Form GC-859 Nuclear Fuel Data Form

GC-859
Revised (12/2012)
Average Burden 67.5 Hours

Energy Information Administration

U.S. DEPARTMENT OF ENERGY

Proposed Form
OMB NO. 1901-0287
Expiration Date: XX/XX/XXXX

NUCLEAR FUEL DATA SURVEY
FORM GC-859
Legislative Authority:

Data on this mandatory form are collected under authority of the Federal Energy
Administration Act of 1974 (15 USC Schedule 761 et seq.), and the Nuclear Waste
Policy Act of 1982, as amended (42 USC 10101 et seq.). Failure to file after
receiving Energy Information Administration (EIA) notification may result in criminal
fines, civil penalties and other sanctions as provided by the law. Data being collected
on this form are not considered to be confidential.
Title 18 U.S.C. 1001 makes it a criminal offense for any person knowingly and willingly to
make to any Agency or Department of the United States any false, fictitious, or
fraudulent statements as to any matter within its jurisdiction.

Public Reporting Burden:

The public reporting burden for this collection of information is estimated to average
67.5 hours per response. The estimate by respondent category is 80 hours per
response for operating nuclear reactors, 40 hours per response for permanently
shutdown nuclear reactors, and 20 hours per response for storage facilities and
research/test reactors. The estimate includes the time for reviewing instructions,
searching existing data sources, gathering and maintaining the data needed, and
completing and reviewing the collection of information. Send comments regarding
this burden estimate or any other aspect of this collection of information, including
suggestions for reducing this burden, to the Energy Information Administration,
Office of Survey Development and Statistical Integration, EI-21, 1000 Independence
Avenue, S.W., Washington, DC 20585, and to the Office of Information and
Regulatory Affairs, Office of Management and Budget, 735 17th Street, N.W.,
Washington, DC 20503.

Form Due Date:

This form shall be submitted by September 15, 2013. Data on the form should reflect
the spent fuel status as of June 30, 2013.

EIA Contact:

Refer all questions to: Marta Gospodarczyk at (202) 586-0527 or Jack Thorpe at
(443) 542-5804 and return completed forms to:
Energy Information Administration
Office of Electricity, Coal, Nuclear, and Renewables Analysis
U.S. Department of Energy
Attn: Marta Gospodarczyk, EI-34
1000 Independence Ave. SW
Washington, DC 20585

RESPONDENT IDENTIFICATION
Site Operator Name:
REPORT PERIOD
Begin Report Period: January 1, 2003
End Report Period: June 30, 2013

If this is a resubmission, insert X in the block

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE A: SITE OPERATOR DATA
A.1

Site Operator Name/Identifier

A.1.1

Site Operator Name:

A.1.2

List all reactors being covered by this report.
See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”

Reactor Identifier

A.1.3

Reactor Name

List all spent fuel storage facilities being covered by this report.
See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”

Storage Facility Identifier

A.2

Storage Facility Name

Site Operator Point of Contact

Provide a site operator point of contact for verification of information provided on this form.
Name:
Title:
Mailing Address:

City:

State:

Telephone Number:

Fax Number:

Zip Code:

Email:

A.3

Authorized Signature/Certification

I certify as a cognizant individual that the historical information contained herein and in any associated
electronic media supplied and other materials appended hereto are true and accurate to the best of my
knowledge. (NOTE: Corporate Officer signature is not required, but the signatory must be appropriately
authorized.)
Name:
Title:
Signature:
Date:
Provide in Schedule G at the end of this data collection form any comments you have concerning
Site Operator Data. Label your comments by the Schedule and Item Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE B: REACTOR DATA
Complete a Schedule B for each reactor, including operating and shutdown reactors.

B.1

Reactor Point of Contact
Provide a reactor point of contact for verification of information provided on this form.
If the person is also the site operator point of contact, insert X in the block.

Name:
Title:
Mailing Address:

City:

State:

Telephone Number:

Fax Number:

Zip Code:

Email:

B.2

Reactor License Data
Complete a Schedule B.2 for each reactor, including operating and shutdown reactors.

B.2.1

Reactor Identifier
__________ (See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”)

B.2.2

NRC License Expiration Date (MMDDYYYY): ___ ___ _______

B.2.3

NRC License Type:

Provide the expiration date of the reactor’s NRC operating license as of the end of the reporting
period for this data submission. If the reactor is permanently shutdown, provide the expiration
date of the NRC possession only license.

B.2.4

Reactor Type:

NUCLEAR FUEL DATA SURVEY
FORM GC-859
B.3

Cycle Data

Provide the following data for all operating cycles.
The first cycle of a reactor's operations is designated 01 and successive cycles are numbered
consecutively. Operating cycles covered by this report should continue the sequential cycle numbering
listed in the previous reporting period, which are provided.
If the reactor has experienced an outage in the midst of a cycle where fuel assemblies were temporarily
or permanently discharged, indicate by providing subcycle numbers and start up and shutdown dates as
if the subcycle were a complete cycle. Designate subcycles as a, b, c, etc. (example 16a, 16b, 16c). If
no fuel assemblies were discharged, simply report the cycle number, start up and shutdown dates
without regard to subcycles.

Cycle Number

Start Up Date
(MMDDYYYY)

Shutdown Date
(MMDDYYYY)

Provide in Schedule G at the end of this data collection form any comments you have concerning
Reactor Data. Label your comments by the Schedule and Item Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE C: FUEL DATA
C.1

Data On Permanently Discharged Fuel

The Form GC-859 survey collects data on an assembly-specific basis to ensure that all owners have
been properly allocated spent nuclear fuel acceptance capacity in the Acceptance Priority Ranking &
Annual Capacity Report (APR/ACR). For this reason, respondents are requested to report all
permanently discharged fuel - both spent nuclear fuel reported on previously submitted Form RW-859
surveys and spent nuclear fuel discharged during the current reporting period. Data reported on
previous versions of the survey (formerly the Form RW-859) will be provided. Respondents are
requested to update previously submitted data with appropriate changes. The assembly specific data to
be reported are as follows:
Assembly
Identifier

This should be either the site operator-assigned unique identifier or the
American National Standards Institute (ANSI) Identifier. Note that non-intact
assemblies may have more than one entry in this table with each piece of
the assembly in a physically separate location being reported on a separate
line.

Initial Heavy
Metal Content

The initial contents of the fuel assembly in kilograms of uranium and in
kilograms of plutonium (should be reported to the nearest thousandth of a
kilogram).

Initial
Enrichment

The average enrichment of the assembly (should be reported to the nearest
hundredth of a percent).

Discharge
Burnup

Assembly burnups (should be reported in megawatt days thermal per metric
ton of (initially loaded) uranium (MWDt/MTU)).

Last Cycle
Number

Report cycle number for the assembly’s final cycle of irradiation.

Fuel Vendor

Report the fuel vendor at the time the fuel was purchased.

Lattice Type

Specify the fuel rod array.

Assembly Status

Use the appropriate code from the following table. Note that only
permanently discharged assemblies are to be reported in this Schedule.

Status
Code

Description

Standard intact assembly - blank or no code - This is the default.
Non-standard intact assembly
Failed assembly with cladding damage or mechanical damage (not
F
canistered)
C
Canistered assembly
R
Canistered fuel rods
P
Canistered fuel debris (pieces)
B
Fuel in a basket
Other - provide description of other conditions in Schedule G at the end of
this data collection form; for example, to identify an assembly type that is not
O
included under one of the Status Codes listed above; or to describe
characteristics which require special handling, etc.
Note: Standard intact assembly, non-standard intact assembly, and failed assembly as defined in
10CFR 961.11 Appendix E.
N

NUCLEAR FUEL DATA SURVEY
FORM GC-859
Storage Location

Select the appropriate pool storage site or dry storage site identifier from
Appendix C. If all assemblies are stored in a common pool specific to the
reactor, these identifiers need not be included.

