICT code.
When the ICT code for a normal operational loss / measured discard / accidental loss (LD, TW, FW) is used, additional information is required.
There are four dispositions of measured discards for which data is to be reported:
(1) when material is discarded into the atmosphere (A);
(2) when material is discarded through ground effluents (G);
(3) when material is discarded into a pond or lagoon (L);
and (4) when material is transferred to a holding area (H) at the facility pending possible shipment offsite for disposal.
When any of the above occurs, a DOE /NRC Form 741 should be prepared.
The shipper will enter his own RIS in the
" Shipper's RIS" block (block 1), and the same RIS in the l
" Receiver's RIS" block (block 2), but append the receiver's RIS with an "A," "G,"
"L," or "H," as appropriate.
For example, if a facility with RIS "XYZ" discards material to a lagoon, the transaction on the Form 741 would be from XYZ to XYZL.
l 9
l
-_______--____-___---________________--___-__-___-____a
I s
C.
Identification (Batch Name) - A name or number, or a com-bination of both, that is common to the reporting facility and identifies the batch of material involved in the ship-ment.
If the licensee is reporting pursuant to 10 CFR Part 75,.or if the transfer is an import or export, this item must be completed as follows:
the shipper or receiver makes an entry which identifies a unique portion of nuclear material handled as a unit for accounting purposes.
Batch name is limited to 16 characters with the right hand eight characters uniquel to the reporting facility.
For fuel assemblies pins and rods, batch name should be the identi-fication number of the fuel assembly pin or rod.
In the case of an import the receiver must use.the same batch name as the shipper provided the shipper's batch name conforms to the above specifications.
If it does not see the Concise Note instructions (Appendix IV).
D.
Number of Items - Enter the number of similar items of which the line entry consists; i.e., cylinders, packs, drums, bird cages, bottles, tank vessels, etc. 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 repre-sented on the line entry.
In the case of transfer of bulk material, enter a 1.
E.
Project Number - Enter the DOE Project Number (s) for which DOE-owned material is, to be used; otherwise, leave ' blank.
F.
Material Type - Enter the appropriate special nuclear mate-rial, or source material type code from the list below.
U.S. CODE IAEA CODE.
(Domestic (Imports /
transfers)
Exports)
DESCRIPTION 10 D
Depleted uranium 20 EG Enriched uranium 50 P
Plutonium 70 EK 2339 81 N
Normal uranium 83 Pu Pu-238*
88 T
- Use this code only if Pu-238 is greater than 10%
of total Pu by weight; otherwise use code 50.
G.
Composition / Facility Code - Enter the appropriate code describing the physical (unencapsulated, encapsulated) and iThe batch name must be unique to the reporting facility for the duration of the material balance period in which reported.
10 i
V
chemical form of the material from Appendix II, Composition Code.
NOTE:
If your installation has been notified by letter from the NRC, as provided in 10 CFR S 75.11, that it has been identified under the U.S./IAEA Safeguards l
Agreement, enter the appropriate code from the list i
developed during the formulation and negotiation of your facility attachment or_ transitional facility attachment (after such document has'been provided to you under 10 CFR S 75.8).
In accordance with 10 CFR S 75.11, any change in facility operations or proc-esses that would result in any changes to, additions in or deletions from the list should be communicated to the NRC in writing, to the extent provided in your license conditions, at least 70 days in advance of the changes so that new composition codes can be assigned.
H.
Production Code - For DOE use only.
I.
Owner Code - This code describes the ownership of the mate-rial at the time it was in the shipper's possession.
Enter the appropriate code from the list below.
Code Description A
DOE loan material - Lease Agreement - Waiver of Use Charge)
B DOE lease material - Lease Agreement-Non-Waiver of Use Charge G
DOE owned material H
Owned by other U.S.-Government Agencies J
Privately owned (domestic)
R Privately owned (foreign) 5 DOE uwned, lease or loan agreement (foreign)
J.
Country Control Number - This block is used to reflect a
" Country Control Number" (CCN), a code assigned to material upon its import into the U.S., material transferred within the U.S., and material exported from the U.S.
Each CCN is structured to be an eight (8) character code consisting of four, distinct, two-character codes.
The first two characters indicate the country of origin of the source material and are required for all transactions.
The remaining characters (three through eight) are to be com-pleted, if applicable.
The second set of two characters 11
I indicates _ the country providing the isotopic separation services; the third set of two characters indicates the country in which reactor products (Pu or U-233) are pro-duced; and the last two characters identify any other country (ies) or international' organizations (s) attaching conditions
- to the material in addition to any condition (s) that may be attached by a country identified in set one, two, or three, above.
This unique code established for each combination of country (ies) or organization (s) attaching conditions, and represented by these last two characters, is maintained in the system as part of the CCN reference file.
The reference file contains all CCN's structured alphanumerically.
NOTE:
The two-character alpha symbol that identifies the country (ies) in the CCN is derived as follows:
(1) to identify a foreign country, the two character symbol is derived by dropping the "R" at the beginning of the standard foreign country RIS and using the next two letters; and, (2) to identify the United States as a country within the CCN, use "US."
For further information needed for the completion of this block, refer to the detailed CCN instructions that appear I
in Appendix III of these instructions.
K.
Key Measurement Point (KMP) - (The next two items (K and L) apply only to licensees reporting pursuant to the require-ments of 10 CFR Part 75.) This block is for the reporting of a location where nuclear material appears in such form that it may be measured to_ determine material flow or inventory.
Codes for KMP's will be identified in the facil-ity attachments or transitional facility attachments developed for those facilities described in the Note in 24.G.
All others leave blank.
L.
Measurement Identification (see K above) - This block also applies only to those facilities covered in the Note in 24.G above.
All others leave blank.
This code indicates where and when the material was measured.
It consists of three (3) parts.
(1) Basis -
Enter the pertinent one-character code from the following:
7" Attached conditions" are described in the supplemental instructions in Appendix III.
12 e
x e
N - if. batch data are based on measurements made in an IAEA MBA other than the reporting MBA.
L - if 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 (Nuclear Materials Transaction Report) or a 00E/
NRC Form 742C (Physical Inventory Listing).
M - if batch data are based on measurements made in the reporting IAEA MBA and the data were not previously reported.
T - if 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.
(2) Other Measurement KMP (OMP) - For batch data designated code "M" under Measurement Basis, enter the code of'the KMP where measurements were made if different from the KMP indicated in K above.
If the same,' leave blank.
(3) Measurement Method - If there are two or more measure-ment methods employed at the same KMP which have a different measurement uncertainty, enter the code for the measurement method used, as identified in your Facility Attachment.
M.
Gross Weight - Enter the gross weight in pounds, i.e., weight of material shipped plus packaging and shipping container, of the line entry.
An approximate or estimated gross weight figure is acceptable in this block.
NOTE:
Where it is necessary to'use gross and net weights that are different from the prescribed reporting unit (pounds), the specific weight unit used must be entered on the report.
N.
Net Weight - Enter weight of material shipped excluding packaging and container weight, in pounds.
O.
Element Weight - Enter the weight of the contained special nuclear material or source material rounded to the quantities reported below.
Material Units Plutonium or uranium enriched Nearest whole gram in U-235 or U-233 Pu-238 Nearest 1/10 gram Source material Nearest kilogram For quantities that round to zero enter an asterisk (*).
13
/
P.
Element Limit of Error - Limits of error are only required to be reported by licensees authorized to possess at any time and location special nuclear material in a quantity exceeding one effective kilogram and to use special nuclear material for activities other than those involved in the operation of a nuclear reactor licensed pursuant to 10 CFR Part 50; those involved in a waste disposal operation; or as sealed sources (10 CFR 70.58(e)).
Complete when the total shipment contains more than 50 grams of U-235, U-233 or plutonium, or any combination of these.
Enter the Limit of Error for each element entry using the same weight units as in block 24.0, except where the line entry represents a sealed plutenium-beryllium source (com-position code 481); samples which have been determined by other means to cantain less than 10 grams U-235, U-233, or plutonium each (composition code 771); and reactor-irradiated fuels (composition code 375) involved in research, devel-opment, and evaluation programs in facilities other than irradiated-fuel reprocessing plants.
Limits of error are to be at the 95% confidence level, propagated by the uncertainties of the weight measurement, the chemical analysis, and the sampling method.
Limits of error need be entered only on the copy submitted to the NRC and on the record copy.
Limits of error do not apply for source material. Licensees making onsite transfers between two different RIS's or the same RIS are exempt from supply-ing 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.)
Q.
Weight % Isotope - Enter the weight percent of the isotope U-235 if uranium enriched or depleted in U-235.
If pluto-nium, enter the weight percent of the isotope Pu-240.
If Pu-238, enter the weight percent of the isotope Pu-238.
Report weight percent to at least two but not more than four decimal places, depending upon the accuracy yielded by the measurement method employed.
Example of weight percent isotope to four decimal places:
XX.XXXX%.
For U-233, enter the parts per million of U-232. Does not apply for normal uranium and thorium.
Use separate lines to report material of different enrichments.
R.
Isotope Weight - Enter the isotope weight.
If enriched uranium or U-233, enter weight to the nearest gram of U-235 or U-233 as appropriate.
If plutonium, enter the sum of Pu-239 and Pu-241 to the nearest gram.
If Pu-238, enter the weight of the isotope Pu-238 to the nearest 1/10 of a gram. For depleted uranium, enter the isotope weight to the nearest kilogram. Make no entry for other source material. For quantities that round to zero enter anasterisk(*).
14
S.
Isotope Limit of Error - Limits of error are only required to be reported by licensees authorized to possess at any one time and location special nuclear material in a quant-ity exceeding one effective kilogram and to use such special nuclear material for activities other than those involved in the operation of a nuclear reactor licensed pursuant to 10 CFR Part 50, those involved in a waste disposal opera-tion, or as sealed sources (10 CFR 70.58(e)).
