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Energy Information Administration
U.S. DEPARTMENT OF ENERGY
Form Approved
OMB NO. 1901-0287
Expiration Date:
/ /
NUCLEAR FUEL DATA SURVEY
FORM RW-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.
As described in Article VIII of the Standard Contract for Disposal of Spent Nuclear Fuel and/or
High Level Radioactive Waste, you also have a contractual obligation to report any changes in
the status of fuel assemblies covered by the one-time fee to the DOE on Annex B of Appendix
G of the Standard Contract.
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 40 hours
per response, including 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 aspects of this
collection of information, including suggestions for reducing this burden, to the Energy
Information Administration, Statistics and Methods Group, EI-70, 1000 Independence Avenue,
S.W., Washington, DC 20585, and to the Office of Information and Regulatory Affairs, Office of
Management and Budget, Washington, DC 20503.
Form Due Date:
This form shall be submitted by February 15 of the year following receipt of the survey form.
Data on the form should reflect the spent fuel status as of December 31 of the survey year.
EIA Contact:
Refer all questions to: Jim Finucane at (202) 287-1966 or Jack Thorpe at (202) 287-1920 and
return completed form to:
Energy Information Administration (EI-52)
U.S. Department of Energy
1000 Independence Ave. SW
Attn: Jim Finucane, EI-52
Room 6018, 950 L’Enfant Plaza
Washington, DC 20585-1615
RESPONDENT IDENTIFICATION
Site Operator Name:
REPORT PERIOD
Begin Report
Period: January
End Report
Period: December
2
0
0
3
2
0
0
X
If this is a resubmission, insert X in the block
NUCLEAR FUEL DATA SURVEY
FORM RW-859
CONTENTS
SCHEDULE A:
PAGE
SITE OPERATOR DATA ....................................................................................................... 1
A.1
Site Operator Name/Identifier......................................................................................................................... 1
A.2
Site Operator Point of Contact ........................................................................................................................ 1
A.3
Authorized Signature/Certification ................................................................................................................. 1
SCHEDULE B:
REACTOR DATA................................................................................................................... 2
B.1
Reactor Point of Contact .................................................................................................................................. 2
B.2
Reactor License Data........................................................................................................................................ 2
B.3
Cycle Data ......................................................................................................................................................... 3
SCHEDULE C:
DISCHARGED FUEL DATA .................................................................................................. 4
C.1
Data On Permanently Discharged Fuel .......................................................................................................... 4
C.2
Reinserted Fuel Data ........................................................................................................................................ 7
C.3
Projected Assembly Discharges ....................................................................................................................... 7
C.4
Special Fuel Form – Canisters ......................................................................................................................... 8
C.5
Special Fuel Form – Uncanistered Fuel Rods/Pieces ................................................................................... 10
C.6
Special Fuel Form – Nonstandard assemblies .............................................................................................. 10
C.7
Special Fuel Form – Failed Assemblies ......................................................................................................... 10
C.8
Special Fuel Form – Consolidated/Reconstituted/Reconstructed Assemblies ........................................... 10
SCHEDULE D:
STORAGE FACILITY DATA ................................................................................................ 11
D.1
Storage Facility Point of Contact................................................................................................................... 11
D.2
Storage Facility Information.......................................................................................................................... 11
SCHEDULE E:
NON-FUEL DATA ................................................................................................................ 13
E.1
Non-Fuel Components .................................................................................................................................... 13
E.2
Non-Fuel Components – Canistered.............................................................................................................. 13
E.3
Non-Fuel Components – Separate from an Assembly ................................................................................. 14
E.4
Non-Fuel Components – In Dry Storage....................................................................................................... 15
SCHEDULE F:
COMMENTS ........................................................................................................................ 16
Appendix A – Instructions for Completing Nuclear Fuel Data Form RW-859 ................................................... A-1
Appendix B – Identification of Fuel Type Codes.................................................................................................... B-1
Appendix C – Assembly Status Codes ..................................................................................................................... C-1
Appendix D – Reactor and Spent Fuel Storage Site Identification Codes............................................................ D-1
Appendix E – Glossary of Terms ............................................................................................................................. E-1
Appendix F – Form RW-859 Data Collection System Instructions ...................................................................... F-1
ii
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE A:
A.1
SITE OPERATOR DATA
SITE OPERATOR NAME/IDENTIFIER
A.1.1
Site Operator Name:
A.1.2
List all reactors being covered by this report. See Appendix D, “Reactor and Spent Fuel
Storage Site Identification Codes.”
Reactor
Identifier
Reactor Name
A.1.3
List all storage facilities being covered by this report. See Appendix D, “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 F at the end of this data collection form (page 15) any comments you have concerning
Site Operator Data. Label your comments by the Schedule and Item Number to which they refer.
1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE B:
B.1
REACTOR DATA
REACTOR POINT OF CONTACT
Provide a reactor point of contact for verification of information provided on this form.
If contact information is the same as in Schedule A, insert X in the block.
Name:
Title:
Mailing Address:
City:
State:
Telephone Number:
Fax Number:
Zip Code:
Email:
B.2
REACTOR LICENSE DATA
B.2.1
Reactor Identifier
___________ (See Appendix D, “Reactor and Spent Fuel Storage Site Identification
Codes.”)
B.2.2
NRC License Expiration Date (MMDDYYYY): ___ ___ _______
B.2.3
NRC License Type:
B.2.4
Is an NRC License Extension Anticipated or Completed?
B.2.5
NRC License Extension Status:
2
NUCLEAR FUEL DATA SURVEY
FORM RW-859
B.3
CYCLE DATA
Provide the following data, including all cycles completed since your last report.
Cycle Number
Start Up Date
(MMDDYYYY)
Shutdown Date
(MMDDYYYY)
Provide in Schedule F at the end of this data collection form (page 15) any comments you have concerning
Reactor Data. Label your comments by the Schedule and Item Number to which they refer.
3
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE C:
C.1
DISCHARGED FUEL DATA
DATA ON PERMANENTLY DISCHARGED FUEL
The Form RW-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.
Assembly
Identifier
This should be the site operator-assigned unique identifier. Note that nonintact 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.
Uranium Content
The initial contents of the fuel assembly in kilograms of uranium (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).)
Cycle Number
Report cycle number for the assembly’s final cycle of irradiation. You need
not report cycle number if the cycle numbers and corresponding dates were
reported in Schedule B.3 above.