If possible, submit assembly-specific data in either database or spreadsheet format. You may use any
readily-available database or spreadsheet. These data must include the above elements at the required
degrees of precision. One exception is that cycle shutdown date may be substituted for cycle number.
Note that these are minimum degrees of precision and more precise data are preferred.
Your completed assembly-specific data (as an electronic file) in database or in a spreadsheet format
should be transmitted by electronic mail, compact disk, DVD, or flash drive, to DOE at the addresses
specified in the instructions and on the cover page of this form. In lieu of submitting assembly-specific
data in database or spreadsheet format, you may fill in the required data in Schedule C.1 of this form.
Update (only changes or corrections are needed) all previously submitted data (which you have been
provided) and enter the additional data on assemblies discharged since the last Form RW-859 Survey
was collected.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.1.1
Assembly
Identifier

Data On Permanently Discharged Fuel 1

Initial Heavy
Metal
2
Content
Initial
kgU

Initial
kgPu

Initial Enrichment
3
(Weight %)
U235

Pu239

Pu241

Discharge
Burnup
4
(MWDt/MTU)

Last
Cycle
5
Number

Assembly Status Code(s)
Fuel Vendor

6

8

Storage
10
Location

Lattice
7
Type
9

N

F

C

R

P

B

O

      

      
      
1

Report permanently discharged fuel only. If you are not certain if an assembly will be reinserted, prioritization rules suggest that it is in the site operator’s interest to report it as permanently discharged
and modify the total burnup, last cycle number, and last cycle shutdown date later if the assembly is subsequently reinserted.

2

In kilograms to the nearest thousandth of a kilogram, consistent with data reported on the Nuclear Regulatory Commission Form 741, “Nuclear Material Transaction Report.”

3

To the nearest hundredth of a percent.

4

In megawatt days thermal per metric ton of uranium.

5

Report last cycle number.

6

Fuel Vendor – Select the vendor name at time of purchase.

7

Lattice Type – Select the fuel rod array.

8

See the Assembly Status Code table on the previous page or refer to Appendix B, “Assembly Status Codes”. Note: Insert ALL codes that apply to this assembly – multiple codes permitted. Since only
permanently discharged assemblies are to be reported in this Schedule, historical status codes (D = Discharged, T = Temporarily Discharged, and I = Incore) should not be included.

9

Non-standard Fuel – If all fuel from this reactor is considered non-standard, you may check the box in Schedule C.3.3.2 “Special Fuel Form – Non-standard Assemblies” instead of checking all boxes in
this column.
See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.” If all assemblies discharged from this reactor are stored in this reactor’s pool, the storage location column need not be
filled in.

10

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.1.2

Fuel Cycle History
For each assembly listed in Table C.1.1, identify the cycles during which the assembly was irradiated in the reactor core. Historical data reported
on previous Form RW-859 surveys are being provided. Note that you may submit your fuel cycle history data in any readily-available format.
Include data for all discharged assemblies and for assemblies that have been inserted but not yet discharged.

Reactor Cycle Number (from Table B.3)
Assembly
Identifier
01

02

03

04

05

06

07

08

09

10

11

12

13

14

15



























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
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








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










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





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




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





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
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


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

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…

…
…
…
…
…
…
…
…
…
…
…

39

40



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




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






NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.2

Projected Assembly Discharges

Projections of discharged assemblies shall be reported on a group basis, where each assembly in the
group has the following common characteristics:


Assembly Type (same Vendor and Lattice)



Reactor/Cycle History



Initial Uranium Content (within 3 kg for BWR, 5 kg for PWR)



Initial Enrichment (within nearest tenth of a percent)



Estimated Final Burnup (within 5% of the group average MWDt/MTU). Round the estimated final
burnup to the nearest thousand MWDt/MTU.

Projections of discharged assemblies must be reported for at least the next five cycles.

Cycle
Number

Planned
Cycle
Shutdown
Date
(MMYYYY)

Group
Identifier

Projected
Number of
Assemblies
Discharged in
the Group

Initial Heavy
Metal Content
Initial
kgU

Initial
kgPu

Average
Initial Enrichment
(Weight %)
U-235

Pu-239

Pu-241

Projected
Discharge
Burnup per
Assembly
(MWDt/MTU)

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.3

Special Fuel Forms
Report in this section, data on the following. Check all that apply.




C.3.1

Single Assembly Canisters (Complete Schedule C.3.1) 
Uncanistered Fuel Rods/Pieces (Complete Schedule C.3.2) 
Consolidated/Reconstituted/Reconstructed Assemblies;  Non‐standard 
Assemblies, & Failed Assemblies (Complete Schedule C.3.3)

Special Fuel Form – Canisters

A canister is defined as any single assembly canister designed to confine contents that may be
delivered to a Federal facility. Within this schedule, canistered material may include damaged
assemblies, reconstituted assemblies, intact fuel rods that have been removed from an assembly,
and miscellaneous fuel. Empty canisters should not be reported.
Does your facility have single assembly canisters?
______ Yes. Complete the remainder of Schedule C.3.1
______ No. Skip to Schedule C.3.2
For all single assembly canisters, provide a detailed description.
C.3.1.1
Canister
Identifier

1

Single Assembly Canisters Description
Canister
Shape
C

R



























Canister Dimensions
(to the nearest 0.1 inch)
Length

Diameter/ Width

C = cylindrical

Depth

R = rectangular

See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”

Loaded Weight
(to nearest lb)

Storage
1
Identifier

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.3.1.2

Qualitative Canister Contents

For each canister identified in Schedule C.3.1.1, provide a qualitative description of the contents
and identify, if applicable, the method used to close the canister. Also indicate whether the
canister may be handled as a standard fuel assembly.

Canister
Identifier

Description of Contents
(check all that apply)

Canister Closure

Is Canister
Handled As A
Standard Fuel
Assembly?

B

Yes

W

NS

No

__
__
__
__

Intact failed fuel assembly
Intact reconstituted/reconstructed fuel assembly
Intact fuel rods
Fuel debris (rod pieces, fuel pellets, etc.).

    

__
__
__
__

Intact failed fuel assembly
Intact reconstituted/reconstructed fuel assembly
Intact fuel rods
Fuel debris (rod pieces, fuel pellets, etc.).

    

__
__
__
__

Intact failed fuel assembly
Intact reconstituted/reconstructed fuel assembly
Intact fuel rods
Fuel debris (rod pieces, fuel pellets, etc.).

    

__
__
__
__

Intact failed fuel assembly
Intact reconstituted/reconstructed fuel assembly
Intact fuel rods
Fuel debris (rod pieces, fuel pellets, etc.).