Complete when the total shipment contains more than 50 grams of U-235, or plutonium, or any combination of these. Enter the limit of error for each isotope entry using the same weight units as in Block 24.R, except where the line entry represents a sealed plutonium-beryllium source (composition code 481); samples which have been determined by other means to contain less than 10 grams U-235, U-233, or plutonium each (composition code 771); and 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% confidence level, pro-pagated by the uncertainties of the weight measurement, the chemical analysis, the isotopic analysis and the sampling method. Limits of error need to be entered only on the copy submitted to the NRC and on the record copy.
Limits of error do not apply for source material.
T.
S_ijnature of Authorized Official and Date Signed - The report is to be signed by an authorized representative of the licensee.
Enter the date signed.
Proprietary information must be included when necessary to pro-vide an adequate response. An application to withhold such information from public disclosure may be made, and wo'11d be disposed of, in accordance with the provisions of 10 CFR 2.790.
If any of this information is of particular sensitivity, a request may be made that such information not be physically transmitted to the IAEA; such a request must refer to, and must conform with 10 CFR 75.12.
- 25. RECEIVER'S DATA -
Each receiver of reportable quantities of special nuclear material or source material must acknowledge receipt of shipments in accordance with the following instructions:
1.
IF THE RECEIVER PLANS TO ACCEPT THE SHIPPER'S MEASUREMENT DATA WITHOUT MAKING INDEPENDENT MEASUREMENTS - ("B" action code)
The receiver shall, within ten (10) days of receipt of the material:
(1) complete block 7 (Receiver), block 20.C, block 25.T of the 741 and state on the form " Based on Shipper's Values"; or 15
l (2) complete Block 7-(Receiver), Block 20.C, and Block 25.A through T of the 741.
Dispatch the form in accordance with Distribution of Copies by Receiver.
Facilities reporting pursuant to 10 CFR 75 must follow option.two (2).
2.
IF THE RECEIVER MAKES INDEPENDENT MEASUREMENTS - ("E" action code)
The receiver shall, within ten (10) days of receipt of the material:
(1) complete block 7 (Receiver), block 20.C, D, and 25.A through T of the 741; showing the quantities of material as measured; and (2) dispatch the form in accordance with Distribution of Copies by Receiver.
If delayed measurements are to be made, they must be completed and reported on a copy of the initial DOE /NRC Form 741 within thirty (30) days after the receipt of each shipment except in the case of receipts of scrap and irradiated material.
3.
IF THE RECEIVER INTENDS TO MAKE INDEPENDENT MEASUREMENTS WITHIN THIRTY (30) DAYS - ("N" action code)
The receiver shall, within ten (10) days of receipt of the material:
(1) complete bloch 7 (Receiver), block 20.C, and block 25.T of the 741; (2) state on the form " Nuclear Material Transfer Receipt";
(3) dispatch the form in accordance with Distribution of Copies by Receiver; and (4) after independent measurements are made, use the instruc-tions for reporting a "B" or "E" action code.
4.
IF THE RECEIVER INTENDS TO MAKE INDEPENDENT MEASUREMENTS FOR SCRAP AND IRRADIATED MATERIAL BEYOND THIRTY (30) DAYS BUT LESS THAN 60 DAYS - ("U" action code)
The receiver shall, within ten (10) days of receipt of the material:
(1) complete block 7 (Receiver), block 20.C, and block 25.T of the 741; (2) state on the form " Nuclear Material Transfer Receipt",
(3) dispatch the form in accordance with Distribution of Copies by Receiver; and (4) after independent measurements are made, use the instructions for reporting a "B" or E" action code.
In the case of a scrap processor receiving several shipments of scrap which are accumulated and processed together, the recovered 16
1 4
4 quantity of material must be prorated to the specific transmittal documents and line entries to maintain the one-to-one corres-pondence between shipper and receiver data.
WHEN REPORTING RECEIVERS DATA -
A.
LINE NUMBER - Enter a line number, beginning with 01 (up to
- 99) for the first line of detailed receiver's data, and increase the line number by one for each additional line of detailed receiver's data entered.
Refer to instructions in Section IV for action code M.
NOTE:
RECEIVER MEASUREMENT DATA MUST BE ENTERED ON A ONE-TO-0NE CORRESPONDENCE WITH THE SHIPPER DATA.
For example, if the shipper lists five line entries (01 through 05) of transfer data, the receiver must report five line entries.
Line number 01 of the receiver's data must correspond to line number 01 of the shipper's data, etc.
If both the shipper and receiver are reporting pursuant to 10 CFR Part 75 or the transfer is an import, the receiver must report the receipt using the same batch name as the shipper.
B.
TYPE OF INVENTORY CHANGE - See item 24.8.
C.
IDENTIFICATION (Batch Name) - See Item 24.C.
D.
NUMBER OF ITEMS - See Item 24.0.
E.
PROJECT NUMBER - See Item 24.E.
F.
11ATERIAL TYPE - See Item 24 F.
G.
COMPOSITION / FACILITY CODE - See Item 24.G.
H.
PRODUCTION CODE - Not applicable.
I.
0WNER CODE - This code describes the material ownership at the time it comes into the receiver's possession.
See 24.I.
J.
COUNTRY CONTROL NUMBER - See instructions for Item 24.J and Appendix III.
K.
KEY MEASUREMENT POINT - See Item 24.K.
L.
MEASUREMENT IDENTIFICATION - See Item 24.L.
M.
GROSS WEIGHT - See Item 24.M.
N.
NET WEIGHT - See Item 24.N.
17 l
t
l 0.
ELEMENT WEIGHT - See Item 24.0.
P.
ELEMENT LIMIT OF ERROR - See Item 24.P.
Q.
WEIGHT % ISOTOPE - See Item 24.Q.
R.
ISOTOPE WEIGHT - See Item 24.R.
S.
ISOTOPE LIMIT OF ERROR - See Item 24.S.
T.
SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED - The report is to be signed by an authorized representative of the licensee.
Enter the date signed.
B.
DISTRIBUTION OF DOE /NRC FORM 741 OR FACSIMILE 1.
SHIPPER Distribute the completed DOE /NRC Form 741 as follows:
a.
Send four (4) copies to the receiver, one of which must be with the shipment.
b.
Mail one (1) copy to:
Forms containing Unclassified and/or Confidential data should be mailed to:
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Dak Ridge, Tennessee 37831 Forms containing Secret data should be mailed to:
Martin Marietta Energy Systems, Inc.
ORGDP/ Records Department P.O. Box 2003 Oak Ridge, Tennessee 37831 c.
Retain one (1) copy for your file.
2.
RECEIVER Distribute the completed DOE /NRC Form 741 as follows:
a.
Mail one (1) copy to:
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Oak Ridge, Tennessee 37831 18
Forms containing Secret data should be mailed to:
Martin Marietta Energy Systems, Inc.
ORGDP/ Records Department P.O. Box 2003 Dak Ridge, Tennessee 37831 b.
Return one (1) copy to shipper.
l c.
Retain one (1) copy for your file.
II
I. PROCEDURE
FOR CONTINUATION PAGE If more lines of data are to be reported than can be accommodated on one pag i, use-Nuclear Material Transaction Report, DOE /NRC Form 741A (continua-tirn page) and follow the basic instructions for shipper, receiver, or onsite activity as appropriate.
PAGE NUMBER - Enter the page number of the continuation page.
TRANSFER SERIES - Enter the same transfer series data entered on
-the first page in Blocks 1 through 4.
IV.
PROCEDURE FOR ONSITE GAINS AND LOSSES ("M" ACTION CODE).
A.
DOE /NRC Form 741 Blocks When action code "M" is used, the DOE /NRC Form 741 should be completed in accordance with the following instructions.
1.
SHIPPER'S RIS - Enter your RIS.
2.
RECEIVER'S RIS - Same as block one.
3.
TRANSACTION NUMBER - See II.3 4.
CORRECTION NUMBER - See II.4 and Section V 5.
PROCESSING CODE - For NRC use only.
6.
RESERVED - For NRC use only.
7.
ACTION CODE - Enter "M" in either the shipper, receiver or both 8.
DATA CODE - For NRC use only.
9.
NAME AND ADDRESS OF SHIPPER - See II.9 10.
NAME AND ADDRESS OF RECEIVER - Enter "SAME" 11.
NUMBER OF DATA LINES - Enter the total number of detail line entries on the form 1
19
12.
NATURE OF TRANSACTION - Leave blank 13.
SHIPPED FOR ACCOUNT OF -
DOE-Owned Material - See II.13 Privately Owned Material - Leave blank 14.
SHIPPED TO ACCOUNT OF -
DOE-Owned Material - See II.14 Privately Owned Material - Leave blank 15.
TRANSFER AUTHORITY -
DOE-Owned Material - See II.15 Privately Owned Material - Leave blank 16.
EXPORT OR IMPORT TRANSFERS - Leave blank 17.
MATERIAL TYPE AND DESCRIPTION - See II.17 18.
TRANSPORTATION PROFILE - Leave blank 19.
PACKAGE IDENTIFICATION - Leave blank 20.
ACTION DATE - Enter the date of the activity in at least one of blocks A. - E.
If more than one block is completed, all dates must be the same.
21.
MISCELLANE0US - See 11.21 22.
TOTAL GROSS WEIGHT - Leave blank 23.
TOTAL VOLUME - Leave blank 24.
SHIPPER'S DATA -
A.
Line Number - Both shipper (block 24) and receiver (block 25) data may be used.
If both blocks are used, number consecutively for the entire report.
See II.24.A B.
Type of Inventory Change - Entry required see II.24.8 C.
Identification (Batch Name) - Entry required if under 10 CFR Part 75, otherwise optional.
See II.24.C D.
Number of Items - Leave blank E.
Project Number - See II.24.E F.
Material Type - See II.24.F G.
Composition / Facility Code - Leave blank for inventory change type code MF.
See II.24.G 20
7 H.
Production-Code - For DOE use only I.
Owner Code - See II.24.I J.
Country Control Number - See II.24.J K.