Cycle Shutdown
Date
Report shutdown date for the assembly’s final cycle of irradiation, regardless
of when the fuel assembly was removed from the core.
Fuel Assembly
Type
Assign the appropriate code from Appendix B, pages B-1 to B-11. If there is
no appropriate code listed, include the type assigned by the manufacturer,
call EIA for an appropriate code, or insert an “O” and provide details of the
fuel assembly type in the Comments Schedule, Schedule F.
Assembly Status
Use the appropriate code from Appendix C, page C-1). Note that only
permanently discharged assemblies are to be reported in this Schedule.
Storage Location
Select the appropriate pool storage site or dry storage site identifier from
Appendix D, pages D-1 and D-2. 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. 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 or on diskette or compact disk to DOE at the addresses
specified in the instructions and on the cover page of this form. In lieu of submitting assemblyspecific 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 during this reporting
period.
4
NUCLEAR FUEL DATA SURVEY
FORM RW-859
C.1
DATA ON PERMANENTLY DISCHARGED1 FUEL
Assembly
Identifier
Uranium
Content
2
(Initial kgU)
Initial
Enrichment
3
(Weight %)
Discharge
Burnup
4
(MWDt/MTU)
Last
Cycle
5
Number
Last Cycle
Shutdown Date
5
(MM/DD/YYYY)
Fuel
Assembly
Type
6
Code
Assembly Status Code(s)
Storage
7
Location
8
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 either last cycle number or last cycle shutdown date.
6
See Appendix B, “Identification of Fuel Type Codes” If the fuel assembly type is not included in Appendix B, include the type assigned by the manufacturer here and put an “O” in the
Assembly Status Code column for that item, or provide a description of the assembly type in the comments Schedule (Schedule F).
7
See Appendix D, “Reactor and Spent Fuel Storage Site Identification Codes.”
5
NUCLEAR FUEL DATA SURVEY
FORM RW-859
8
See Appendix C, “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.
6
NUCLEAR FUEL DATA SURVEY
FORM RW-859
C.2
REINSERTED FUEL DATA
Reinserted fuel data should include both assemblies previously reported as permanently discharged
and in a storage pool at the end of the previous reporting period that were removed and reinserted
into this reactor and assemblies that were discharged during this reporting period and subsequently
reinserted during this reporting period.
C.2.1
Number of Reinserted Assemblies
C.2.2
Assembly Identifiers
______
Provide the Assembly Identifier for each reinserted assembly.
Assembly
Identifier
C.3
Assembly
Identifier
Assembly
Identifier
Assembly
Identifier
Assembly
Identifier
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
•
Reactor/Cycle History
•
Initial Uranium Content (within 3 kgU for BWR, 5 kgU for PWR)
•
Initial Enrichment (within nearest tenth of a percent)
•
Estimated Final Burnup (within 5% of the group average GWDt/MTU)
Projections of discharged assemblies must be reported for at least the next five cycles.
Cycle
Number
Planned Cycle
Shutdown
Date
(MMYYYY)
Group
Identifier
Number of
Assemblies
Discharged in
the Group
Projected
Average
Initial
Uranium
Content per
Assembly
(kgU)
Projected
Average
Initial
Enrichment
(Weight %)
Projected
Discharge
Burnup per
Assembly
(GWDt/MTU)
7
NUCLEAR FUEL DATA SURVEY
FORM RW-859
C.4
SPECIAL FUEL FORM – CANISTERS
A canister is defined as any container designed to confine waste that may be delivered to a Federal
repository. Within this Schedule, canistered material may include damaged assemblies, intact fuel
rods that have been removed from an assembly, and miscellaneous fuel. Empty canisters should not
be reported.
C.4.1
Canisters in Pool
Are there canisters containing fuel in your pool that are planned for delivery to a Federal
repository?
____ Yes. Complete Schedule C.4.2. Complete Schedule C.4.3 – C.4.4 for each canister
identified in Schedule C.4.2.
____ No. Skip to Schedule C.5.
C.4.2
Canister Description
Canister
Identifier
Canister
Shape
C
R
Length
C = cylindrical
C.4.3
Loaded Weight
(kg)
Canister Dimensions (inches)
Diameter/ Width
Depth
R = rectangular
Qualitative Canister Contents
For each canister identified in Schedule C.4.2, provide a qualitative description of the
contents and identify, if applicable, the method used to close the canister.
Canister
Identifier
Description of Contents
(check all that apply)
Canister Closure
B
W
NS
__ 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.4.4
W = welded
NS = not sealed
Detailed Canister Contents
For each canister identified in Schedule C.4.2, provide a detailed description of the contents.
Canister
Identifier
Assembly
Identifier
Number of Fuel Rod
Equivalents from
Assembly
Uranium Content
(Initial kgU)
Discharge Burnup
(MWDt/MTU)
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NUCLEAR FUEL DATA SURVEY
FORM RW-859
9
NUCLEAR FUEL DATA SURVEY
FORM RW-859
C.5
SPECIAL FUEL FORM – UNCANISTERED FUEL RODS/PIECES
Does your facility have uncanistered fuel? Include all materials that were not listed in Schedules
C.4.1 to C.4.4 (i.e., materials stored in baskets, materials to be repackaged, etc.).
______ Yes. Complete the remainder of Schedule C.5.
______ No. Skip to Schedule C.6.
For all uncanistered fuel rods and fuel pieces, provide a detailed description.
Assembly
Identifier
C.6
Number of Fuel Rod
Equivalents from Assembly
Uranium Content (Initial kgU)
Discharge Burnup
(MWDt/MTU)
SPECIAL FUEL FORM – NONSTANDARD ASSEMBLIES
For each nonstandard assembly that is currently stored uncanistered in the pool, and requires special
handling relative to intact assemblies for safety reasons, provide:
Assembly
Identifier
Description of Nonstandard Assembly
All fuel from this reactor is considered nonstandard.
C.7
SPECIAL FUEL FORM – FAILED ASSEMBLIES
For each assembly that is currently stored uncanistered in the pool, and requires special handling
relative to intact assemblies for safety reasons, provide:
Assembly
Identifier
C.8
Description of Failure
SPECIAL FUEL FORM – CONSOLIDATED/RECONSTITUTED/RECONSTRUCTED ASSEMBLIES
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
Uranium
Content
(Initial kgU)
Discharge
Burnup
(MWDt/MTU)
Provide in Schedule F at the end of this data collection form (page 15) any comments you have concerning
Fuel Data. Label your comments by the Schedule and Item Number to which they refer.