    

B = bolted
C.3.1.3

W = welded

NS = not sealed

Detailed Canister Contents

For each canister identified in Schedule C.3.1.1, provide a detailed description of the contents.
Canister Identifier

Source Assembly
Identifier

Number of Fuel Rod
Equivalents from
Assembly

Initial Heavy Metal Content
Initial kgU

Initial kgPu

Discharge Burnup
(MWDt/MTU)

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.3.2

Special Fuel Form – Uncanistered Fuel Rods/Pieces
Does your facility have uncanistered fuel? Include all materials that were not listed in
Schedule C.3.1 (i.e., materials stored in baskets, materials to be repackaged, etc.).
______ Yes. Complete the remainder of Schedule C.3.2
______ No. Skip to Schedule C.3.3
For all uncanistered fuel rods and fuel pieces, provide a detailed description.
Number of
Uncanistered Fuel
Rods or Pieces
from Assembly

Source
Assembly Identifier

Initial Heavy Metal Content
Initial kgU

Initial kgPu

Discharge Burnup
(MWDt/MTU)

C.3.3 Special Fuel Form – Consolidated/Reconstituted/Reconstructed Assemblies;
Non-standard Assemblies, & Failed Assemblies
C.3.3.1

Special Fuel Form – Consolidated/Reconstituted/Reconstructed Assemblies

Does your facility have consolidated/reconstituted/reconstructed assemblies?
______ Yes. Complete the remainder of Schedule C.3.3.1
______ No. Skip to Schedule C.3.3.2
For each consolidated/reconstituted/reconstructed assembly in the pool, give the assembly
identifier for the source assembly and provide the following:
Current Location
(Assembly
Identifier)

Source Assembly
Identifier

Number of Fuel
Rods from Source
Assembly

Initial Heavy Metal Content
Initial kgU

Initial kgPu

Discharge Burnup
(MWDt/MTU)

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.3.3.2

Special Fuel Form – Non-standard Assemblies

Does your facility have non-standard assemblies?
______ Yes. Complete the remainder of Schedule C.3.3.2
______ No. Skip to Schedule C.3.3.3
For each non-standard assembly that is currently stored canistered or uncanistered in the pool,
and requires special handling relative to intact assemblies for safety reasons, provide the
assembly identifier and a generic description of why the assembly is considered “non-standard”.
“non-standard intact assembly” means a spent nuclear fuel (SNF) assembly that does not meet
the general specification set forth in Appendix E of the Standard Contract.. Also included as
non-standard are assemblies other than light water reactor (LWR) assemblies and consolidated
assemblies.
“Standard intact assembly” means a SNF assembly that meets the following general
specification:
Maximum Nominal Physical Dimensions
Reactor (BWR)

Reactor (PWR)

Overall Length

14 feet, 11 inches

14 feet, 10 inches

Active Fuel Length

12 feet, 6 inches

12 feet, 0 inches

Cross Section*

6 inches x 6 inches

9 inches x 9 inches

*The Cross Section of the fuel assembly shall not include the channel.
For each non-standard assembly in the pool, give the assembly identifier for the source
assembly and provide the following:
Assembly
Identifier

Description of Non-standard Assembly

All fuel from this reactor is considered non-standard.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
C.3.3.3

Special Fuel Form – Failed Assemblies

Does your facility have failed assemblies?
______ Yes. Complete the remainder of Schedule C.3.3.3
______ No. Skip to Schedule C.3.4
For each failed fuel assembly that is currently stored canistered or uncanistered in the pool, and
requires special handling relative to intact assemblies for safety reasons, provide the assembly
identifier and a generic description of why the assembly is considered “failed”. “Failed Fuel”
means SNF assemblies that show visual evidence of structural deformity or damage to cladding
or spacers which may require special handling, assemblies which are structurally deformed or
have damaged cladding to the extent that special handling may be required, or assemblies that
cannot be handled with normal fuel handling equipment.
For each failed assembly in the pool, give the assembly identifier for the source assembly and
provide the following:
Assembly
Identifier

C.4

Description of Failure

Potential High Level Waste
Has your utility entered into a contract for reprocessing any discharged fuel which will result in
high level waste expected to be disposed of by the Federal government?
____ Yes.
____ No.

C.4.1

If Yes, is this contract with a domestic or international supplier of reprocessing
services?
____ Domestic
____ International
____ Both Domestic and International

C.4.2

What quantity of discharged fuel will be reprocessed?
________________________________________ (Metric Tons)

C.4.3

Provide details as to the type of waste anticipated to be generated.

Provide in Schedule G at the end of this data collection form any comments you have concerning Fuel Data.
Label your comments by the Schedule and Item Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE D: STORAGE FACILITY DATA
D.1

Storage Facility Point of Contact
Provide a storage facility point of contact for verification of information provided on this form.
If contact information is the same as in Schedule A or B, insert X in the block. A

B

Name:
Title:
Mailing Address:

City:

State:

Telephone Number:

Fax Number:

Zip Code:

Email:

D.2

Storage Facility Information (Pool Storage)
Complete a Schedule D.2 for each pool storage site.

D.2.1

Storage Site Identifier
_________ (See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”)

D.2.2

Storage Capacity
No. of Assemblies

BWR

PWR

Current NRC Licensed Storage Capacity

Current Installed Storage Capacity

Current NRC Licensed Storage Capacity -- report in number of assemblies. If the site is licensed for
different types of fuel (PWR, BWR), note each in the appropriate column. Note any change from
previous reporting period in the Comments Schedule (Schedule G).
Current Installed Storage Capacity -- report in number of assemblies. If the site is licensed for different
types of fuel (PWR, BWR), note each in the appropriate column. Do not deduct inventory from current
capacity.
Note in the Comments Schedule (Schedule G) if some of the storage capacity is unusable due to
mechanical/physical limitations.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
D.2.3

Storage Inventory

Storage Inventory -- Provide the number of assemblies stored at the storage site. Also enter the
number of assemblies discharged from each contributing reactor that are stored at the storage site.
Contributing Reactor Name

Number of Assemblies

Total Storage Site Inventory

D.3

Storage Facility Information (Dry Storage)
If your company has implemented a dry storage cask storage system at your site, an
independent spent fuel storage facility (ISFSI), provide the following information.

D.3.1

Storage Site Identifier
_______________________________________________________________
(See Appendix C, “Reactor and Spent Fuel Storage Site Identification Codes.”)

D.3.2

Multi-Assembly Canisters/Casks Inventory
Number of multi-assembly canisters/casks in service _____________

Unique Canister/Cask
Identifier

Vendor

Model Number

Date Loaded
(MMYYYY)

Total Number of Assemblies in Dry Storage

Number of Assemblies
Stored

NUCLEAR FUEL DATA SURVEY
FORM GC-859
D.3.3

Assemblies In Dry Storage
For each multi-assembly canister/cask, enter the assembly identifier for each assembly in that canister/cask.

Unique Canister/Cask
Identifier

Assembly Identifier

________________

________________

________________

________________

________________

For each canister / cask also submit a diagram showing the loading pattern. This can be submitted in any readily available format. Examples may include, an
attached pdf file of the face map which shows the location of the assemblies by ID number, paper copy diagrams, or a text or spreadsheet showing location
identifiers and assembly ID’s.
Provide in Schedule G at the end of this data collection form any comments you have concerning Storage Facility Data. Label your comments by the Schedule
and Item Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE E: NON-FUEL DATA
All materials not listed in Schedule C.3, Special Fuel Forms, should be included here. Non-fuel
components may be integral to an assembly (enter data in Schedule E.2), canistered (enter data in
Schedule E.3), separate from an assembly and uncanistered (enter data in Schedule E.4).