Key Measurement Point - See II.24.K L.
Measurement Identification - See II.24.L M.
Gross Weight - Entry required only for corrections, see Section V.
N.
Net Weight - Leave blank 0.
Element Weight - See II.24.0 P.
Element Limit of Error - Leave blank Q.
Weight % Isotope - Leave blank for inventory change type code MF except for enriched uranium in which case weight %
isotope is optional.
For inventory change type codes, LN and TN, report the same weight % isotope as the weight %
isotope of the beginning inventory for the period.
See II.24.Q R.
Isotope Weight - See II.24.R S.
Isotope Limit of Error - Leave blank T.
Signature of Authorized Official and Date Signed.
See II.24.T 25.
Receiver's D'ata - See IV above.
B.
DISTRIBUTION OF DOE /NRC FORM 741 OR FACSIMILE Distribute the completed DOE /NRC Form 741 as follows:
1.
Mail one copy to:
Forms containing Unclassified and/or Confidential data should be mailed to:
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Oak Ridge, TN 37831 l
l 21 l
L 1
1
Forms containing Secret data should be mailed to:
Martin Marietta Energy Systems, Inc.
ORGDP/ Records Department P.O. Box 2003 Oak Ridge, TN 37831 2.
Retain one (1) copy for your file.
P i
V.
PROCEDURES FOR CORRECTING DOE /NRC FORM 741 OR FACSIMILE - ("C",
"D,"
or "M" action code)
Adjustments are independent actions which means either the shipper or the receiver may initiate an adjustment to a DOE /NRC Form 741 or Form 741A reporting the original shipment or receipt of material or to any previous adjustment to the original.
Although the other party is obligated to acknowledge that an adjustment was made, they are not obligated to make the same adjustment to their own records.
A.
If there are corrections to be made to blocks 1 through 23 of a pre-viously submitted Form 741, a letter should request that corrections be made to the data base.
The general procedures or procedure for onsite gains and loses, as appropriate, shall be used for providing the new information.
The letter should include the following information:
1.
To identify the 741 being corrected:
Shipper's RIS - block 1 Receiver's RIS - block 2 Transaction number - block 3 Correction number - block 4 Date of shipment - block 20 2.
For each block being corrected:
block number "was" data "should be" data A copy of the letter should be sent to the other party involved in the transaction being corrected.
An example of this letter is provided in Appendix VI.
As an alternative, the appropriate correcting' documents may be completed and distributed.
B.
If correcting blocks 24 or 25, the general procedures or procedure for onsite gains and loses, as appropriate, shall be used for complet-ing the new lines.
The originator of the " corrected copy" shall:
1.
Complete blocks 1 through 16A, 20, ana 21, as appropriate, using the copy of the 741 baing corrected as reference.
22
o 2.
Complete the "did read" line, blocks 24.B through L and N through 5 or 25.B through L and N through S, as appropriate, by duplicating the line being corrected from the 741 being cor-rected in its entirety and indicating the opposite sign (posi-tive or negative) from the original one used in reporting the Number of It4ms (block D), Element Weight (block 0), Elenient Limit of Error (block P), Isotope Weight (block R), and Isotope Limit of Error (block S).
3.
Insert in block 24.M or 25.M of the "did read" line, as appro-priate, a three digit back reference code.
The first digit is 1
the Correction Number (block 4) from the 741 being corrected.
(If the line of data has been previously corrected, the most recent prior correction number should be used.) If the line of data has not been previously corrected a "0" should be used.
The next two digits are the Line Number (block 24.A or 25.A) on the 741 being corrected.
4.
Complete the next line of the 741 adjustment with all informa-tion as it " %ould read" for all the blocks in 24 or 25 except block M.
5.
Insert in block 24.M or 25.M of the "should read" line, as appro-priate, a three digit back reference code that references the corresponding "did read" line.
The first digit is the correction i
number of the document being completed; the next two digits are the line number of the corresponding "did read" line.
Continue this procedure until all lines requiring adjustment have been
" backed out" and resupplied with the correct information.
The "did read" and "should read" for eacn line being adjusted should be paired (i.e., adjacent).
(Note:
One or more changes can be made to each line with an adjust-ing entry.
Also, only incorrect lines should be included in a correc-tion report.)
If adding a line to the original document, the back reference should be "000" (Block M).
If a line previously reported should be split into two or more lines, then one of the "should be" lines shou;d back reference the "did read" line and all others should be considered new additions ("000").
If a line is to be voided, only a "did read" line should be used and pairing is not required.
Examples of an initial report and subsequent correction reports are provided in Appendix VII.
23
C.
-Within ten (10) days the facility receiving the corrected 74) form must either:
1.
. State on the'741 form " Shipper's (or Receiver's) Adjustment."
This will close a transaction but will not affect the acknowl-edging party's values.
Or 2.
State on tne 741 " Shipper's (or Receiver's) Adjustment Accepted."
This will close a transaction and applies the other party's adjustment to the acknowledging party's values.
Or 3.
State on the 741 form " Reporting Own Adjustment" and include adjusting detail information lines.
In addition blocks 7, 20 and 24T or 25T.must be completed.
There is no requirement.for both parties to make the sane quantity adjustments.
However, if both parties do choose to adjust under the same corrected 741, they must both' report the same number of entries and the material type must-agree line-for-line.
D.
Distribution of Corrections to DOE /NRC Form 741 or Facsimile:
Originator should:
1.
Send three (3) copies to the other party in the transaction.
2.
Mail one (1) copy to:
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Dak Ridge,-Tennessee 37831 For Secret data use ORGDP/ Records Department.
4 3.
Retain one (1) copy for your file.
Receives of a correction:
Distribute the completed DOE /NRC. Form 741 as follows:
1.
Mail one (1) copy to:
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Oak Ridge, Tennessee 37831 2.
Return one (1) to the originator.
3.
Retain one (1) copy for your file.
24
t VI.
DOE REPORTING REQUIREMENTS FOR PROPRIETARY INTERESTS OF THE GOVERNMENT DOE Order 5630 prescribes reporting requirements for DOE-owned (lease, loan, contract) materials for the proprietary interests of the Government.
The specific additional requirements pertaining to DOE-owned nuclear material include:
1.
Transfers of enriched lithium, neptunium-237, deuterium, and other nuclear materials of proprietary interest to the Government are to be reported on DOE /NRC Form 741.
2.
Additional distribution of DOE /NRC Form 741 to the shipper's and receiver's designated DOE operations offices is required.
I 25
=.
APPENDIX I LISTING OF IDENTIFICATION CODES FOR U.S. CUSTOMS PORTS Sorted by:
(1) State (2) Port i
26
s a
i t
l t
APPENDIX I LISTING OF IDENTIFICATION CODES i
FOR U.S. CUSTOMS PORTS i
t I
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741
-Unknown Port (Mail) 9999 l
Alcan' AK 3104 l
l Anchorage AK 3126
[
l Fairbanks AK 3111 Juneau AK 3101 l
Ketchikan
.AK 3102 Kodiak AK 3127 t
1 Pelican AK 3124 3
1 I
Petersburg AK 3112 i
[
l Sand Point AK 3125 L
Sitka AK 3115
(
i Skagway AK
'3103 Wrangell AK 3105 Birmingham AL 1904 Mobile AL 1901 Douglas AR 2601-Little Rock-North Little Rock AR 2003 Lukeville.
AR 2602 i
Naco AR 2603 Nogales AR 2604 Phoenix AR 2605 San Luis.
AR 2608 f
Sasabe AR 2606 Nassau-Bahama 5221 Kindly' Field Bermuda 4721 Andrade CA 2502 Calexico CA 2503 Eureka CA 2802 i
r 27
APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 Fresno CA 2803 Los Angeles CA 2704 Los Angeles Int'l Airport CA 2720 Port San Luis CA
?.707 San Diego CA 2501 San Francisco /0akland CA 2809 San Francisco Int'l Airport CA 2801 San Ysidro CA 2504 Tecate CA 2505 Montreal Airport CN 0221 Toronto Airport CN 0921 Vancouver CN 3028 Winnipeg CN 3428 Denver CO 2405 Bridgeport CT 0601 Hartford CT 0602 New Haven CT 0603 New London CT 0604 Washington DC 5401 Wilmington DE 1103 Apalachicola FL 1905 Boca Grande FL 1807 Carrabelle FL 1906 Fernandina Beach FL 1805 Jacksonville FL 1803 Key West FL 5202 Miami FL 5201 Miami Int'l Airport FL 5206 Panama City FL 1907
)
28 i
2 a
a l
i APPENDIX I (continued) l CODE TO BE USED
- PORT OF ENTRY / EXIT STATE ON FORM 741 Pensacola FL 1908 1
Port Canaveral FL 1816
)
Port Everglades FL 5203 Port St. Joseph FL 1909 St. Petersburg FL 1814 Tampa FL 1801' West Palm Beach FL 5204 Atlanta GA 1704 I
Brunswick GA 1701 l
\\
Savannah GA 1703 Hilo HI 3202 j
Honolulu HI 3201 i
Honolulu Int'l Airport HI 3205 Kahului HI 3203
{
j Nawiliwili - Port Allen HI 3204 Des Moines IA 3907 Eastport ID 3302 j
Porthill ID 3308 I
Chicago IL 3901 0' Hare International-Airport IL 3906 I
Peoria IL 3902 Evansville IN 4113 Indianapolis IN 4110 Lawencesburg IN 4114 Wichita KS 4504 Louisville KY 4115 Baton Rouge LA 2004 Lake Charles LA 2105 Morgan' City LA 2001 29
l APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 New Orleans LA 2002 Boston MA 0401 Fall River MA 0407 Gloucester MA 0404 Lawrence MA 0416 Logan Airport MA 0417 New Bedford MA 0405 Plymouth MA 0406 1
Salem MA 0408 Springfield MA 0402 Worcester MA 0403 Annapolis MD 1301 Baltimore MD 1303 Cambridge MD 1302 Bangor ME 0102 Bar Harbor ME 0112 Bath ME 0111 Belfast ME 0132 Bridgewater ME 0127 Calais ME 0115 Eastport ME 0103 Fort Fairfield ME 0107 Fort Kent ME 0110 Houlton ME 0106 Jackman ME 0104 Jonesport ME 0122 Limestone ME 0118 Madawaska ME 0109 Portland ME 0101 30
APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 Rockland ME 0121 Van Buren ME 0108 Vanceboro ME 0105 Detroit MI 3801 Muskegon MI 3815 Port Huron MI 3802 South Haven MI 3822 Saginaw - Bay City MI 3804 Sault St. Marie MI 3803 Baudette MN 3424 Duluth MN 3601 Grand Portage MN 3613 International Falls-Rainer MN 3604 Minneapolis - St. Paul MN 3501 Noyes MN 3402 Pinecreek MN 3425 j
Roseau MN 3426 Warroad MN 3423 j
. Kansas City M0 4501 St. Josepn MO 4502 q
.St. Louis M0 4503 Greenville MS 2011 Gulfport MS 1902 Pascagoula MS 1903 Vicksburg MS 2015 Butte MT 3305 Del Bonita MT 3322 Great Falls MT 3304 Morgan-MT 3319 31 E
APPENDIX I (continued) 4 CODE TO BE USED PORT OF. ENTRY / EXIT STATE ON FORM 741-i 1
f Opheim.