10
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE D:
D.1
STORAGE FACILITY DATA
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
Complete a Schedule D.2 for each storage site, including BOTH wet storage pools and dry storage
sites.
D.2.1
Storage Site Identifier
___________ (See Appendix D, “Reactor and Spent Fuel Storage Site Identification
Codes.”)
D.2.2
Storage Capacity
BWR
PWR
(No. of Assemblies)
Current NRC Licensed Capacity
Current Installed Capacity
D.2.3
Storage Inventory
Number of
Assemblies
Contributing Reactor Name
Cumulative
Number of
Assemblies
Overall Pool Inventory
D.2.4
Shipments/Transfers of Discharged Fuel
Report all shipments of fuel assemblies from this pool to another storage site (pool or dry
storage) and to this pool from another storage site since the end of the previous reporting
period.
(See Appendix D, “Reactor and Spent Fuel Storage Site Identification Codes.”)
Assembly
Identifier
Former
Storage Site
Identifier
Current
Storage Site
Identifier
Assembly
Identifier
Former
Storage Site
Identifier
Current
Storage Site
Identifier
11
NUCLEAR FUEL DATA SURVEY
FORM RW-859
D.2.5
Dry Storage
If your company has implemented dry storage at your site, provide the following additional
information.
Multi-element Canisters/Casks Inventory
Number of Multi-element Canisters/Casks in Service _____________
Unique
Canister/Cask
Identifier
Vendor
Model Number
Date Loaded
(MMYYYY)
Number of
Assemblies
Stored
Provide in Schedule F at the end of this data collection form (page 15) any comments you have concerning
Storage Data. Label your comments by the Schedule and Item Number to which they refer.
12
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE E:
E.1
NON-FUEL DATA
NON-FUEL COMPONENTS
Does your facility have non-fuel components that may be delivered to a Federal repository?
______ Yes. Complete the remainder of Schedule E.
______ No. Skip to Schedule F.
List each applicable type of non-fuel component currently stored at this storage facility. Provide the
quantity and estimate the volume and weight of each type of non-fuel component identified.
Type of Non-fuel Hardware
Number of
Individual
Items
Total
Volume,
if not
intact
3
(inch )
Estimated
Average
Weight
(kg)
Non-fuel
Hardware
Status Code(s)
C
S
D
The default Status Code is null and represents non-fuel components that are stored as an integral
part of an assembly. Other status codes include canistered components (C), separated components
(S), and components in dry storage (D).
E.2
NON-FUEL COMPONENTS – CANISTERED
A canister is defined as any container designed to confine waste that may be delivered to a Federal
repository. Empty canisters should not be reported. A canister that contains ANY spent nuclear fuel
should be reported in Schedule C.4.
Are there canisters of non-fuel components in your pool planned for delivery to a Federal repository?
____ Yes. Provide the date requested in Schedules E.2.1 – E.2.2 for each canister.
____ No. Skip to Schedule E.3.
E.2.1
Canister Description
Canister
Identifier
Canister
Shape
C
R
Length
Canister Dimensions (inches)
Diameter/ Width
Depth
Loaded Weight
(kg)
C = cylindrical
R = rectangular
13
NUCLEAR FUEL DATA SURVEY
FORM RW-859
E.2.2
Canister Contents
Canister
Identifier
Canister
Closure
B
W
NS
Description of Contents
B = bolted
E.3
W = welded
NS = not sealed
NON-FUEL COMPONENTS – SEPARATE FROM AN ASSEMBLY
Does your facility have uncanistered non-fuel components that are separate from an assembly that
are planned for delivery to a Federal repository?
______ Yes. Complete the remainder of Schedule E.3.
______ No. Skip to Schedule E.4.
List and estimate the number, volume and weight of each applicable type of separated non-fuel
component.
Type of Non-fuel Hardware
Number of
Individual
Items
Total
Volume, if
not intact
3
(inch )
Estimated
Average
Weight
(kg)
14
NUCLEAR FUEL DATA SURVEY
FORM RW-859
E.4
NON-FUEL COMPONENTS – IN DRY STORAGE
Does your facility have non-fuel components in dry storage that are planned for delivery to a Federal
repository?
______ Yes. Complete the remainder of Schedule E.4.
______ No. Skip to Schedule F.
List and estimate the number, volume and weight of each applicable type of non-fuel components in
dry storage at your facility.
Type of Non-fuel Hardware
Number of
Individual
Items
Total
Volume, if
not intact
3
(inch )
Estimated
Average
Weight
(kg)
For each individual dry storage multi-element canister/cask containing non-fuel components, provide
the following:
Vendor:_____________ Model: _____________
Date Loaded (MMYYYY): ____ ________
Contents: ____________________ (Describe contents)
_____ No. Skip to Schedule F.
Provide in Schedule F at the end of this data collection form (page 15) any comments you have concerning
Non-Fuel Components Data. Label your comments by the Schedule and Item Number to which they refer.
15
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SCHEDULE F:
COMMENTS
Provide all comments you have in the comment Schedule below. Also Label your comments by the Schedule
and Item Number to which they refer.
Schedule
and Item
Number
Comment
16
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDICES
Appendix A – Instructions for Completing Nuclear Fuel Data Form RW-859 ................................................... A-1
Appendix B – Identification of Fuel Type Codes.....................................................................................................B-1
Appendix C – Assembly Status Codes..................................................................................................................... C-1
Appendix D – Reactor and Spent Fuel Storage Site Identification Codes ........................................................... D-1
Appendix E – Glossary of Terms..............................................................................................................................E-1
Appendix F – Form RW-859 Data Collection System Instructions .......................................................................F-1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX A – INSTRUCTIONS FOR COMPLETING NUCLEAR FUEL DATA FORM RW-859
Appendix A – General Instructions
1.
Purpose and Use of Data
Form RW-859 "Nuclear Fuel Data" collects data that the Office of Civilian Radioactive Waste Management
(OCRWM) uses for assessing spent fuel storage and disposal requirements.
2.
Who Should Submit
This form should be submitted by all owners and custodians of irradiated nuclear fuel.
3.
When To Submit
This form shall be submitted by February 15 of the year following receipt of the form. Data on the form should
reflect the spent fuel status as of December 31 of the survey year.
4.
What To Submit
Data may be provided in electronic or in 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.1 should be submitted in database or
spreadsheet format.
The Form RW-859 updating system is automated and Microsoft Windows-based software is included in this
package.