E.1

Non-fuel Components
Does your facility have non-fuel components that may be delivered to a Federal facility?
______ Yes. Complete the remainder of Schedule E
______ No. Skip to Schedule F
Non-fuel components are defined in the Standard Contract, as including, but not limited to,
control spiders, burnable poison rod assemblies, control rod elements, thimble plugs, fission
chambers, and primary and secondary neutron sources, that are contained within the fuel
assembly, or BWR channels that are an integral part of the fuel assembly, which do not require
special handling and may be included as part of the spent nuclear fuel. Note: Fuel that does not
meet these specifications shall be classified as non-standard fuel.
From the drop-down menu in the Type of Non-fuel Component column, select each type of nonfuel component currently stored at this storage facility. Provide the quantity of each type of nonfuel component identified.
Indicate in the Status Code columns how each type of non-fuel component is currently stored.
Check all status codes that apply. The status codes are:
( I ) – Stored as an integral part of an assembly (Enter the data in schedule E.2)
( C ) – Stored in a single assembly canister or container (Enter the data in schedule E.3)
( S ) – Stored separate from an assembly and uncanistered in the storage pool (Enter the data
in schedule E.4)

Type of Non-fuel Component

Number of Individual
Items

Non-fuel Components
Status Code(s)
I

C

S
















PWR - Control Rods
PWR - Control Rods Spiders
PWR - Thimble Plugs
BWR - Cruciform Control Blades
BWR - Fuel Channels
BWR/PWR - Burnable Absorbers
BWR/PWR - SF Disassembly Hardware
BWR/PWR - In-core Instrumentation
BWR/PWR - Neutron Sources
BWR/PWR – Other:

NUCLEAR FUEL DATA SURVEY
FORM GC-859
E.2

Non-fuel Components – Integral to an Assembly
Does your facility have non-fuel components that are stored as an integral part of an assembly
that are planned for delivery to a Federal facility?
______ Yes. Complete the remainder of Schedule E.2
______ No. Skip to Schedule E.3
For each assembly in which non-fuel components are stored, select each type of non-fuel
component. Estimate the weight of the assembly including all the non-fuel components. If the
storage of non-fuel components within an assembly classifies that assembly as non-standard
according to the Standard Contract, check the Yes box in the Non-standard Assembly column.
For example, changes to an assembly’s maximum physical dimensions may cause it to be
classified as non-standard.

Assembly
Identifier

Type of Non-fuel Component

Estimated
Total Weight
(lbs)

Non–standard
Assembly
Yes

No





















PWR - Control Rods
PWR - Control Rods Spiders
PWR - Thimble Plugs
BWR - Cruciform Control Blades
BWR - Fuel Channels
BWR/PWR - Burnable Absorbers
BWR/PWR - SF Disassembly Hardware
BWR/PWR - In-core Instrumentation
BWR/PWR - Neutron Sources
BWR/PWR – Other:

NUCLEAR FUEL DATA SURVEY
FORM GC-859
E.3

Non-fuel Components – Canistered
A canister is defined as a container designed to confine waste that may be delivered to a Federal facility. Report in this Schedule non-fuel
components data for single assembly canisters or containers which are currently stored in a storage pool. Data for single assembly canisters that
contain any spent nuclear fuel should also be reported in Schedule C.3, Special Fuel Forms.
Are there canisters or containers of non-fuel components in your pool planned for delivery to a Federal facility?
____ Yes. Provide the data requested in the table below for each canister
____ No. Skip to Schedule E.4

Canister
Identifier

Canister
Shape

C

R

Canister Dimensions
(to nearest 0.1 inch)

Length

Diameter/
Width

Loaded
Weight
(lbs)

Number
of
Individual
Items

Type of Non-fuel Component

Depth

Canister Closure

B

W

NC

Is Canister
Handled As A
Standard Fuel
Assembly?
Yes

Storage
Location

No

PWR - Control Rods
PWR - Control Rods Spiders
PWR - Thimble Plugs
BWR - Cruciform Control Blades
BWR - Fuel Channels
BWR/PWR - Burnable Absorbers
BWR/PWR - SF Disassembly Hardware
BWR/PWR - In-core Instrumentation
BWR/PWR - Neutron Sources
BWR/PWR – Other:

 

    

 

    
C = cylindrical

R = rectangular

B = bolted

W = welded

NC = not closed

For each canister identified in Schedule E.3 in which non-fuel components are stored, list and estimate the number of each applicable type of non-fuel component
that is stored in that canister. Estimate the loaded weight of the canister, including the non-fuel components, in pounds. Also indicate whether the canister may be
handled as a standard fuel assembly, using the same equipment used to move assemblies. Note the storage location from Appendix C, “Reactor and Spent Fuel
Storage Site Identification Codes”.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
E.4

Non-fuel Components – Separate from an Assembly and Uncanistered
Does your facility have uncanistered non-fuel components that are separate from an assembly
and currently stored in a storage pool that are planned for delivery to a Federal facility?
______ Yes. Complete the remainder of Schedule E.4.
______ No. Skip to Schedule F.
List and estimate the number of each applicable type of uncanistered non-fuel component
separate from an assembly and indicate the storage pool location from Appendix C “Reactor
and Spent Fuel Storage Site Identification Codes”.

Type of Non-fuel Component

Number of
Individual Items

Storage Location

PWR - Control Rods
PWR - Control Rods Spiders
PWR - Thimble Plugs
BWR - Cruciform Control Blades
BWR - Fuel Channels
BWR/PWR - Burnable Absorbers
BWR/PWR - SF Disassembly Hardware
BWR/PWR - In-core Instrumentation
BWR/PWR - Neutron Sources
BWR/PWR – Other:

Provide in Schedule G at the end of this data collection form any comments you have concerning Non-fuel
Components Data. Label your comments by the Schedule and Item Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE F:

GREATER-THAN-CLASS-C LOW-LEVEL RADIOACTIVE WASTE DATA
DOE is requesting information on Greater-Than-Class C (GTCC) Low-Level Radioactive Waste (LLRW) inventories.
GTCC LLRW is LLRW in which the concentrations of radionuclides exceed the limits for Class C LLRW established
by the Nuclear Regulatory Commission (NRC) in 10 CFR Part 61.55, Tables 1 and 2.

F.1

Stored Inventory
Include in this section waste that is currently packaged and available for disposal as of June 30, 2013.

F.1.1

Activated Metals
Activated metals are removed from the reactor prior to decommissioning nuclear reactors. Portions of the reactor assembly and other
components near the nuclear fuel are activated by neutrons during reactor operations, producing high concentrations or radionuclides. The major
radionuclides in these wastes are typically cobalt-60, nickel-63, niobium-94, and carbon-14.
Packaging3

Packaged
Package
Volum e
Contents 2
(ft3) 1

Type

Loaded
Total
Weight
Date
Package
of
Packaged Activity4
External External External Internal
Package
(MCi)
Num ber Length Diam eter Volum e Volum e
(lbs)
(in)
(ft 3)
(ft 3)
(in)

Rem otely
Handled6

Package Dim ensions

Radionuclide

1

1

3

Yes

Date of
Latest Date of
Last
Segm entation
Criticality
(MM/YYYY) 8
No (MM/YYYY)7























5

Packaged Volume (ft ): Combined volume of the waste and the storage container.
Package Contents: Identify the contents of each package.
3
Packaging Type and Number: Provide an entry for each waste stream indicating the type of package (for other, describe what the package is) and the quantity of packages.
4
Total Package Activity (MCi): Report the total activity of the package in million curies associated with the activated metals.
5
Radionuclide: Report the radionuclides that account for > 1% of total activity anticipated in the waste stream.
6
Remotely Handled: If the package has a dose rate of greater than 200 mrem/hr on the surface of the package, indicate if the package must be remotely handled.
7
Date of Last Criticality: The date of last criticality is the date the reactor was last critical from which the metal was derived.
8
Latest Date of Segmentation: For activated metal waste, indicate the date when the waste segmentation was complete.
* Alpha emitting transuranic nuclides with half-life greater than 5 years
2

NUCLEAR FUEL DATA SURVEY
FORM GC-859
F.1.2

Process Waste/Other Waste
Process and other waste includes GTCC LLRW that is not activated metals. It consists of contaminated equipment, debris, trash, filters, resins,
scrap metal, and decontamination and decommissioning waste.