MT 3317 Piegan MT 3316 Raymond-MT 3301 Roosville MT 3318
'Scobey MT 3309 j
Sweetgrass MT 2310
-j Turner MT 3306 i
Whitetail' MT 3312 Whitlash MT 3321 Beaufort-Morehead City NC 1511 Charlotte NC 1512 Durham NC 1503 i
Reidsville NC 1506 Wilmington NC 1501 Winston-Salem NC 1502 Ambrose ND 3410 Antler ND 3413 4
Carbury ND 3421 Dunseith-ND 3422 l,
Fortuna ND 3417
)
'Hannah ND 3408 Hansboro ND
'3415
.Maida-ND 3416 Neche ND 3404 Noonan-ND 3420 Northgate ND 3406 Pembina ND 3401 Portal' ND 3403 Sarles ND 3409 32
. ~.
i I
APPENDIX I (continued) 4 6
i CODE TO BE USED j
PORT OF ENTRY / EXIT STATE ON FORM 741 l
Sherwood ND 3414 St.. John ND 3405 Walhalla ND 3407.
l Westhope ND 3419 Omaha NE 3903 Portsmouth NH 0131
+
Newark NJ 4601 Perth Amboy NJ 4602 I
Albuquerque NM 2407 Columbus NM 2406 i
Las Vegas.
NV 2722 i
Reno NV 2833 Albany NY 1002
(
Alexandria Bay NY 0708 Buffalo-Niagara Falls NY 0901 Cape Vincent NY 0706 Champlain-Rouses Point NY 0712 i
Chateaugay NY 0711 C1ayton NY 0714 Fort Covington NY 0705 J.'F. Kennedy Int'l Airport NY 4701 Massena NY 0704 Morristown NY 0707 New York NY 1001 Ogdensburg NY 0701 Oswego NY 0904
' Rochester NY 0903 Sodus Point NY 0905 Syracuse NY 0906 33
I APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 Trout River NY 0715 Utica NY 0907 Waddington NY 0713 Akron OH 4112 Ashtabula OH 4108 Cincinnati OH 4102 Cleveland OH 4101 Columbus OH 4103 Conneaut OH 4109 Dayton OH 4104 Sandusky OH 4107 Toledo OH 4105 Astoria OR 2901 Coos Bay OR 2903 Newport OR 2902 Portland OR 2904 Oklahoma City OK 5304 Tulsa OK 5305 Chester PA 1102 Erie PA 4106 Harrisburg PA 1109 Philadelphia PA 1101 Pittsburgh PA 1104 Wilkes-Barre /Scranton PA 1106 Aguadilla PR 4901 Fajardo PR 4904 Gualica PR 4905 Humacao PR 4906 Jabos PR 4911 34 l
{.
APPENDIX I (continued)
L j
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 i
Mayaguez PR 4907
-l Ponce.
PR 4908 San Juan PR 4909 San Juan Int'1 Airport.
PR 4913 Newport RI 0501 Providence RI-0502 Charleston SC 1601 Columbia SC 1604 Georgetown SC 1602' Greenville-Spartanburg SC 1603 Chattanooga TN 2008 Knoxville TN 2016 Memphis TN 2006 Nashville TN 2007 Beaumont TX 2104 Amarillo TX 5307
-Brownsville TX 2301 Corpus Christi TX 2205 Dallas - Fort Worth TX 5306 Del Rio TX 2302 Eagle Pass TX 2303' El Paso TX 2402
~
Fabens TX 2404 Freeport TX 2204 Galveston TX 2201 Hidalgo TX 2305 Houston TX 5301 Laredo TX 2304 Lubbock-TX 5308 Orange TX 2103 i
35
APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE ON FORM 741 Port Arthur TX 2101 Port Lavaca/ Port Comfort TX 2208 Presido TX 2403 Progresso TX 2309 Rio Grande City TX 2307 Roma TX 2310 Sabine TX 2102 San Antonio TX 2308 Salt Lake City UT 2832 Alexandria VA 5402 Cape Charles City VA 1406 Newport News VA 1402 u
Norfolk VA 1401 Portsmouth VA 1401 Reedville VA 1407 Richmond - Petersburg VA 1404 Charlotte Amalie VA 5101 Christiansted VA 5104 Coral Bay VI 5103 Cruz Bay VI 5102 Frederiksted VI 5105 St. Croix Airport VI 5207 St. Thomas Airport VI 5208 Alburg VT 0205 Beecher Falls VT 0206 Durlington VT 0207 Derby Line VT 0209 Highgate Springs VT 0210 North Troy VT 0208 36
APPENDIX I (continued)
CODE TO BE USED PORT OF ENTRY / EXIT STATE
'ON FORM 741 Norton VT 0211 Richford VT 0203 St. Albans VT 0201 Aberdeen WA 3003 Anacortes WA 3010 Bellingham WA 3005 Blaine WA 3004 Boundary WA 3015 Danville WA 3012 Everett WA 3006 Ferry WA 3013 Friday Harbor WA 3014 8
Frontier WA 3020 Laurier WA 3016 Longview WA 2905 Lynden WA 3023 Metaline Falls WA 3025 Neah' Bay WA 3027 Nighthawk WA 3011 Olympia WA 3026 Oroville WA 3019 Port Angeles WA 3007 Port Townsend WA 3008 Seattle WA 3001 Seattle-Tacoma Int'l Airport WA 3029 South Bend - Raymond WA 3021 Spokane WA 3022 l
Sumas WA 3009 Tacoma WA 3002 37 N
APPENDIX I (continued)
CODE TO GE USED PORT OF ENTRY / EXIT STATE ON FORM 741 Ashland WI 3602 Green Bay WI 3703 Manitowoc WI 3706 Marinette WI 3702 Milwaukee WI 3701 Racine WI 3708 3
Sheboygan WI 3707 Superior WI 3608 Charleston WV 1409 4
l 38
/
4 s.
APPENDIX II COMPOSITION AND NATURE OF TRANSACTION CODES r.
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39
1 APPENDIX II COMPOSITION AND NATURE OF TRANSACTION CODES 1
1.
Composition Codes (For Additional Codes See NMMSS Report D-25)
CODE CATEGORY (AND DESCRIPTION, IF WARRANTED)
UNENCAPSULATED - except scrap 032 Ua0s 048 U03 (Trioxide Product) 770 Carbides 455 Other Oxides Product - For all oxides not otherwise identified 064 Tetrafluorides (Tetrafluoride Product) 100 UFs Commercial Feed 083 UFs Hexafluoride Product s
UNENCAPSULATED - except scrap (Continued) 773 UFs Heels 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 Scrap - for recovery *+
A00 Unalloyed metal
- American National Standard Institute 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 describing the predominant scrap category.
40
APPENDIX II (Continued)
CODE CATEGORY (AND DESCRIPTION, IF WARRANTED)
B00 Alloyed metal C00 Compounds 000 Combustibles E00 Noncombustibles F00 Solutions G00 Process Residues 375 Irradiate Recyclable Fuel Waste - for disposal:
Waste material shauld be described by an appropriate scrap. category.
ENCAPSULATE 0' 291 Fabricated Fuel Elements
- pins, rods, plates 309 Fuel assemblies (Assembled Items Product) 481 Sealed sources (Fabricated Sources Product)
OTHER 776 Other Products Note:
U/Th and Pu/U 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.
2.
Nature of Transaction CODE DESCRIPTION
- 00E Owned Material -
A Initiates lease / financial responsibility B
Transfers lease / financial responsibility 41 m
APPENDIX II (Continued)
C Transfer of leased material - No change of lease or financial responsibility.
D RC. urn to DOE for credit under DOE lease agreement.
E Sale for DOE F
Pursuant to an enriching service agreement G
Sale to DOE R
Donation for DOE S
Donation to DOE
- Privately Owned Material (Non-D0E) -
L Lease of privately owned material M
Sale of privately owned material N
Transfer only of privately owned material s
P OTHER (explain in Block 21, "Micellaneous")
)
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42
APPENDIX III SUPPLEMENTAL INSTRUCTIONS FOR COMPLETING BLOCKS 24.J AND 25.J 0F DOE /NRC FORM 741 4
43 1
E.
l j
APPENDIX III SUPPLEMENTAL INSTRUCTIONS FOR COMPLETING q
BLOCKS 24.J and 25.J OF DOE /NRC FORM 741 Country Control Number (CCN) i The country control number is structured as an eight (8) character code composed of four (4) sets of two character country codes as follows:
Characters Description (1 and 2) - The country of origin of the source material (3 and 4) - the country providing isotopic separation services I
(5 and 6) - the country in whic! reactor products are produced (7'and 8) - any other country or international organization attaching safeguards conditions (as explained in paragraph d on page 44) to the material in additional to any that may be' attached by a country identified in set one, two, or three above (characters 1 j
through 6).