Complete documentation and operating instructions for the supplied software may be found in Appendix F, "Form
RW-859 Data Collection Software”. After completing the form, print the Form RW-859 to make sure the data are
correct. Sign the statement certifying the accuracy of the historical data and return it with your data diskettes or
compact disks to the address in Schedule 5, below.
5.
Where To Submit
Submit Forms RW-859 and associated material to:
Energy Information Administration (EI-52)
U.S. Department of Energy
1000 Independence Ave., SW
ATTN: Jim Finucane, EI-52
Room 6018, 950 L’Enfant Plaza
Washington, DC 20585-1615
The Form RW-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 (page 1) 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 may also transmit your files using the EIA’s Secure File Transfer (SFT) System. You may access the SFT
System at the following URL:
https://idc.eia.doe.gov/upload/noticerw859.jsp
You will receive a notice from the DOE confirming receipt of the files. If you have not received a
A-1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
confirmation notice within three days, contact DOE at the telephone number provided on the cover sheet
of this form.
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.
7.
Fee Status Changes
Any assemblies that were reported as irradiated prior to April 7, 1983, were assigned a status (D = Discharged,
T = Temporarily Discharged, I = Incore). This status was used as a basis for calculating the one-time fee. A
change of status of any of those assemblies and the corresponding adjustment to the one-time fee must be
reported to the DOE Contracting Officer on Annex B to Appendix G of the Standard Contract for Disposal of
Spent Nuclear Fuel and/or High-Level Radioactive Waste.
A-2
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Appendix A – Specific Instructions
SCHEDULE A: SITE OPERATOR DATA
A.1
Complete name of the utility or operating company assigned primary operating
responsibility, and the names of the reactors and storage facilities. Also provide the reactor and
storage facility IDs using the codes in Appendix D.
A.2
Complete name, title, address and telephone number of person with corporate (site
operator-wide) responsibility who may be contacted to verify the data given on this form or verify
changes between updates of this form.
A.3
Complete name, title and address of cognizant individual having the authority to certify
and release the information included on this form. Be sure to sign and date the preprint. (NOTE:
Corporate Officer's signature is not required.)
SCHEDULE B: REACTOR DATA
Complete a Schedule B for each reactor, including operating and shutdown reactors.
B.1
Complete name, title, address and telephone number of person who may be contacted
to verify the data for this reactor or verify changes between updates of this form. If this person is
also the site operator-wide contact, simply indicate this by placing an ‘X’ in the indicated box.
B.2
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.3
List all operating cycles covered in this reporting period. 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.
If the reactor has experienced a fuel 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. If the reactor is currently
shutdown in a mid-cycle outage, you may indicate a shutdown date for the subcycle. This data
may be changed at a later time if the subcycle is resumed without the discharge of fuel.
Verify the continued accuracy of previously submitted cycle data.
SCHEDULE C: DISCHARGED FUEL DATA
C.1
Data on Permanently Discharged Fuel
The Form RW-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, there is a need to update all
previously submitted Form RW-859 survey data at the assembly level.
It is preferred that you submit assembly-specific data in either database or spreadsheet
format. You may use any readily-available database or spreadsheet. In lieu of submitting
these data in database or spreadsheet format you may complete Schedule C.1. Update all
previously submitted data and enter new data for assemblies discharged during the
reporting period.
A-3
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Provide the following for all permanently discharged fuel from this reactor:
Assembly
Identifier
Provide a unique identifier for each assembly. This identifier may be
assigned by the fuel vendor or by the site operator. 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.
Uranium
Content
Report initial uranium content of the fuel assembly to the nearest gram.
Report in kilograms of uranium (kg U).
Initial
Enrichment
Report the overall initial enrichment of the assembly to the nearest
hundredth of a percent.
Discharge
Burnup
Report the final discharge burnup of the assembly in MWDt/MTU.
Last Cycle
Number
Report cycle number for the final cycle of irradiation.
Last Cycle
Shutdown
Date
Report shutdown date for the final cycle of irradiation, regardless of when
the fuel assembly was removed from the core.
Fuel
Assembly
Type
Use the appropriate code from Appendix B. If there is no appropriate code
listed, contact the EIA for an appropriate fuel assembly type code.
Assembly
Status
Use the appropriate code from Appendix C. Note that only permanently
discharged assemblies are to be reported in this Schedule.
Storage
Location
Select the appropriate pool storage site or dry storage site identifier from
Appendix D.
C.2
Reinserted Fuel Data
Provide the assembly identifiers for all assemblies that had previously been reported as
permanently discharged (and in this pool at the end of the previous reporting period), but which
were 1) removed from this pool and, 2) reinserted in a reactor during this reporting period.
Assemblies that were discharged and subsequently reinserted within the current reporting period
should also be provided.
C.3
Projected Assembly Discharges
Projections of discharged assemblies shall be reported on a group basis, where each assembly
in the group has common characteristics. These characteristics include: Assembly Type;
Reactor/Cycle History; Initial Uranium Content (within 3 kgU for BWRs, 5 kgU for PWRs); Initial
Enrichment (within nearest tenth of a percent); and Estimated Final Burnup (within 5% of the
group average GWDt/MTU).
The current operating cycle number is 1 greater than the last historical cycle number reported in
Schedule B.3.
The group identifier is a combination of the cycle number and the number of unique groups in
the cycle, e.g., 01-1, 01-2, 11-1, etc.
C.4 through C.8
Special Fuel Forms
These Schedules are used to report data on special fuel forms including canisters and their
contents (Schedule C.4), uncanistered fuel rods and fuel pieces (Schedule C.5), nonstandard
fuel assemblies (Schedule C.6), failed fuel assemblies (Section C.7), and consolidated,
reconstituted, or reconstructed assemblies (Section C.8).
A-4
NUCLEAR FUEL DATA SURVEY
FORM RW-859
C.4
Canisters
In this Schedule, report all Canistered Material which is scheduled to be delivered to a Federal
repository. It covers all materials in canisters (e.g., failed and nonfailed fuel). A canister is
defined as the outermost container designed to confine waste that may be delivered to a Federal
repository (excluding transport casks). It may contain vitrified high-level waste, intact or failed
spent fuel assemblies, consolidated spent fuel rods, or spent fuel rod pieces. A canister may
also contain non-fuel components. Empty canisters should not be reported.