Packaging3

Packaged
Package
Volum e
Contents 2
(ft 3) 1

Type

Loaded
Total
Weight
Date
Package
of
External External External Internal
Packaged Activity4
Package
Num ber Length Diam eter Volum e Volum e
(MCi)
(lbs)
(in)
(in)
(ft 3)
(ft 3)
Package Dim ensions

Radionuclide 5

1

1

3

Date
RCRA Listed
Rem otely
Hazardous
Handled6 Contents
Were
Waste
Rem oved Constituents
Yes No
From
or
Service 7 Characteristics 8



























Packaged Volume (ft ): Combined volume of the waste and the storage container.
Package Contents: Identify the contents of each package (e.g., resins, filters, etc .).
3
Packaging Type and Number: Provide an entry for each waste stream indicating the type of package (for other, describe what the package is) and the quantity of packages.
4
Total Package Activity (MCi): Report the total activity of the package in million curies associated with the process waste.
5
Radionuclide: Report the radionuclides that account for > 1% of total activity anticipated in the waste stream.
6
Remotely Handled: If the package has a dose rate of greater than 200 mrem/hr on the surface of the package, indicate if the package must be remotely handled.
7
Date Contents Were Removed From Service: For multiple dates, use the latest date.
8
RCRA Listed Hazardous Waste Constituents or Characteristics: If mixed waste, list any Resource Conservation and Recovery Act (RCRA) hazardous waste constituents or characteristics.
* Alpha emitting transuranic nuclides with half-life greater than 5 years
2

NUCLEAR FUEL DATA SURVEY
FORM GC-859
F.2

Projected Inventory (2013-2065)
F.2.1

Activated Metals
Include waste not packaged and waste projected to be generated from licensed activities from
2013 through reactor decommissioning. Include all waste not in F.1.1.

Years Packaged

Description of Waste

1

Estimated
Unpackaged Volume 2
(ft3)

Estimated
Packaged Volume 3
[If known]
(ft 3)

2013-2020

2021-2030

2031-2040

2041-2050

2051-2060

2061-2065

1

Description of Waste: Identify the specific content of the waste.
3
Estimated Unpackaged Volume (ft ): Volume of only the waste without any storage container.
3
3
Estimated Packaged Volume (ft ): Volume of the waste including any storage container.
2

NUCLEAR FUEL DATA SURVEY
FORM GC-859
F.2.2

Process Waste/Other Waste
Include process and other waste not packaged and waste projected to be generated from
licensed activities from 2013 through reactor decommissioning. Include all waste not in F.1.2.

Years
Packaged

Description of
Waste 1

Estimated
Unpackaged
Volume 2 (ft 3)

Estimated
Packaged Volume 3
[If known]
(ft 3)

RCRA Listed
Hazardous Waste
Constituents or
Characteristics 4

2013-2020

2021-2030

2031-2040

2041-2050

2051-2060

2061-2065

1

Description of Waste: Identify the specific content of the waste. (e.g., resins, filters, etc .)
3
Estimated Unpackaged Volume (ft ): Volume of only the waste without any storage container.
3
3
Estimated Packaged Volume (ft ): Volume of the waste including any storage container.
4
RCRA Listed Hazardous Waste Constituents or Characteristics: If mixed waste, list any Resource Conservation and
Recovery Act (RCRA) hazardous waste constituents or characteristics.
2

Provide in Schedule G at the end of this data collection form any comments you have concerning GreaterThan-Class C Low-Level Radioactive Waste Data. Label your comments by the Schedule and Item
Number to which they refer.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

SCHEDULE G: COMMENTS
Provide all comments you have in the comment schedule below. Label your comments by the Schedule and
Item Number to which they refer.
Schedule
and Item
Number

Comment

NUCLEAR FUEL DATA SURVEY
FORM GC-859

APPENDIX A – INSTRUCTIONS FOR COMPLETING NUCLEAR FUEL DATA
FORM GC-859
Appendix A - General Instructions
1.

Purpose and Use of Data

The Form GC-859 Nuclear Fuel Data survey collects data that the Office of the General Counsel (GC) uses for
assessing spent fuel storage and disposal requirements.
2.

Who Should Submit

This form should be submitted by all owners and custodians of spent nuclear fuel and/or high-level radioactive
waste.
3.

When To Submit

This form shall be submitted by September 15, 2013 following receipt of the form. Data on the form should
reflect the spent fuel status as of June 30, 2013.
4.

What To Submit

Data will be provided in both electronic and hard copy format.
Respondents will be provided with an electronic copy of their previous submittal to aid in the preparation of this
form. They will also be provided with electronic files and blank paper forms to aid in the current submittal. Note
that the detailed assembly-specific data requested on Schedule C should be submitted in database or
spreadsheet format.
The Form GC-859 updating system is automated and Microsoft Windows-based software is included in this
package. The system is self-contained and no additional software is needed.
Complete documentation and operating instructions for the software may be found in Appendix E, "Form GC859 Data Collection System Instructions”. After completing the form, print the Form GC-859 to make sure the
data are correct. Sign the statement certifying the accuracy of the historical data and return it with your data (as
an electronic file) in database or in a spreadsheet format by electronic mail, compact disk, DVD, or flash drive,
to the address in Schedule 5, below.
5.
Where To Submit
Submit Forms GC-859 and associated material to:
U.S. Energy Information Administration
Office of Electricity, Coal, Nuclear, and Renewables Analysis
U.S. Department of Energy
ATTN: Marta Gospodarczyk, EI-34
1000 Independence Ave., SW
Washington, DC 20585.
The Form GC-859 Access database files (mdb files) and spreadsheet files may be sent by electronic mail to
the following email address:
[email protected]
If you send your completed survey data by electronic mail, mail a signed copy of Schedule A to the mailing
address shown above.
After completing the survey using the Data Collection Software, click on “Tools/Database Utilities/Compact
Database” to reduce the size of the file before submitting.
You will receive a notice from the DOE confirming receipt of the files. If you have not received a
confirmation notice within three days, contact DOE at the telephone numbers provided on the cover
sheet of this form.
You may also submit your forms by fax at (202) 586-3045.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
6.

Legal Authority and Sanctions Statement

Data on this mandatory form are collected under authority of the Federal Energy Administration Act of 1974 (15
USC Schedule 761 et seq.), and the Nuclear Waste Policy Act of 1982 (42 USC l0l0l et seq.). Data being
collected on this form are not considered to be confidential.

Appendix A – Specific Instructions
Specific instructions to individual schedules of the Form GC-859 survey are included within the schedules.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

APPENDIX B – ASSEMBLY STATUS CODES
Status Code
N
F
C
R
P
B
O

Description
Standard intact assembly - blank or no code - This is the default.
Non-standard intact assembly
Failed assembly with cladding damage or mechanical damage (not canistered)
Canistered assembly
Canistered fuel rods
Canistered fuel debris (pieces)
Fuel in a basket
Other - provide description of other conditions in comment schedule; for
example, to identify an assembly type that is not included in Appendix B of the
instructions; or to describe characteristics which require special handling, etc.