I If no country code is entered, zeros must be used.
For all foreign origin
{
material, the two character symbol is derived by dropping the "R" at the j
beginning of the standard three letter foreign country RIS designated I
heretofore and using the remaining two letters (e.g., "CA" for Canada, "FR" for France, etc.).
See list of country RIS's in NMMSS Report 0-15.
I For all United States origin material, use the two character symbol "US.~'
l A licensee determines the proper CCN, using either the rumber assigned initially to the material or the initial number plus any applicabla set of two character codes following the instructions as stated below.
The appropriate CCN for each nuclear material contained in the transaction is entered in either blocks 24.J or 25.J, as applicable of the DOE /NRC Form 741 (Nuclear Material Transaction Report).
An explanation of each set of two character codes follows:
a.
The country of origin of the source material (1st and 2nd characters).
The first set of two characters are alpha symbols to identify the country of j
-origin of the source material and is required for all transactions.
NOTE:
The remaining characters (three through eight in sets of two each) are to be used if applicable.
44
APPENDIX III (Continued)
I b.
The country providing the isotopic separation services (3rd and 4th characters).
The second set of two characters are alpha symbols to iden-tify the country that performed the isotopic separation service that orig-inally produced the enriched or depleted uranium in the material involved in the nuclear material transaction.
Some examples are:
(1) Normal uranium mined, converted to concentrates and then to ufo in Canada, and the UFe was sent to the U.S. and enriched with no safe-guards conditions attached by other countries.
The CCN would be CA US 00 00.
(2) Enriched uranium that was a product of normal uranium mined, converted to concentrates and then to UFe in the U.S. and the U-235 was enriched in the U.S. with no safeguards conditions attached by other countries.
The CCN would be US US 00 00.
c.
The country in which reactor products are produced (5th and 6th characters).
The third set of two characters are alpha symbols to identify the country where the production of Plutonium (Pu) or Uranium-233 (U-233) occurred.
(1) Normal uranium mined, converted to concentrates and then to UFs in Canada; ufo sent to U.S. and enriched.
Fuel elements fabricated in U.S. and shipped to Spain for insertion into a reactor.
The irra-diated fuel elements are discharged from the Spanish reactor and sent to the U.S. without any safeguards conditions attached by other 3
i than the countries already identified in sets 1, 2, and 3 of the CCN.
For the produced plutonium the CCN would be CA US SP 00.
(2) Normal uranium mined, converted to concentrates, and then to UFe in the U.S., enriched in the U.S., fuel elements fabricated in the U.S.,
used in a power reactor in the U.S., and irradiated fuel elements discharged from the reactor and sent to a U.S. facility for storage without safeguards conditions attached by other than the countries already identified in sets 1, 2, and 3 of the CCN.
For the produced plutonium, the CCN would be US US US 00.
For the remai.ning enriched or depleted uranium, the CCN would be US US 00 00.
d.
Any other country or international organization attaching safeguards conditions to the material in addition to those that may be attached by a country identified in set one, two, or three above (3.a, 3.b, and 3.c, respectively) (7th and 8th characters).
The fourth set of two characters may be numeric, alpha or alphanumeric symbols.
These last two characters identify any other country (ies) or international organization (s) attaching safeguards conditions, and are unique for each such combination of country (ies) or organization (s).
The word " conditions" means any appli-cable supplier requirements that material be used only for peaceful appli-cations; that it be subject to IAEA safeguards; that the foreign country 45
APPENDIX III (Continued) or countries concerned be informed of material location; or that the mate-rial may not be exported from the U.S., enriched or reprocessed, without the prior consent of such country or countries.
The safeguards conditions attached depend on the terms of agreements for cooperation for supply of the material.
Information as to the conditions stipulated by the indivi-dual countries attached conditions must be known at the time of import license application in order that they may be coded and fed back to the licensee as part of the CCN structure.
These unique combinations repre-sented by the last two characters will be maintained in the NMMSS as part of a CCN reference file.
A two character alpha / numeric code will be assigned to each unique condition or set of conditions as they are defined or identified.
These codes will be maintained within the NMMSS and dis-seminated to prospective users.
Country Control Number Entries in Blocks 24.J and 25.J of DOE /NRC Form 741 The licensee is to use either the "as received" CCN code intact, without any additions, or the "as received" CCN code with any applicable addition of one or more sets of two characters codes incurred while the material was in the possession of the licensee.
The use or application of CCN codes for import material are special cases and are developed and perpetuated as described below.
a.
Imports Each import of nuclear material into the U.S. requires an import license, either specific or general.
As a condition for obtaining a specific license, the importing facility must identify:
the country of origin of the source material; the country which provided any isotopic separation; the country in which~ reactor products were produced (if any); and the country (ies) or organization (s) attaching safeguards conditions, if appli-cable. When material is imported having special safeguards conditions attached, the NRC will provide the proper code (s) to be used in characters 7 and 8 of the CCN.
This will be determined during the licensing process.
In cases of import of source or byproduct material' under a general license the importing facility is required to provide the above listed information upon submission of the DOE /NRC Form 741 which documents the transaction.
At the time the imported nuclear material is received at the facility, a DOE /NRC Form 741 is prepared to document the transfer of the material. All shippers and receivers data are to be entered, including the appropriate country control number (s) which must be entered in blocks 24.J and 25.J for each nuclear material imported.
NOTE:
Only one import license number and/or contract number is to be entered on a DOE /NRC Form 741.
If more than one license number and/or contract number applies to the material received, a separate DOE /NRC Form 741 is prepared to document the transfer of the material imported under each license number and/or con-tract number.
46
APPENDIX III (Continued)
The CCN, assigned to material on its import into the U.S., is used to follow (track) that material throughout the U.S.
Following are only a few of the many possible examples of how to construct the appropriate CCN code to identify material imported into the U.S..
(1) Source material (normal uranium concentrates) imported into the U.S.
from Canada, with no safeguards conditions attached by other countries.
CCN:
CA 00 00 00 (2) Normal uranium mined in Canada, converted to concentrates, then to ufo, shipped to a U.S. enrichment facility and then to a U.S.
fabrication facility, with no conditions attached by other countries.
CCN:
CA US 00 00 (3) Normal uranium was mined in Australia and then converted to concentrates, enriched and fabricated into fuel elements in the United Kingdom.
The elements were included in a fuel assembly and put in power reactors in the United Kingdom; then the spent fuel elements, containing reactor products Pu and/or U-233, are shipped to the U.S.
The material has no safeguards attached.
2 CCN:
AU UK UK 00 (4) The material described in (3) above is subject to international Atomic Energy Agency (IAEA) safeguards at the time it was shipped to a U.S. facility.
The material now has IAEA safeguards conditions attached, the latter identified, for this example, by code "XX."
CCN:
AU UK UK XX b.
Transfers Within the U.S.
Transfers of nuclear material are documented on the DOE /NRC Form 741.
The form must show the CCN in block 24.J or 25.J.
(1) Transfer of Imported Material For the initial transfer of imported material from the importing facility to another U.S. facility, the DOE /NRC Form 741 must show the CCN assigned to the material at the time of import modified as necessary to reflect any change in the material status while possessed by the importing facility.
If material from more than one CCN is being transferred in the shipment, a separate line must be used for the quantity associated with each CCN.
47
APPENDIX III (Continued)
For example:
Canadian source material (normal uranium) already in the U.S. and sub-sequently shipped to a U.S. enrichment facility.
The material has no safeguards conditions attached by other countries.
CCN:
CA 00 00 00 (2) Transfer of Enriched Material From Enrichment Facilities When a U.S. shipping facility has enriched the material and the enriched product is being transferred, the CCN assigned to the product will retain the identity of the country of origin of the source material and any country (ies) or organization (s) attaching safeguards conditions.
In addi-tion, the shipper will enter "US" in the second set of two-character codes of the original CCN to denote that the material was enriched or depleted in the U.S.
(3) Transfer of Material Between U.S. Facilities Other Than The Importing Facility) l If no change in the status of the material (i.e., enrichment or use in a x
reactor) has resulted form the use in the shipping facility, the facility N
will enter in block 24J the CCN obtained from the 00E/NRC Form 741 originally transferring the material into the facility.
NOTE:
The CCN does not change as a result of the conversion or the fabrication operations.
(4) Transfer of Reactor Products If a reactor product resulted at the shipping facility, enter "US" in the third set of two-character codes of the CCN to identify the country producing the reactor product.
The receiving facility involved in all of the above instances must identify in its records system the quantity of each type of material received associated with each CCN.
Reports prepared from the U.S. tracting system inventory files and furnished to each facility holding nuclear material will provide a means of verifying the accuracy of the facility records.
c.
Exports Each export of nuclear material from the U.S. requires an export license.
As a condition for obtaining a license to export nuclear material from the U.S.,
the exporting facility will be asked to identify the country of origin of the material, the country providing any isotopic separation, the 48 a..
APPENDIX III (Continued) country in which any reactor products are produced, and the country (ies) or organization (s) attaching safeguards conditions, if applicable.
Such information will be used by the NRC to determine if the export license can be approved.
In cases of export of source or byproduct material under a general license or license exempt the exporting facility is required to provide the above listed information upon submission of the DOE /NRC Form 741 which documents the transaction.
At the time of export, the exporter must prepare a DOE /NRC Form 741 transfer document entering in block 24J, the CCN which identifies the material being exported.
If material with more than one CCN is involved in the shipment, a separate line must be used for the quantity associated with each CCN.
The CCN must agree with the CCN account holdings (inventory) shown on the exporting facility " book inventory." Examples of exports:
(1) Canadian origin material shipped to Australia after enrichment in the U.S. with no safeguards conditions attached by other countries.