C.4.1 Canisters in Pool. Are there canisters in your pool planned for delivery to the Federal
repository? If the answer to this question is no, skip Schedules C.4.2 – C.4.4. If your answer is
yes, complete a separate Schedule C.4.2 – C.4.4 for each canister.
C.4.2 Canister Identifier should be a unique alphanumeric designator. Also provide
information on the canister shape, dimensions, and loaded weight.
C.4.3 Provide the information indicated. Checking more than one "Applicable Contents" item
is acceptable. If the canister contains fuel rod pieces, provide the information in terms of intact
rods, e.g., 0.5 rods, 2.3 rods, etc.
C.4.4 Provide a detailed description of the contents of each canister. Indicate which assembly
specific fuel rods came from and their initial loading weight and discharge burnup.
C.5
Uncanistered Fuel Rods and Pieces
Include in this schedule all materials that were not listed as canistered in Schedules C.4.1
through C.4.4. Indicate which assembly specific fuel rods came from and their initial loading
weight and discharge burnup.
C.6
Nonstandard Assemblies
Provide information on all assemblies classified as nonstandard. Nonstandard assemblies are
those that require special handling. If all assemblies at this facility are considered nonstandard
simply check the box.
C.7
Failed Assemblies
Provide information on all assemblies classified as failed. Failed assemblies are those that may
require special handling.
C.8
Consolidated/Reconstituted/Reconstructed Assemblies.
Provide the information indicated. Provide information on both the source assembly and the
current assembly.
SCHEDULE D: STORAGE FACILITY DATA
D.1
Complete name, title, address and telephone number of person who may be contacted
to verify the data given on this form or verify changes between updates of this form.
D.2
Storage Facility Information
Complete a Schedule D.1 for each spent fuel storage site, including pools and dry storage
facilities.
D.2.1 Storage Site Identifier -- Use the appropriate code from Appendix D in the Storage Site
Identifier column.
D.2.2 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 F).
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.
A-5
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Note in the Comments Schedule (Schedule F) if some of the storage capacity is unusable due to
mechanical/physical limitations.
D.2.3 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.
D.2.4 Shipments/Transfers of Discharged Fuel -- Report all shipments of fuel assemblies both
from this storage site to another storage site (pool or dry storage) and to this storage site from
another storage site since the end of the previous reporting period. Include all shipments or
transfers since the last reporting period.
D.2.5
Dry Storage
Complete Schedule D.2.5 if your company has implemented dry storage at your site.
Provide dry storage site identifier (Appendix D, "Reactor and Spent Fuel Storage Site
Identification Codes." If no code is listed for this site, assign the nearest pool identifier followed
by a "D").
Provide the information indicated, including the number of assemblies stored in each multielement canister/cask.
SCHEDULE E: NON-FUEL DATA
This Schedule should include all non-fuel hardware, non-fuel components, and other materials
that need to be repackaged. All materials not listed in Schedule C.4 should be included here.
Non-fuel components may be integral to an assembly (enter data in Schedule E.1), canistered
(enter data in Schedule E.2), separate from an assembly (enter data in Schedule E.3), or in dry
storage (enter data in Schedule E.4).
SCHEDULE F: COMMENTS
Comments on any item in Schedules A - E are to be recorded in Schedule F. Include the
Schedule/Sub-Schedule number to which each comment applies with each individual comment.
A-6
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX B – IDENTIFICATION OF FUEL TYPE CODES
The identification of Fuel Type Codes for your fuel is a three-step process (Steps 1, 2, & 3) or a two-step process
(Steps 1 & 4) described below:
Step 1: Using the following list of reactors, identify the Assembly Class for your reactor. Proceed to either Step 2
or Step 4 as indicated.
Table 1 Reactor Assembly Class List
Reactor Name
Assembly Class
Go to
Reactor Name
Assembly Class
Go to
Arkansas Nuclear 1
B&W 15X15
Step 2
Millstone 2
CE 14 X 14
Step 2
Arkansas Nuclear 2
CE 16 X 16
Step 2
Millstone 3
WE 17 X 17
Step 2
Beaver Valley 1, 2
WE 17 X 17
Step 2
Monticello
GE BWR/2,3
Step 2
Big Rock Point
BIG ROCK POINT
Step 4
Nine Mile Point 1
GE BWR/2,3
Step 2
Braidwood 1, 2
WE 17 X 17
Step 2
Nine Mile Point 2
GE BWR/4,5,6
Step 2
Browns Ferry 1, 2, 3
GE BWR/4,5,6
Step 2
North Anna 1, 2
WE 17 X 17
Step 2
Brunswick 1, 2
GE BWR/4,5,6
Step 2
Oconee 1, 2, 3
B&W 15X15
Step 2
Byron 1, 2
WE 17 X 17
Step 2
Oyster Creek
GE BWR/2,3
Step 2
Callaway
WE 17 X 17
Step 2
Palisades
PALISADES
Step 4
Calvert Cliffs 1, 2
CE 14 X 14
Step 2
Palo Verde 1, 2, 3
CE System 80
Step 2
Catawba 1, 2
WE 17 X 17
Step 2
Peach Bottom 2, 3
GE BWR/4,5,6
Step 2
Clinton 1
GE BWR/4,5,6
Step 2
Perry 1
GE BWR/4,5,6
Step 2
Columbia
GE BWR/4,5,6
Step 2
Pilgrim 1
GE BWR/2,3
Step 2
Comanche Peak 1, 2
WE 17 X 17
Step 2
Point Beach 1, 2
WE 14 X 14
Step 2
Cook 1
WE 15 X 15
Step 2
Prairie Island 1, 2
WE 14 X 14
Step 2
Cook 2