GENERAL SPECIFICATIONS FROM THE STANDARD CONTRACT, APPENDIX E
a. “Standard intact assembly” means a spent nuclear fuel (SNF) assembly that meets the following
General Specifications:
Maximum Nominal Physical Dimensions
Reactor (BWR)

Reactor (PWR)

Overall Length

14 feet, 11 inches

14 feet, 10 inches

Active Fuel Length

12 feet, 6 inches

12 feet, 0 inches

Cross Section*

6 inches x 6 inches

9 inches x 9 inches

*The Cross Section of the fuel assembly shall not include the channel.
b. “Non-standard intact assembly” means an SNF assembly that does not meet the general specification
set forth above. Also included as non-standard are assemblies other than light water reactor (LWR)
assemblies and consolidated assemblies.

c.

“Failed Fuel” means SNF assemblies that show visual evidence of structural deformity or damage to 
cladding or spacers which may require special handling, assemblies which are structurally deformed or 
have damaged cladding to the extent that special handling may be required, or assemblies that cannot 
be handled with normal fuel handling equipment. 

NUCLEAR FUEL DATA SURVEY
FORM GC-859

APPENDIX C – REACTOR AND SPENT FUEL STORAGE SITE
IDENTIFICATION CODES
Storage Location
Arkansas Nuclear One - Unit 1
Arkansas Nuclear One - Unit 2
Arkansas Nuclear One (ISFSI)
Beaver Valley - Unit 1
Beaver Valley - Unit 2
Beaver Valley (ISFSI)
Big Rock Point
Big Rock Point (ISFSI)
Braidwood - Unit 1
Braidwood - Unit 2
Braidwood (ISFSI)
Browns Ferry - Unit 1
Browns Ferry - Unit 2
Browns Ferry - Unit 3
Browns Ferry (ISFSI)
Brunswick - Unit 1
Brunswick - Unit 2
Brunswick (ISFSI)
Byron - Unit 1
Byron - Unit 2
Byron (ISFSI)
Callaway
Callaway (ISFSI)
Calvert Cliffs - Unit 1
Calvert Cliffs - Unit 2
Calvert Cliffs (ISFSI)
Catawba - Unit 1
Catawba - Unit 2
Catawba (ISFSI)
Clinton
Clinton (ISFSI)
Columbia
Columbia (ISFSI)
Comanche Peak - Unit 1
Comanche Peak - Unit 2
Comanche Peak (ISFSI)
Cook - Unit 1
Cook - Unit 2
Cook (ISFSI)
Cooper Station
Cooper Station (ISFSI)
Crystal River 3
Crystal River 3 (ISFSI)
Davis-Besse
Davis-Besse (ISFSI)
Diablo Canyon - Unit 1
Diablo Canyon - Unit 2
Diablo Canyon (ISFSI)
Dresden - Unit 1
Dresden - Unit 2
Dresden - Unit 3
Dresden (ISFSI)
Duane Arnold
Duane Arnold (ISFSI)
Enrico Fermi 2
Enrico Fermi 2 (ISFSI)
Farley - Unit 1
Farley - Unit 2
Farley (ISFSI)
Fitzpatrick
Fitzpatrick (ISFSI)
Fort Calhoun

Reactor
ID
0401
0402
1601
1602
1201
1001
1002
4803
4804
4805
0701
0702
1003
1004
5101
0501
0502
1501
1502
2301
5302
4901
4902
5801
5802
3001
1701
5001
3501
3502
1005
1006
1007
2401
1402
0101
0102
3901
3401

Pool
ID
0401
0402
0401D
1601
1602
1601D
1201
1201D
1001
1001
1001D
4803
4803
4805
4803D
0701
0702
0701D
1003
1003
1003D
5101
5101D
0501
0501
0501D
1501
1502
1501D
2301
2301D
5302
5302D
4901
4901
4901D
5801
5801
5801D
3001
3001D
1701
1701D
5001
5001D
3501
3502
3501D
1005
1006
1007
1005D
2401
2401D
1402
1402D
0101
0102
0101D
3901
3901D
3401

Note

DC

DC
DC
CP
CP
DC
TC
TC
DC

DC
CP
CP
DC
DC
TC
TC
DC

DC
DC
DC
TC
TC
DC
CP
CP
DC
DC
DC
DC

DC

DC
DC
DC

DC
DC

Storage Location
Fort Calhoun (ISFSI)
Fort St. Vrain
Fort St. Vrain (ISFSI)
GE Morris
GE Vallecitos
Ginna
Ginna (ISFSI)
Grand Gulf
Grand Gulf (ISFSI)
H. B. Robinson
H. B. Robinson (ISFSI)
Haddam Neck
Haddam Neck (ISFSI)
Harris
Harris (ISFSI)
Hatch - Unit 1
Hatch - Unit 2
Hatch (ISFSI)
Hope Creek
Hope Creek (ISFSI)
Humboldt Bay
Humboldt Bay (ISFSI)
Idaho National Laboratory
Indian Point - Unit 1
Indian Point - Unit 2
Indian Point - Unit 3
Indian Point (ISFSI)
Kewaunee
Kewaunee (ISFSI)
Lacrosse
Lacrosse (ISFSI)
LaSalle County - Unit 1
LaSalle County - Unit 2
LaSalle County (ISFSI)
Limerick - Unit 1
Limerick - Unit 2
Limerick (ISFSI)
Maine Yankee
Maine Yankee (ISFSI)
McGuire - Unit 1
McGuire - Unit 2
McGuire (ISFSI)
Millstone - Unit 1
Millstone - Unit 2
Millstone - Unit 3
Millstone (ISFSI)
Monticello
Monticello (ISFSI)
Nine Mile Point - Unit 1
Nine Mile Point - Unit 2
Nine Mile Point (ISFSI)
North Anna - Unit 1
North Anna - Unit 2
North Anna (ISFSI)
Oconee - Unit 1
Oconee - Unit 2
Oconee - Unit 3
Oconee (ISFSI)
Oyster Creek
Oyster Creek (ISFSI)
Palisades
Palisades (ISFSI)

Reactor
ID
4101
4401
2901
0705
5701
0703
2001
2002
4201
3503
1101
1102
3902
5501
1301
1008
1009
3701
3702
2801
1504
1505
3201
3202
3203
3301
3101
3102
5201
5202
1506
1507
1508
1903
1204
-

Pool
ID
3401D
4101
4101D
6601
6201
4401
4401D
2901
2901D
0705
0705D
5701
5701D
0703
0703D
2001
2001
2001D
4201
4201D
3503
3503D
7002
1101
1102
3902
3902D
5501
5501D
1301
1301D
1008
1008
1008D
3701
3701
3701D
2801
2801D
1504
1505
1504D
3201
3202
3203
3201D
3301
3301D
3101
3102
3101D
5201
5201
5201D
1506
1506
1508
1506D
1903
1903D
1204
1204D