CCN:
CA US 00 00 (2)
U.S. origin material enriched in the U.S. is shipped to Germany for conversion of the UFs to UO2 with no safeguards conditi'ns attached o
by other countries.
CCN:
US US 00 00 (3) Canadian origin material, enriched in the U.S., fabricated into fuel elements for and used in a U.S. power reactor, and the spent fuel elements containing reactor products (Pu and/or U-233), are shipped to Japan with no safeguards conditions attached by other countries.
CCN:
CA US US 00 For Pu and U-233 CCN:
CA US 00 00 For depleted U.
49
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APPENDIX IV l
INSTRUCTIONS FOR COMPLETING DOE /NRC FORM 740M FOR A i
CONCISE NOTE e
s J
50
APPENDIX IV CONCISE NOTE - DOE /NRC FORM 740M These instructions apply to installations which have been notified by letter from the NRC, as provided o
in 10 CFR 675.11, that they have been identified under the US/IAEA Safe-guards Agreement.
Facility Attachments or Transitional Facility Attach-ments for such installations may specify circumstances under which Concise Notes are required to be submitted to the IAEA as attachments to other reports, or o
export - of nuclear material in a quantity of 1 kilogram or more of sourc(
'.erial or 1 gram or more of special nuclear material.
These facilitt6s should use the DOE /NRC Form 740M to explain to the foreign State, where on the DOE /NRC Form 741 the IAEA required data items appear.
In particular the following information is to be provided:
IAEA country code - appears in Block 20. A in parentheses on DOE /NRC Form 741.
(These codes are listed in NMMSS Report 0-15.)
IAEA element (material type) code - appears in Block 24.F on DOE /NRC Form 741.
IAEA material balance area codes - appear in Block 1 in parentheses (U.S. MBAs) and Block 2 in parentheses (Foreign HJA codes) on DOE /
(The Foreign MBA codes are listed in NMMSS Report 0-15.
The Domestic IAEA MBA codes are formed by prefixing your domestic RIS with the letter "U". )
Batch Name - appears in Block 24.C on DOE /NRC Form 741.
Material Weights (Element and Isotope) - appeat in Block 24.0 and 24.R, respectively, on the DCE/NRC Form 741.
o or importers who for any reason cannot use the same batch name as the shipper or if the shipper fails to supply a batch name, the importer should supply his own and attach a concise note to that effect.
In addition, if the shipper fails to supply his IAEA MBA code, the IAEA material type code, or the IAEA country code, a concise note should be prepared stating that the data was not supplied.
In some cases, it may be desirable to provide additional explanatory into ma-tion'v'th reports.
The DOE /NRC Form 740M is the vehicle to be used to submit a cond.se Note.
Form 740M may be attached to a DOE /NRC Form 741, Transaction Report; a DOE /NRC Form 742, Material Balance Report; or a DOE /NRC Form 742C,
%e 51
I APPENDIX IV (Continued)
)
l Physical Inventory Listing; or a stand alone concise note for facilities report-ing under 10 CFR Part 75.
No classified information should be entered on DOE /
These instructions detail the procedures for use of Form 740M:
Instructions for Completing DOE /NRC Form 740M The numbered blocks of the DOE /NRC Form 740M shall be filled in as follows:
1.
Name and address:
Enter the name and address of the reporting _ facility.
2.
Attachment to:
Place a check mark or an X in the appropriate box to indicate whether this explanatory information will be attached to a Form 741/741A, 742, or 742C.
3.
kIS.
Enter the four (4) character 'leporting Identification Symbol (RIS) for the IAEA MBA to which the explanatory information in this report applies.
1 4.
Reporting Period:
Completc this block only if box 2b was checked, indicating that this Concise Note is attached to a DOE /NRC Form 742, Material Balance Report.
Enter the beginning and ending dates of the reporting period as shown on the Form 742.
5 Transaction Data:
Complete this b.u k only if box 2a was checked, indicalmg that this Form 740M is attached to a Form 741/741A, Nutrear Material Transaction Report or if a stand alone concise note is reported.
Copy the requested data from the Form 741/741A.
All entries in this block must be identified to those on the Form 741/741A.
Fill in the blocks as follows:
a.
Shipper's RIS:
Enter the RIS of the shipper.
b.
Receiver's RIS:
Enter the RIS of the receiver.
c.
Transaction No.:
Enter the unique transaction number, d.
Correction No.:
If the Form 741/741A is a correction to a previous report, enter the correction number, e.
Processing Code:
For NRC use only, f.
Action Code If a Form 740M is used with a Form 741, enter the same action code as on Form 741 block 7, otherwise enter action code "M".
g.
Data Code:
For NRC me only.
6.
Reporting Date:
Complete this block if box 2a or 2c was checked.
Copy the date shown on the Form 741/741A or 7420.
52 l
- -. - ~ -
. _. - ~ -.
l l
l APPENDIX IV (Continued) l 7.
License Number (s):
Enter any applicable license number (s).
8.
This block contains the actual explanatory data and the other data necessary to link the explanatory data to the part(s) of the report j
to which they apply.
Complete this block as follows:
a.
Line Number:
Enter consecutive numbers beginning with one (1) for each explanatory reference.
For example, if two sets of explanatory information are entered (e.g, one set for the whole report and one set for specific batch), the first set consisting of two lines and the second set, of three lines, the line numbers, in order, should
. read 1, 2, 1, 2, 3.
b.
Entry
Reference:
If the explanatory information entered on this line of the For:t 740M applies to the entire Form 741/741A, 742, or 742C, enter the words, "WHOLE REPORT."
If the explanation applies to the data on a specific batch on a Form 741/741A or 742C, copy the batch name exactly as it appears on the Form 741/741A or 742C.
If the explanation applies to a specific material balance category on a Form 742, enter the two digit number of the material balance category.
i Additionally, if the explanation applies to material balance cate-gories 11, 30, 42, 43, or 51, enter the RIS shown on that line of the Form 742; if the explanation applies to categories 22 or 71, enter the two-character inventory change type (ICT) as shown on that line of the Form 742.
If Form 740M action code is "M" enter " General."
c..
Text of Concise' Note:
Enter any 43 characters of letters, numbers, or special characters par line.
Up to 99 lines of text may be used for any one explanation 9.
Signature:
The DOE /NRC Form 740M is to be signed by an euthorized representative of the licensee.
j 10.
Title:
Enter the title of the person signing the form.
11.
Date:
Enter the date the form was signed.
i 12.
Distribution of Form 740M Copies of Form 740M shall be attached to and distributed with the DOE /NRC Form 741/741A, 742, or 742C to which the Form 740M applies.
l l
53 i
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1 i
4 1
APPENDIX V INVENTORY CHANGE TYPE CODES i
I i
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)
I 54
-. = -
. ~.
I I
APPENDIX V INVENTORY CHANGE TYPE CODES l
All inventory change type codes on transaction reports consist of two alphabetic characters.
The accounting entry type codes used on MBRs consist of two digits.
In the following pages'the number (s) in parenthesis following the alphabetic code represent the MBR line for 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 Material Balance Reports (MBR), the same corresponding 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 which occur based on the total inventory or in which individual effects to inventories by country control number cannot be deter-mined, should be reported as a loss to all country control number balances by.
applying a one to one ratio by percent of country control number to the amount of inventory affected to the amount of the inventory change.
For example, if
. decay is reported for plutonium within a reactor and the plutonium balance represents several different country control number balances the following calculations would determine the amount of decay to apply to each country con-trol number balance.
1 Element Isotope Amount of inventory for which decay applies 1,202,239 950,947 Calculated decay for the period 998 998 4
Balance by Country Control Number CCN ELEMENT IS0 TOPE
% Ratio to Total Inventory UKUSUS00 200,000 158,196 200,000/1,202,239 =.166 x 100 = 17%
USFRUS00 509,321 402,863 509,321/1,202,239 =.424 x 100 = 42%
CAUSUS00 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 control number balance l
UKUSUS00 998 x 17% = 169.66 rounded to the nearest gram = 170 f
L USFRUS00 998 x 42% = 419.16 rounded to the nearest gram = 419 l
l CAUCUS 00 998 x 41% = 409.18 rounded to the nearest gram = 409 998 55
-... - - _ -... ~. - ~. -. -.
i J
APPENDIX V (Continued) i
-The'above procedure should also be followed using the isotope balances.
i i
TRANS. MBR REQUIREMENT FOR
.i CODE:LINE EXPLANATION BLOCKS 24.B AND 25.B-RF Nuclear material imported into the-United Make no entry (11,30,39) States (Receipt Foreign) i l
RD Domestic receipt of nuclear material from Make no entry
- (11,30,39) another domestic RIS (Receipt Domestic)
RN Domestic receipt of nuclear material from Make no entry (11,30,39) activity not subject to 10 CFR Part 74 NP (21)
Production of fissionable. material in a Entry required by reactor (Pu, U233) licensee DU (76)
Reapplication of safeguards _in nuclear Entry required only material previously exempted therefrom after notification pursuant to Article 38 of the Agreement by NRC after being exempted based on use J
(Licensees subject to 10 CFR 75 only)
)
DQ (76)
Reapplication of safeguards on nuclear Entry required only material previous exempted therefrom after notification pursuant to Article 38 of the' Agreement by NRC after being exempted based on quantity 3
(Licensees) subject to 10 CFR 75 only)
SF Export of nuclear material out of the Make no entry l
(42,51,58) United States i
SD Domestic transfer of nuclear material Make no entry (42,51,58) to another Domestic RIS SN Domestic transfer.of nuclear material Entry required-L
-(42,51,58) from a facility subject to 10 CFR
(
l.
Part 75 to a waste management facility 1
L SN _
Domestic transfer of nuclear material Make no entry j
(42,51,58) from a facility subject to 10 CFR Part 75 to a facility other than a waste management facility LN* (73)
Consumpt. ion of nuclear material due to Entry required by l
its transformation into other element (s) licensee i
or isotope (s) as a result of nuclear reactions (burnup)
- NOTE:
When calculating weight % isotope in the case of burnup or decay, J
report the same weight % isotope for decay and burnup as the weight % isotope of the beginning inventory for the period.