WE 17 X 17
Step 2
Quad Cities 1, 2
GE BWR/2,3
Step 2
Cooper Station
GE BWR/4,5,6
Step 2
Rancho Seco
B&W 15X15
Step 2
Crystal River 3
B&W 15X15
Step 2
River Bend 1
GE BWR/4,5,6
Step 2
Davis-Besse
B&W 15X15
Step 2
Robinson 2
WE 15 X 15
Step 2
Diablo Canyon 1, 2
WE 17 X 17
Step 2
Salem 1, 2
WE 17 X 17
Step 2
Dresden 1
DRESDEN 1
Step 4
San Onofre 1
SAN ONOFRE 1
Step 4
Dresden 2, 3
GE BWR/2,3
Step 2
San Onofre 2
CE 16 X 16
Step 2
Duane Arnold
GE BWR/4,5,6
Step 2
San Onofre 3
CE 16 X 16
Step 2
Enrico Fermi 2
GE BWR/4,5,6
Step 2
Seabrook
WE 17 X 17
Step 2
Farley 1, 2
WE 17 X 17
Step 2
Sequoyah 1, 2
WE 17 X 17
Step 2
FitzPatrick
GE BWR/4,5,6
Step 2
Shoreham
GE BWR/4,5,6
Step 2
Fort Calhoun
FORT CALHOUN
Step 2
South Texas 1, 2
SOUTH TEXAS
Step 2
Ginna
WE 14 X 14
Step 2
St. Lucie 1
CE 14 X 14
Step 2
Grand Gulf 1
GE BWR/4,5,6
Step 2
St. Lucie 2
ST. LUCIE 2
Step 2
B-1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Haddam Neck
HADDAM NECK
Step 4
Summer
WE 17 X 17
Step 2
Harris 1
WE 17 X 17
Step 2
Surry 1, 2
WE 15 X 15
Step 2
Hatch 1, 2
GE BWR/4,5,6
Step 2
Susquehanna 1, 2
GE BWR/4,5,6
Step 2
Hope Creek
GE BWR/4,5,6
Step 2
Three Mile Island 1
B&W 15X15
Step 2
Humboldt Bay
HUMBOLDT BAY
Step 4
Trojan
WE 17 X 17
Step 2
Indian Point 1
INDIAN POINT 1
Step 4
Turkey Point 3, 4
WE 15 X 15
Step 2
Indian Point 2, 3
WE 15 X 15
Step 2
Vermont Yankee
GE BWR/4,5,6
Step 2
Kewaunee
WE 14 X 14
Step 2
Vogtle 1, 2
WE 17 X 17
Step 2
LaCrosse
LACROSSE
Step 4
Waterford 3
CE 16 X 16
Step 2
LaSalle County 1, 2
GE BWR/4,5,6
Step 2
Watts Bar 1
WE 17 X 17
Step 2
Limerick 1, 2
GE BWR/4,5,6
Step 2
Wolf Creek 1
WE 17 X 17
Step 2
Maine Yankee
CE 14 X 14
Step 2
Yankee Rowe
YANKEE ROWE
Step 4
McGuire 1, 2
WE 17 X 17
Step 2
Zion 1, 2
WE 15 X 15
Step 2
Millstone 1
GE BWR/2,3
Step 2
B-2
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Step 2: The tables in Step 3 are based on the current vendor name. Use the following list of historical vendor
names to determine the appropriate Schedule of the fuel design tables to use in Step 3.
Table 2 Fuel Vendor List
Fuel Vendor (Original Name)
Short Name
Current Vendor Name
ABB CE
Westinghouse
ANF
Areva
AC
N/A
Areva
Areva
ABB Atom
Westinghouse
B&W
Areva
Combustion Engineering
CE
Westinghouse
Exxon Nuclear Corporation (EXA)
EX
Areva
Framatome
FR
Areva
GE Nuclear Energy
GE
Global Nuclear Fuel
General Atomics
GA
N/A
Global Nuclear Fuel
GNF
Global Nuclear Fuel
Gulf General Atomics
GGA
N/A
Gulf/United Nuclear Fuels
GULF
N/A
JN
Areva
NFS
N/A
Nuclear Materials and Equipment Corporation
NUMEC
N/A
Siemens Nuclear Corporation
Siemens
Areva
United Nuclear Corporation
UNC
N/A
Westinghouse Electric
WE
Westinghouse
ABB Combustion Engineering
Advanced Nuclear Fuel Corporation
Allis Chalmers
Areva
ASEA Brown Boveri (ABB) Atom
Babcock & Wilcox Company
Jersey Nuclear
Nuclear Fuel Services
B-3
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Step 3: Find the appropriate Schedule of Table 3 (in the Table Schedule Title) for the Current Vendor Name
(See Table 2) for the fuel assemblies in question. Use the Descriptions (See Table Below) to identify the Fuel
Design applicable to your assemblies. Use the individual tables to identify the fuel code for the assemblies.
Insert this code into the appropriate field in the RW-859 Nuclear Fuel Survey form.
Table 3.1 Areva (for Babcock & Wilcox plants)
All operating B&W plants are B&W 15 x 15 Assembly Class plants.
Fuel Design
Description
Fuel Code
Mark B2
Mark B2 fuel uses a corrugated flexible grid spacer and a zirconium dioxide solid
spacer between the fuel column and the fuel rod end plug.
B1515B2
Mark B3
Mark B3 characteristics are not well known.
B1515B3
Mark B4
Mark B4 fuel was the standard fuel from B&W for many years. These assemblies use
Inconel spacer grids.
B1515B4
Mark B4Z
Mark B4Z fuel has Mark B4 features with 6 Zircaloy grid spacers in the core zone
B1515B4Z
Mark B5
Mark B5 fuel has a redesigned upper end fitting, eliminates retainers for Burnable
Poison Rod Assembly holddown; and has a redesigned holddown spring made of
Inconel 718 rather than Inconel X-750.
B1515B5
Mark B5Z
Mark B5Z fuel features 6 Zircaloy grid spacers in the core zone in addition to Mark B5
features.
B1515B5Z
Mark B6
Mark B6 fuel features 6 Zircaloy grid spacers in the core zone and a skirtless,
removable upper end fitting.
B1515B6
Mark B7
Mark B7 fuel features, in addition to the Mark B6 features, include slightly longer fuel
rods and a shorter lower end fitting. These features increase the plenum volume and
fuel rod-to-nozzle gap and allow for increased discharge burnups.
B1515B7
Mark B8
Mark B8 fuel features a debris fretting resistant fuel rod design and includes Mark B7
fuel features.
B1515B8
Mark B9
Mark B9 fuel includes Mark B8 features plus slightly increased pellet diameter and
reduced stack length.
B1515B9
Mark B10
Mark B10 fuel includes Mark B9 features along with a redesigned upper end fitting (a
cruciform leaf-spring design replaces the helical holddown springs) and zone-loaded
fuel enrichment variations.
B1515B10
Mark B11
Mark B11 fuel utilizes a new alloy, M5, for the fuel rod cladding.
B1515B11
Mark B12
Mark B12 fuel utilizes the M5 alloy for fuel rod cladding and guide tubes; incorporates
the TRAPPER bottom nozzle, a fine mesh debris filter; and has a heavier uranium
loading.