Note
DC
DC

DC
DC
DC
DC
DC
TC
TC
DC
DC
DC

DC
DC
DC
TC
TC
DC
TC
TC
DC
DC

DC

DC
DC

DC
CP
CP
DC
CP
CP
DC
DC
DC

NUCLEAR FUEL DATA SURVEY
FORM GC-859
Storage Location
Palo Verde - Unit 1
Palo Verde - Unit 2
Palo Verde - Unit 3
Palo Verde (ISFSI)
Peach Bottom - Unit 2
Peach Bottom - Unit 3
Peach Bottom (ISFSI)
Perry - Unit 1
Perry (ISFSI)
Pilgrim - Unit 1
Pilgrim (ISFSI)
Point Beach - Unit 1
Point Beach - Unit 2
Point Beach (ISFSI)
Prairie Island - Unit 1
Prairie Island - Unit 2
Prairie Island (ISFSI)
Quad Cities - Unit 1
Quad Cities - Unit 2
Quad Cities (ISFSI)
Rancho Seco
Rancho Seco (ISFSI)
River Bend
River Bend (ISFSI)
Salem - Unit 1
Salem - Unit 2
Salem (ISFSI)
San Onofre - Unit 1
San Onofre - Unit 2
San Onofre - Unit 3
San Onofre (ISFSI)
Seabrook
Seabrook (ISFSI)
Sequoyah - Unit 1
Sequoyah - Unit 2
Sequoyah (ISFSI)
Shoreham
South Texas One - Unit 1
South Texas One - Unit 2
South Texas One (ISFSI)
St Lucie - Unit 1
St Lucie - Unit 2
St Lucie (ISFSI)

Reactor
ID

Pool
ID

0301
0302
0303
3704
3705
0901
0601
5401
5402
3302
3303
1010
1011
4501
2101
4202
4203
4701
4702
4703
5901
4808
4809
2601
2201
2202
1801
1802
-

0301
0302
0303
0303D
3704
3705
3704D
0901
0901D
0601
0601D
5401
5401
5401D
3302
3302
3302D
1010
1010
1010D
4501
4501D
2101
2101D
4202
4203
4202D
4701
4702
4703
4701D
5901
5901D
4808
4808
4808D
2601
2201
2202
2201D
1801
1802
1801D

Note

DC

DC
DC
DC
CP
CP
DC
CP
CP
DC
TC
TC
DC
DC
DC

DC

DC
DC
CP
CP

Storage Location

Summer
Summer (ISFSI)
Surry - Unit 1
Surry - Unit 2
Surry (ISFSI)
Susquehanna - Unit 1
Susquehanna - Unit 2
Susquehanna (ISFSI)
Three Mile Island - Unit 1
Trojan
Trojan (ISFSI)
Turkey Point - Unit 3
Turkey Point - Unit 4
Turkey Point (ISFSI)
Vermont Yankee
Vermont Yankee (ISFSI)
Vogtle - Unit 1
Vogtle - Unit 2
Vogtle (ISFSI)
Washington Hanford
Waterford 3
Waterford 3 (ISFSI)
Watts Bar - Unit 1
Watts Bar - Unit 2
Watts Bar (ISFSI)
Wolf Creek
Wolf Creek (ISFSI)
Yankee Rowe
Yankee Rowe (ISFSI)
Zion - Unit 1
Zion - Unit 2
Zion (ISFSI)

Reactor
ID

Pool
ID

4601
5203
5204
3601
3602
1901
3801
1803
1804
6001
2003
2004
2701
4810
4811
2501
5601
1012
1013
-

4601
4601D
5203
5203
5203D
3601
3601
3601D
1901
3801
3801D
1803
1804
1803D
6001
6001D
2003
2003
2003D
7007
2701
2701D
4810
4810
4810D
2501
1601D
5601
5601D
1012
1012
1012D

Note

DC
CP
CP
DC
TC
TC
DC

DC

DC
DC
TC
TC
DC

DC
CP
CP
DC
DC
DC
CP
CP
DC

TC: Transfer Canal
CP: Common Pool Serving Two or More Reactors
DC: Dry Storage Site
ISFSI: Independent Spent Fuel Storage Installation
DC

DC

The Form GC-859 APPENDIX C – REACTOR AND SPENT FUEL STORAGE SITE IDENTIFICATION CODES will be
modified, adding Research Reactors, prior to delivery to the respondents for preparation.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

APPENDIX D – GLOSSARY OF TERMS
Activated Metals: Activated metals result from decommissioning nuclear reactors. Portions of the reactor
assembly and other components near the nuclear fuel are activated by neutrons during reactor operations,
producing high concentrations or radionuclides. The major radionuclides in these wastes are typically cobalt-60,
nickel-63, niobium-94, and carbon-14.
ANSI Assembly Identifier: The serial numbering scheme adopted by the American National Standards
Institute (ANSI) to ensure uniqueness of an assembly serial number.
Assembly Identifier: A unique string of alphanumeric characters which identifies an assembly, bundle, or
canister for a specific reactor in which it has been irradiated. This identifier should be consistent with other
submissions to the DOE/NRC, i.e., previous Form RW-859 and DOE/NRC Form 741.
Average Assembly Weight: Average initial loading weight in kilograms (kg) of heavy metal of fresh fuel
assemblies in a batch before they are initially inserted into the reactor core.
Average Discharge Burnup: The average amount of energy produced by each assembly in a batch of spent
fuel assemblies discharged from a nuclear reactor, reported in thousand megawatt days thermal per metric ton
of uranium (MWDt/MTU).
Average Initial Enrichment: Average initial enrichment for a fresh fuel assembly as specified and ordered in
fuel cycle planning. This average should include axial blankets, and axially and radially zoned enrichments.
Basket: An open container into which fuel and/or non-fuel components including rods, sections of rods, fuel
pellets, garbage, debris, etc., are placed. Baskets are usually defined as rodlet or garbage and debris
containers with dimensions less than that of a fuel assembly.
Batch: A batch (or group) is a logical grouping of assemblies with similar characteristics. All assemblies in a
batch have the same initial average enrichment, the same cycle/reactor history, the same current location, the
same burnup, the same owner, and the same assembly design characteristics.
Boiling Water Reactor (BWR): A light water reactor in which water, used as both coolant and moderator, is
allowed to boil in the core. The resulting steam is used directly to drive a turbine.
Burnup: Amount of thermal energy generated per unit mass of fuel, measured in units of megawatt days
thermal per initial metric ton of uranium (MWDt/MTU).
Canister: A single assembly canister is defined as any container designed to confine waste that may be
delivered to a Federal facility. A canister has dimensions that fit within the envelope defined by the Standard
Contract and can be handled similar to an assembly.
Cell: A physical position in a rack in a storage pool or a dry storage module, which is intended to be occupied
by an intact assembly or equivalent (that is, a canister or an assembly skeleton).
Consolidated Fuel: Fuel rods are removed from an assembly and placed into a canister in a grid with spacing
closer than that of an intact assembly. Consolidation maximizes density, lowers criticality, and improves heat
transfer.
Core: The place in the reactor in which the nuclear fuel is irradiated and thermal energy is generated.
Core Size: The fixed number of fuel assemblies that can be irradiated at any one time in the reactor core.
Current Installed Capacity: Total number of assembly storage cells in the spent nuclear fuel pool. Both
occupied and unoccupied cells are included in the current capacity.
Current Inventory: Number of spent nuclear fuel assemblies stored at a given site or spent nuclear fuel pool,
at a given point in time.
Cycle: For the purposes of this form, a cycle is the time period beginning with the startup of a reactor after
refueling (or initial fueling) to the time the reactor is considered subcritical. Refueling times should not be
included in cycle lengths.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
Enrichment: A nuclear fuel cycle process in which the concentration of fissionable uranium is increased above
its natural level. Enrichment is the process that changes the isotopic ratio in a material.
Failed Fuel Assembly: “Failed Fuel” means spent nuclear fuel assemblies that show visual evidence of
structural deformity or damage to cladding or spacers which may require special handling, assemblies which are
structurally deformed or have damaged cladding to the extent that special handling may be required, or
assemblies that cannot be handled with normal fuel handling equipment. Included are spent nuclear fuel
assemblies that will not fit into a spent fuel rack, cannot be lifted normally, or have already been canistered. An
assembly is classified as failed if it contains any fuel rods having known or suspected cladding defects greater
than pin holes or hairline cracks that would require canistering for shipment. Failed fuel means spent nuclear
fuel that meets the specifications in 10 CFR 961.11 subparagraphs 1 through 3 of paragraph B and is classified
as Failed Fuel Class F-1 through F-3 in subparagraph 6 of paragraph B.
Fuel Assembly: The basic unit of nuclear fuel. Uranium dioxide pellets are encased in cladding to form a fuel
rod. Fuel rods are structurally connected to form a fuel assembly.
Fuel Cycle: The length of time a reactor is operated between refueling, typically 18 to 24 months, including the
refueling time, measured from the startup of one cycle to the startup of the following cycle.
Greater Than Class C (GTCC) Waste: Greater-Than-Class-C radioactive waste (GTCC) is waste generated
by licensees of the NRC. The waste has concentrations of certain radionuclides above the Class C limits as
stated in 10 CFR 61.55. GTCC waste is considered a form of low-level radioactive waste (LLW). Most forms of
GTCC waste are generated by routine operations at nuclear power plants. Examples of GTCC waste include
activated metal hardware (e.g., nuclear power reactor control rods), spent fuel disassembly hardware, ion
exchange resins, filters and evaporator residues.
High-Level Radioactive Waste (HLW): The highly radioactive materials produced as byproducts of fuel
reprocessing or of the reactions that occur inside nuclear reactors. HLW includes irradiated spent nuclear fuel
discharged from commercial nuclear power reactors, highly radioactive liquid and solid materials resulting from
the reprocessing of spent nuclear fuel, and other highly radioactive materials that the NRC may determine
require permanent isolation.
High-Temperature, Gas-Cooled Reactor (HTGR): A reactor that is cooled by helium and moderated by
graphite.
Independent Spent Fuel Storage Installation (ISFSI): A dry storage complex designed and constructed for
the interim storage of spent nuclear fuel; solid, reactor-related, greater than Class C waste; and other
associated radioactive materials. A spent fuel storage facility may be considered independent, even if it is
located on the site of another NRC-licensed facility.
Initial Enrichment: The isotopic percentage of uranium-235 or plutonium, by weight, that is present in nuclear
fuel.
Initial Loading Weight: Average weight in kilograms (kg) of heavy metal in a fresh fuel assembly before it is
inserted into the reactor core.
Lattice Type: Lattice is an arrangement or array of fuel rods in a nuclear fuel assembly.
Light Water Reactor (LWR): A nuclear reactor that uses water as the primary coolant and moderator, with
slightly enriched uranium as fuel. There are two types of commercial light water reactors: the boiling water
reactor (BWR) and the pressurized water reactor (PWR).
Non-fuel Components: Non-fuel components include, but are not limited to, control spiders, burnable poison
rod assemblies, control rod elements, thimble plugs, fission chambers, and primary and secondary neutron
sources, that are contained within the fuel assembly, or BWR channels that are an integral part of the fuel
assembly, which do not require special handling.
Non-standard Fuel: Non-standard fuel means a spent nuclear fuel assembly that does not meet one or more
of the general specifications in 10 CFR 961.11 subparagraphs 1 through 5 of paragraph B. Also included as
non-standard are assemblies other than light water reactor (LWR) assemblies and consolidated assemblies.