56
APPENDIX V (Continued)
TRANS. MBR REQUIREMENT OR CODE LINE EXPLANATION BLOCKS 24.B AND 25.B I
TN* (72)
Consumption of nuclear material due to its Entry required by transformation into other elements or iso-licensee tope (s) as a result of nuclear reactions (decay) j
'O (74)
Operational loss; i.e., loss of a measured Entry required by or estimated (on the basis of measure-licensee ment) quantity of nuclear material from processing which has been disposed of in i
such a way that it is not suitable for further nuclear use TW (74)
Transfer to the retained waste category Entry required by of measured nuclear material which is licensee deemed to be irrecoverable, to be stored at the MBA and to be deleted from the i
inventory of the MBA FW (51)
Retransfer of material which has been Entry required by stored at the MBA as retained waste to licensee 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 i
retransfer from the MBA EU (76)
Exemption of nuclear material from Entry required only safeguards pursuant to Article 36 of after notification 1
the Agreement (Licensees subject to by NRC 10 CFR Part 75 only)
EQ (76)
Exemption of nuclear material from Entry required only safeguards pursuant to Article 37 of after notification the Agreement (Licensees subject to by NRC 10 CFR Part 75 only)
TU (76)
Termination of safeguards on nuclear Entry required only material pursuant to Articles 13 and 35 after notification of the Agreement (Licensees subject to by NRC 10 CFR Part 75 only)
- NOTE:
When calculating weight % isotope in the case of burnup or decay, report the same weight % isotope for decay and burnup as the weight % isotope of the original inventory for the period.
i 57
_. ~..
. - - -.... - -.... -.. ~ - - -.. -. -.
2 1
APPENDIX:V (Continued) l TRANS.. MBR REQUIREMENT FOR CODE LINE EXPLANATION BLOCKS 24.8 AND 25.B LA (75)
Irretrievable and inadvertent loss of a Entry required by known quantity of nuclear material as the licensee result of an operational accident GA (75)
Nuclear material unexpectedly found to be
' Entry required by present in the MBA, except when detected licensee in the course of a physical inventory j
taking i
i DI (N/A)
The difference between the batch quantity Make no entry reported as received.(always on shipper's data) and the quantity of the same batch
)
as measured by the operator of the i
receiving MBA (Licenses subject to 10 CFR Part 75 only)
)
)
j l
58
APPENDIX V (Continued) l TRANS. MBR REQUIREMENT FOR CODE LINE EXPLANATION BLOCKS 24.B AND 25.B RM (N/A)
The quantity by which the batch mentioned Licensee entry in the entry is diminished in cases of required, if rebatching (Licensees subject to 10 CFR applicable Part 75 only)
RP (N/A)
The quantity of material added from Licensee entry another batch to the batch mentioned in required, if the entry (Licensees subject to 10 CFR applicable Part 75 only)
EN (22,71) Category Change -
ED The quantity of uranium which has changed Entry required NE category as a result of blending, enrich-by licensee ment, depletion or burn-up.
The first ND letter denotes the original, the second DE letter the resulting category (E= enriched, DN N= natural (for " normal"), d= depleted uranium).
The material type codes should bethose for both the original and the resulting material.
The weight data should be provided both for the originat-ing 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 denoting the original mate-rial and the other denoting the resulting material.
MF (77)
Inventory differrence:
this should be Entry required calculated as the difference between the by licensee adjusted ending book inventory and the physical inventory PB (N/A)
Beginning physical inventory:
it should Make entry required 1
be equal to the ending physical inventory of the previous MBR relating to the same material BA (83)
The algebraic sum of the beginning Make entry required physical inventory and of the inventory changes over the period, adjusted to take account of the shipper-receiver differences 59
APPENDIX V (Continued)
TRANS. MBR REQUIREMENT FOR-CODE LINE
. EXPLANATION BLOCKS 24.B AND 25.B PE (N/A)
The sum of all. measured and derived batch Make entry required quantities of nuclear material on hand at the date of the physical inventory taking j
RAXX (N/A) Applicable to licensees subject to the Entry by licensee 10 CFR Part 75 only.the quantity that required only if has to be added to the rounded sum to applicable make it equal to the sum of the rounded terms.
A rounding adjustmer.t is made to an entry in the MBR-on which the IAEA
^
has been. informed differently through ICRs and PILs, in order to bring the i
MBR entry into agreement with the corre-sponding figures established on the basis of ICRs and PIls.
In the case of the ending book inventory and of the
-i MUF, the following formulae should be i
used respectively.
RABA = PB + IC
- DI - BA and MBR RAMF + BA - PE - MF where IC represented the sum of.the consolidN0d 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.
I No rounding adjustment is needed for the beginning physical inventory.
4 The rounding adjustment should be coded j
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.
1 l
)
-l 60
4 i
I APPENDIX V (Continued) 4 i
TRANS. MBR REQUIREMENT FOR
.)
CODE LINE EXPLANATION-BLOCKS 24.8 AND 25.B j
i l
34 (30)
Receipts - Miscellaneous.
Enter quant-
-Licensee ities of material = received in two party entry required transactions where 'only receiver's data i
are reported or receipts of quantities l
of material falling below the reporting l
level and now cumulatively total 1 gram j
or more for SNM or 1 kilogram or more for source material.
Examples include i
receipts of material (not reported else-i where) from facilities that have not i
been assigned a reporting identification i
symbol, and receipts from licensees that are not required to document or report i'
transactions, i
54 (51)
Shipments - Miscellaneous.
Enter Licensee entry ~
quantities of material shipped in~
required j
two party transactions where only shipper's data are reported or ship-ments of quantities of material fall-ing below the reporting level and now cumulatively total 1 gram or more of SNM or 1 kilogram or more for source material.
Examples include 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.
D' 61
d l
i I
i l
l i
APPENDIX VI SAMPLE LETTER TO CORRECT HEADER INFORMATION (Blocks 1 through 23) i
)
J l
t I
l' 62
Sample Letter to Correct Header Data (Block 1 through 23)
Martin Marietta Energy Systems, Inc.
ORGDP Site Nuclear Material Control - Mail Stop 19 P.O. Box 2003 Dak Ridge, TM 37831
Dear Sirs:
Please make corrections as indicated below to the following transactions:
1.
XXX to YYY Transaction #0012 Correction #0 2/12/84 block number 13B was "XSNM-0000" should be "XSNM-1111" 2.
XXX to ABC Transaction #0015 Correction #0 2/15/84 block number 2 was "ABC" should be "ACB" Sincerely, Licensee XXX 63
n i
APPENDIX VII Examples of Documents Correcting Shipper and Receiver Data (Blocks 24 and 25) i i
I 64
2 f~
' EXAMPLE 1 - INITIAL REPORT l
On May:16, 1982 shipper "XXX" transferred to receiver "YYY" fabricated fuel elements containing:
i Line Element
' Isotope 1
natural uranium 2 kilograms 2
1.7080% enriched uranium' 5,429 grams 93.00 gms 3-2.0110% enriched uranium 8,220 grams 65.00 gms l
4-2.2180% enriched uranium 5,469 grams 21.00 gms On May 30, 1982 receiver "YYY" acknowledged receipt of the shipment and accepts shipper "XXX" weights without further measurement.
j These transactions were reported on XXX/YYY/2 (Example 1).
l EXAMPLE 2 - CORRECTION 1 On July 30, 1982, the shipper corrects the element weights for lines 1 and 3 to reflect adjusted element weights of 3 and 9220 respectively.
This correction is reported on XXX/YYY/2/1 (Example 2).
EXAMPLE 3 - CORRECTION 2 On November 15, 1982-shipper reports an adjustment to the country control number entry on detail line 04 of correction 1 report (line 3 of the original report),
i l
This correction is reported on XXX/YYY/2/2 (Example 3).
NOTE:
The line of data was adjusted in the correction 1 report.
Therefore, for the back reference in Block 25M, the most recent prior correction number is "1" with line number "04".
EXAMPLE 4 - CORRECTION 3 On December 31, 1982 receiver reports an adjustment to the weight percent isotope on line 2 of the initial report.
This. correction is_ reported on XXX/YYY/2/3 (Example 4).
NOTE:
No other corrections by the receiver have been made to the initial-report.
Therefore, for the back reference in block 24M, a "0" is used to reference the correction number from the 741 being corrected, 4
65 w
+w y
a
+w w
o EXAMPLE 5 - INITIAL REPORT ACTION CODE M On September 30, 1987 facility XXX reported decay, production and inventory difference.
These inventory changes were reported on XXX/XXX/1 (Example 5).
EXAMPLE 1 - CORRECTION 1 TO ACTION CODE M On March 31, 1988 facility XXX corrects the country control number and, of
{
element and isotope weights on line 3 and 4.
In addition, the element and isotope weights on line 6 were corrected and a new line was added.
l l
1 I
i 66 L.
~ _.
"'"*C**'
EXAMPLE 1: INITIAL REPORT w es ome 112 411 Pro.ous edfons see obsosoie U S DEPARTMENT OF ENERGY AND U S NtX:L(AR REGIAATORY COsamSSION gapsg NUCLEAR MATERIAL TRANSACTION REPORT M, *' ""
"7,""
M'jjyRC' &..
e-
==
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- A_ lB XXX YYY Z
=
.=
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File Nuclear Facility Nuc. Inc.