B1515B12
Mark BEB
Mark BEB fuel was a Lead Test Assembly design used to test extended burnup
features, this fuel had a shorter active fuel length and was used only at Arkansas
Nuclear 1.
B1515BEB
Mark BGd
Mark BGd fuel utilized gadolinia in the fuel rods as a neutron absorber and apparently
had removable upper end fittings, the forerunner of the skirtless (Mark B6) upper end
fitting.
B1515BGD
Mark B
Mark B fuel is a generic designation. Should not be used unless the specific fuel
design cannot be determined.
B1515B
Mark BZ
Mark BZ fuel is a generic designation and is used for fuels with Zircaloy grid spacers,
which encompass Mark B4Z, B5Z, B6, B7 and B8 fuels. Should not be used unless
the specific fuel design cannot be determined.
B1515BZ
B-4
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Fuel Design
Mark C
Description
Fuel Code
Mark C Fuel uses a 17x17 fuel rod array, designed for use in B&W 17x17 Class
reactors. None of the reactors in this class (Bellefonte, WNP-1) were completed, but
a limited number of Mark C lead test assemblies were irradiated in B&W 15x15 Class
reactors.
B1717B
Table 3.2 Areva (for Combustion Engineering plants)
CE Reload Fuels – Reload fuel sold by ANF and their successors for CE power plants.
Assembly Class
Fuel Code
CE 14 x 14
C1414A
CE 16 x 16
C1616A
CE System 80
C8016A
Ft. Calhoun
XFC14A
St. Lucie
XSL16A
Table 3.3 Areva (for General Electric plants)
ANF – 7x7 fuel manufactured by Exxon Nuclear (and Advanced Nuclear Fuels). No water rods.
Assembly Class
Fuel Code
GE BWR/2,3
G2307A
GE BWR/4-6
G4607A
ANF – 8x8 fuel manufactured by Exxon Nuclear (and Advanced Nuclear Fuels). Uses one water rod.
Assembly Class
Fuel Code
GE BWR/2,3
G2308A
GE BWR/4-6
G4608A
ANF Prepressurized – 8x8 Fuel manufactured by Advanced Nuclear Fuels. Uses one water rod. Features
prepressurized fuel rods.
Assembly Class
Fuel Code
GE BWR/2,3
G2308AP
GE BWR/4-6
G4608AP
ANF 9-1 – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Uses one water rod.
Assembly Class
Fuel Code
GE BWR/2,3
G2309A
GE BWR/4-6
G4609A
ANF 9-2 – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Uses two water rods.
Assembly Class
Fuel Code
GE BWR/2,3
G2309A2
GE BWR/4-6
G4609A2
B-5
NUCLEAR FUEL DATA SURVEY
FORM RW-859
ANF 9-5 – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Uses five water rods.
Assembly Class
Fuel Code
GE BWR/2,3
G2309A5
GE BWR/4-6
G4609A5
ANF 9X – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Central water replaces 9 fuel rod
positions.
Assembly Class
Fuel Code
GE BWR/2,3
G2309A9X
GE BWR/4-6
G4609A9X
ANF IX – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Central water replaces 9 fuel rod
positions. Internal claddling liner of pure zirconium.
Assembly Class
Fuel Code
GE BWR/2,3
G2309AIX
GE BWR/4-6
G4609AIX
ANF IX+ – 9x9 fuel manufactured by Advanced Nuclear Fuels (and Siemens). Central water replaces 9 fuel rod
positions. Internal claddling liner of pure zirconium. High-performance thermal spacer grids.
Assembly Class
Fuel Code
GE BWR/2,3
G2309AX+
GE BWR/4-6
G4609AX+
Atrium – ATRIUMTM fuel is reload fuel for GE power plants. It is available in 9x9 and 10x10 rod arrays.
ATRIUM fuels are distinguished by an internal square water channel that displaces a 3x3 array of fuel rods; load
bearing support from tie rods (ATRIUM-9) or the water channel (ATRIUM-10); ULTRAFLOW grid spacers that
increase the achievable critical power level; cladding with or without a zirconium liner; and advanced fuel
channels.
Assembly Class
Array Size
Fuel Code
GE BWR/2,3
9x9
G2309ATR
GE BWR/2,3
10 x 10
G2310ATR
GE BWR/4-6
9x9
G4609ATR
GE BWR/4-6
10 x 10
G4610ATR
Table 3.4 Areva (for Westinghouse plants)
ANF Reload Fuel – Reload fuel manufactured by Siemens (and predecessor organizations) for Westinghouse
plants, prior to the creation of Areva.
Assembly Class
Fuel Code
WE 14 x 14
W1414A
WE 15 x 15
W1515A
WE 17 x 17
W1717A
South Texas
XST17A
B-6
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Top Rod Fuel – an ANF-manufactured fuel for WE 14 X 14 reactors with a longer, smaller diameter fuel rod than
ANF reload fuel.
Assembly Class
Fuel Code
WE 14 x 14
W1414ATR
Part Length Fuel – an ANF-manufactured fuel for WE 15 X 15 reactors. Bottom 42 inches of the fuel rods
contains stainless steel, rather than uranium to shield core support structure.
Assembly Class
Fuel Code
WE 15 x 15
W1515APL
Mark BW Reload Fuel – Reload fuel manufactured by B&W for Westinghouse plants, prior to the creation of
Areva.
Assembly Class
Fuel Code
WE 14 x 14
W1414B
WE 15 x 15
W1515B
WE 17 x 17
W1717B
South Texas
XST17B
Mark BW (M5) Reload Fuel – Reload fuel manufactured by Areva for Westinghouse plants. Mark BW (M5) fuel
uses the alloy M5 for fuel rod cladding.
Assembly Class
Fuel Code
WE 14 x 14
W1414BM5
WE 15 x 15
W1515BM5
WE 17 x 17
W1717BM5
South Texas
XST17BM5
HTP Fuel – High Thermal Performance (HTP) fuel from Framatome is designed for power plants built by
Westinghouse. HTP is distinguished by improved cladding materials (optimized Zircaloy and Duplex cladding);
HTP spacer grids that utilize flow channels to improve coolant mixing and enhanced fuel rod support to preclude
grid-to-rod fretting, intermediate flow mixing grids, and the FUELGUARDTM lower tie plate.