NUCLEAR FUEL DATA SURVEY
FORM GC-859
NRC Licensed Site Capacity: Maximum number of spent nuclear fuel assembly and canister slots licensed for
use at a given site or spent nuclear fuel pool, as licensed by the Nuclear Regulatory Commission.
Nuclear Fuel: Fissionable materials that are enriched to such a composition that when placed in a nuclear
reactor will support a self-sustaining fission chain reaction, producing heat in a controlled manner for process
use.
Permanently Discharged Fuel: Spent nuclear fuel for which there are no plans for reinsertion in the reactor
core.
Planar Initial Enrichment: The average of the distributed fuel rod initial enrichments within a given axial plane
of the assembly lattice.
Pressurized Water Reactor (PWR): A light water reactor in which heat is transferred from the core to a heat
exchanger via water kept under high pressure, so that high temperatures can be maintained in the primary
system without boiling the water. Steam is generated in a secondary circuit.
Pool Site: One or more spent fuel storage pools, which have a single cask loading area. Dry cask storage
areas are considered separate sites.
Process Waste: Process and other waste includes Greater than Class C (GTCC) waste that is not activated
metals or sealed sources. It consists of contaminated equipment, debris, trash, filters, resins, scrap metal, and
decontamination and decommissioning waste.
Radioactivity: The rate at which radioactive material emits radiation, stated in terms of the number of nuclear
disintegrations occurring per unit of time; the basic unit of radioactivity is the curie.
Radionuclide: An unstable isotope of an element that decays or disintegrates spontaneously, thereby emitting
radiation. Approximately 5,000 natural and artificial radioisotopes have been identified.
Reconstituted Fuel: Spent nuclear fuel which has had a defective rod or rods removed and replaced with
another rod or rods. The recipient fuel assembly is intended to be reinserted into a subsequent fuel cycle.
Refueling: The process of shutting down a reactor and replacing some of the spent nuclear fuel assemblies.
Reinserted Fuel: Irradiated fuel that is discharged in one cycle and inserted in the same reactor during a
subsequent refueling. In a few cases, fuel discharged from one reactor has been used to fuel a different
reactor.
Shutdown Date: Day, month, and year of shutdown for fuel discharge and refueling. The date should be the
point at which the reactor became subcritical.
Spent Fuel Disassembly (SFD) Hardware: The skeleton of a fuel assembly after the fuel rods have been
removed. Generally, SFD hardware for PWR assemblies includes guide tubes; instrument tubes; top and bottom
nozzles; grid spacers; hold-down springs; and attachment components, such as nuts and locking caps. For
BWR fuel assemblies, SFD hardware includes the top and bottom tie plates, compression springs for individual
fuel rods, grid spacers, and water rods.
Standard Contract: The agreement (as set forth in 10 CFR Part 961) between the Department of Energy
(DOE) and the owners or generators of spent nuclear fuel and high-level radioactive waste.
Standard Fuel: Standard fuel means a spent nuclear fuel assembly that meets all the general specifications
set forth in 10 CFR 961.11 paragraph B.
Storage Site ID: Spent nuclear fuel storage pool or dry cask storage facility, usually located at the reactor site,
as licensed by the Nuclear Regulatory Commission (NRC).
Temporarily Discharged Fuel: Fuel which was irradiated in the previous fuel cycle (cycle N) and not in the
following fuel cycle (cycle N+1), and for which there are definite plans to irradiate in a subsequent fuel cycle.

NUCLEAR FUEL DATA SURVEY
FORM GC-859

APPENDIX E – FORM GC-859 DATA COLLECTION SYSTEM
INSTRUCTIONS
The FORM GC-859 DATA COLLECTION SOFTWARE SYSTEM is currently being developed
and will reflect this data collection form. The Form GC-859 Data Collection System is
being designed in Microsoft Access. The system will be a self-contained system, so no
software is required and minimal computer proficiency is needed. Though the software to
be used in the collection of the Form GC-859 system will be developed in Microsoft
Access, the new system will be designed to look and act like Microsoft Excel.
The Form GC-859 Data Collection System instructions are currently being developed in
conjunction with the development of the Data Collection System.