Anywhere, US 12345 Somewhere US 54321 SAME SAME n
(100)S55-5555 (200)S55-5050
... -. - -.. -. ~
.--~
- l #-
Natural uranium-Fabricated fuel elements U-235,
' " ~ ~ " -
05 16 '82 20% - Fabricated fuel elements unirradiated 05 23 82 T.~ "
~- -
x X
==
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0 Fab Fuel Ele 7
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5 1
RECEIVER'$
I SENATURE OF AUTHOf4 ZED OFFtOAL AND Datt SIGNeO
- PPER'S DA Y GNATURE OF AUTHOm2ED OFFIDAL AND DATE SGNED m
- - - - -e.*'=~~~.aw 05/18/82 N
nh64) h_Ca"* - * -
hk
[2 05/30/82
.s V
3 eny BASED OB SHIPPER' s VALUES j
0 t
- t i
d i
I u sc.swo. ioo. ac os as.e n a usini re mausiv ac.n=re=o.at orrewse vouane a mmuuv en.se svaremeNion mennese= arna to a= owaameur on aoance or Yua u stains as to awe amarrea =v== ors c j
t I
i
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EXAMPLE 2: CORRECTION 1 (shipper adjusting lines 01 and 03 of the initial transaction) g, 00E/ net FORu yet U S. OEPAR1 AMENT OF ENERGY AND U S NUCLfAR REGULATORY CnemmSSION gg ggggg t12419 % set.oes are sesowe
- 'f*J' W; **',@,'j,CR,,,
NUCLEAR MATERIAL TRANSACTION REPORT a
m.
rs ne m L nrotsu m.not
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e
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t YYY r
4 l - - - --
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g...
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Nuclear Facility Nuc, Inc.
Anywhere, US 12345 Somewhere, US 54321 Sa:ne Same i
(100)555-5555
- - (200)S55-5050
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US00000(
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USOOOOOL 101 000 3
3 J3 Fab Fuel Ele 5
20 291 3
USUS0000 003 000
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-4 2.01Il
-65
-1 e D4 Fab Fuel Ele 7
20 291 J
USUS000t 101 000 9220 4
2_01 H 65 1
5 i
E 5
L T.ssrseATURE OF AUTHUptfEDOFFIChAL ANDOATE SIGfEED
{
1gj iPPER1 DA GNATU84E OF AUTHORIZED OFFOAL ANO DATE 9GNED g g g 25.ftECEfvER10ATA
$44
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07/30/82 YYY a- ~ ~-
r
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m.~_......,.._,,T.m e....e-_.....A.T.,
i.
HEPRESENT AYtDN TO Assv DE*.RTh8ENT OR AGENCV OF THE useTED si ARES AS TO Afev teATTEslsurTeam ITS JIAWIWICYuuse l
I i
l
e EXAMPLE 3: CORRECTION 2 (shipper adjusting line 04 of correction 1)
,mm mu ru nun u s Dres.RTueNT eF tNerav ANo u st NectexR Recutaroav co u ssiON
.Wi i
NUCLEAR MATERIAL TRANSACTION REPORT M,
- 0'**
7,^Y=I N.'*. W.m.c'A ",,,
E-u n ua - t.
ww
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2
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l * ** * ~ *
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Anywhere, US 12345 Somewhere, US 54321 Same Same e -.
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CAUS0000 201 000 9220 4
2.0110 65 1
4 O
e 5
k 5
n 11 1 NATURE OF AUTHORIZED OrFICIAL AND OATE SIGNED ggW
- 25. RECEfVER'S DAT A Y. SsGNAIURE OF AUTHORtIED OF Fur.,lAL AND DATE SIGNED 4 4 A (A. SH!PPER$ DAThh f(. ~
m----, +,--.- -* ////f/G 2 TTT
<s
=a.= * - -e *w ceaa'=.a +
6
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a le U R. becistaN 5uut. At OF # sNt h, to SI Af 14th. MAntS li A E 94matNAL Of f ENSE IO MAME A t%tt.LPUL.L V 9' ALSE S14fEMENI OR REP 64ESENTATCfs TO ANY DEPARTh tt es'OR AGENCY OF YME UNETED TYATES AS TO ANY RfAflf R WITHEN ff S JUfkSDeC1Kwe ENT
EXAMPLE 4: CORRECTION 3 (receiver adjusting line 02 of the initial report) g one, 00F,1 HIC FORM 741 g nosyg US DEPARTMENT OF ENERGY AND U $ NUCLEAR REGULATORY COedWt$$10N
^
n24ti Ae.evs eevens se oesosee
"'"o^'o"' 0^'" C L C'*". 70 NUCLEAR MATERIAL TRANSACTION REPORT 3twotito e
a m er AUTHOR.il.l.D.BV 10. CF R 30, 40. 50 rs. isa.
t s> rea mae. mi 4
XXX YYY 2
1 l -.
l.-
l lW lD YYY l*~~""*""*'."..'N_.
" * * * * ' ~ " " "
g..-
SUB-000 l' ""
- SUB-001 7
' ' " * " " ~ * * " ~
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File Nuclear Facility Nuc, Inc.
Anywhere US 12345 Somewhere, US 54321 SAME SAME t.r.pu*e.
g e>gg.9
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=
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- c.t-12 31 82
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=.
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- 24. SMtPPEWS DATA T SIGNATURE OF AUTHORRIED OFFICIAL AND DATE saGNED g gr
- 5. MECf WER' D A T 5;GNATURE OF AUTHOft2ED offer,.lAL ANO DATE 58GNED JJ mM h4a 12/31/82
$44
<s
-a.N = _
01 Fab Fuel Ele
-7 70 741
_f istisonnn
' n~n ?
nnn
~5.479
-t I 70Rn o't 1
02 Fab Fuel Ele 7
20 291 J JSUS0000 101 000 9.479 1
i 7iRn 4 't t
=
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E Id u h o. 5&L !<>f.s p,.Et'. AL
'sp supet J, ipes ay sv al 74
_ OF*tN5410t* Ant apuhate F ALSE 5tattas>Ns OR Af PRESENTATION TO ANT OFPARYtetNf OR AGE.1h WAmt$11 AL---sCV OF f>E UNITED STATES AS TO ANy teATTER mtMoM fYS hie 00s m
EXAMPLE 5:
INITIAL REPORT (Action Code M) e one
.,,,c,,,,,,
a12Sh Pree.on,s eer ons are absoe**
U $ DEPARTufmf 08 ENERGY AND U $ NUCLfAR REGULATORY COuwS$80N SEB RDe4 "j,f,704WQ Cf/' M.,
NUCLEAR MATERIAL TRANSACTION REPORT
^a;ll".**' * *"*
^
E.emos F 31 SB FS.150. Psder La.o SUO1. 91438. 9599
,.m..
XXX XXX t
l
.e.
aM l.a
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w.m enes
)..-- SUB-000 I""
SUB-000
" * * *' *' * "' 0 6 l * - - -- a-XXX
- ~ ~'""*"*
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- (100)555-5555 l *~
~
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Word Description
-. ' ' " * " " ~
09 30 87 i
Example 5
'[
m I
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T.*.".-*
x i
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g "2
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7
.?
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?R_?s 17n 01 TN Decav 50 109
.i mnisfignc i
< 02 TN Der nv 50 309
.I ISFRUSOO 419 28.25 419 3 03 TN Decav 50 309
.I 'AliSIISOO 409 28.25 409
~
6 5
3 a a a
- 24. SHIPPER 4 DATA Y ssGNATURE OF AUTHORIZED OFFICIAL ANO DATE S8GNED Wr g g RECEIVER $yAT A I SKiNATURE OF AUTMoeultD OFf 8CAAL AND DATE SIGNED j
JYJ gg (Qgs 09/30/87 i
a~%
[
04 NP Production so 104 1
nq ntienn 16_000 7A_7s 77 nnn 05 NP Production 50 309 J
USUSUS00 70,000 28.25 63.000 l
- 06 MF Inventory Diff 20 J USUS0000
-10 10 O
n b
+
a na
=
t N
r
- t. A O
- JU.st l').tweb 6d $1 AI 749 h. Ant $ 1T A t ^
_ OHE9tSE 70asaaLE 4 WitLFtAtv e ALSE $1 AttestMi.JR te w bb. Mo ujse :(E.t*4 TO A88V DEPARTRAkht OR AGENCY OF THE UNITED SYaTES As TO Ahv enArYERinnteese sYs JuRLSDICTIO.e RE P8tE SENT AT.
7 b
Y
EXAMPLE 6: CORRECTION 1 (Action Code M)
ODE /WRC 70Ru 741
% One st2an Pro ous see.on s ao cosearre U S. OEPARYMENT OF EhERGV AND U $ NUCLf AR REGULATORY COMMdSSION gagnesyg* * " "
r,*,a,gg; n.',;.gyickh.
3%,,',
NUCLEAR MATERIAL TRANSACTION REPORT mm-t.. om m
. _ _ _. ~
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- - - -.. _. ~ -
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M XXX XXX 1
1 l
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SUB-000 l*"
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(100)555-5555
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t 01 TN Decay SC 305 J CAUSUSOC 003
-400-P 28.25
-409 h D2 TN Decay 5t 30%
J USUSUSOt 101 424 28.25 424 3*
r.
5 1
3 i
T ssGa ATURE OF AUTHOfu2ED OFFICIAL AND DATE SIGNED l ggg RECgVEWS TA r $sGNATURE OF AUTHORIZED OFFICl*L AND DATE SaGNED Aji
- 24. SHIPPEWS DATA s
a-=_
e
<---n
- JJJ qug La. - = -
03/31/38 444 03 NP Production 50 309 J
USFRUS00 004
-36.000 28.25
-22.000 04 NP Production 50 309 J
USUSUS00 103 29.000 28.25 18.000
- i 05 MF Inventory Diff 20 J USUS0000 006
+10
-10 0
06 MF Inveatory Diff 20 J USUS0000 105
-09 09
$ 07 NP Production 50 309 J
USFRUS00 000 7.000 28.25 4.000 r
E n
C te u ic. httleuse SUDt Ati ut JU**f21 #1888 62 51 AI 741s enAnE5 st A LAsheeseAL OFFEse5E fo e.AaE A sif*Ltf utt
- P AtsE st Attestost os.
pef'5tESkNTATIOse TO Aesv DEPAR*MEpsi On aGEasCY OF T*aE UMTED ST ATE 5 AS TO Asev heart 2 a iMitaN ITS JURd5DsCTsuse
.