Assembly Class
Fuel Code
WE 14 x 14
W1414AHT
WE 15 x 15
W1515AHT
WE 17 x 17
W1717AHT
South Texas
XST17AHT
B-7
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Alliance – Alliance fuel from Areva is designed for WE 17 x 17 power plants. Alliance fuels are distinguished by
MONOBLOC™ guide thimbles for increased assembly stiffness and distortion resistance; M5™ cladding, guide
thimbles and grids for reduced corrosion, reduced growth and lower creep; high performance mixing grids with
wrap-around corner for ease of handling; and a TRAPPER™ bottom nozzle for superior debris protection.
Assembly Class
Fuel Code
WE 14 x 14
W1414ALL
WE 15 x 15
W1515ALL
WE 17 x 17
W1717ALL
South Texas
XST17ALL
Table 3.5 Global Nuclear Fuels (for General Electric plants)
GE-2 – GE-2 fuel was the original core fuel for most GE/BWR 2,3 Class reactors and for some BWR/4 plants.
GE-2 fuels have a 7x7 fuel rod array.
Assembly Class
Description
Fuel Code
GE BWR/2,3
0.570-inch-diameter fuel rod
G2307G2A
GE BWR/2,3
0.563-inch-diameter fuel rod
G2307G2B
GE BWR/4-6
G4607G2
GE-3 – GE-3 or “Improved” fuel introduced a hydrogen getter in the fuel rod plenum and thicker fuel rod cladding.
Active fuel lengths of 144” (GE-3a) and 146” (GE-3b) were used. GE-3 fuels have a 7x7 fuel rod array.
Assembly Class
Description
Fuel Code
GE BWR/2,3
G2307G3
GE BWR/4-6
144-inch active fuel length
G4607G3A
GE BWR/4-6
146-inch active fuel length
G4607G3B
GE-4 – GE-4 fuels were the original 8x8 fuel rod array and feature 63 fuel rods and a single “water rod.”
Assembly Class
Description
Fuel Code
GE BWR/2,3
G2308G4
GE BWR/4-6
144-inch active fuel length
G4608G4A
GE BWR/4-6
146-inch active fuel length
G4608G4B
Retrofit Fuel – GE-5, or “Retrofit” fuels used an 8x8 fuel rod array, with 62 fuels rods and 2 water rods. GE-5
fuels also introduced natural uranium axial blankets.
Assembly Class
Fuel Code
GE BWR/2,3
G2308G5
GE BWR/4-6
G4608G5
GE Prepressurized Fuel – Prepressurized fuel used an 8x8 fuel rod array and other GE-5 features. The fuel
rods were prepressurized to 3 Atmospheres to reduce fission gas release.
Assembly Class
Fuel Code
GE BWR/2,3
G2308GP
GE BWR/4-6
G4608GP
B-8
NUCLEAR FUEL DATA SURVEY
FORM RW-859
GE Barrier Fuel – Barrier fuel used an 8x8 fuel rod array and other “prepressurized” fuel features. It introduced
a pure zirconium "barrier" on inside of cladding to reduce pellet-clad interactions.
Assembly Class
Fuel Code
GE BWR/2,3
G2308GB
GE BWR/4-6
G4608GB
GE-8 – GE-8 fuel used an 8x8 fuel rod array and increased the number of water rods from 2 to 4 and increased
the fuel rod prepressurization to 5 Atmospheres. GE-8 fuel has the features of Barrier fuel and added burnable
absorbers and axially zoned enrichment.
Assembly Class
Description
Fuel Code
GE BWR/2,3
2 water rods
G2308G8A
GE BWR/2,3
4 water rods
G2308G8B
GE BWR/4-6
2 water rods
G4608G8A
GE BWR/4-6
4 water rods
G4608G8B
GE-9 – GE-9 fuel used an 8x8 fuel rod array and has the features of GE-8 fuel. GE-9 fuel introduced a single
large diameter water rod that displaces 4 fuel rod positions and a ferule-type spacer grid.
Assembly Class
Fuel Code
GE BWR/2,3
G2308G9
GE BWR/4-6
G4608G9
GE-10 – GE-10 fuel used an 8x8 fuel rod array and has the major features of GE-9 fuel. It introduced a new fuel
channel, which is 100 mils thick at the corners and 65 mils thick on the sides. This new channel design reduces
the parasitic material in core and uses flow directors on the inside of the channel to redirect the flow of water
away from the channel wall and toward the center of the fuel bundle.
Assembly Class
Fuel Code
GE BWR/2,3
G2308G10
GE BWR/4-6
G4608G10
GE-11 – GE-11 fuel uses a 9x9 fuel rod array. It features a ferule-type space grid and two medium diameter
water rods that replace seven fuel rod locations. GE-11 fuel also uses eight part-length fuel rods, which extend
from the bottom of the assembly to the fifth spacer grid.
Assembly Class
Fuel Code
GE BWR/2,3
G2309G11
GE BWR/4-6
G4609G11
GE-12 – GE-12 fuel uses a 10x10 fuel rod array. It features a ferule-type space grid and two medium diameter
water rods that replace seven fuel rod locations. GE-12 fuel also uses eight part-length fuel rods, which extend
from the bottom of the assembly to the fifth spacer grid.
Assembly Class
Fuel Code
GE BWR/2,3
G2310G12
GE BWR/4-6
G4610G12
B-9
NUCLEAR FUEL DATA SURVEY
FORM RW-859
GE-13 – GE-13 fuel uses a 9x9 fuel rod array. It features a ferule-type spacer grid and two medium diameter
water rods that replace seven fuel rod locations. It offers an increased bundle weight relative to GE-11 fuel and
a choice of active fuel lengths.
Assembly Class
Fuel Code
GE BWR/2,3
G2309G13
GE BWR/4-6
G4609G13
GE-14 – GE-14 fuel uses a 10x10 fuel rod array. It features a ferule-type spacer grid and two medium diameter
water rods that replace seven fuel rod locations. It offers an increased bundle weight relative to GE-12 fuel and
a choice of active fuel lengths.
Assembly Class
Fuel Code
GE BWR/2,3
G2310G14
GE BWR/4-6
G4610G14
Table 3.6 Westinghouse (for Babcock & Wilcox reactors)
B&W Reload Fuels – Reload fuel sold by WE for B&W power plants.
Assembly Class
Fuel Code
BW 15 x 15
B1515W
Table 3.7 Westinghouse (for Combustion Engineering reactors)
CE Original Fuels – Original and reload fuel sold by CE for their power plants.
Assembly Class
Fuel Code
CE 14 x 14
C1414C
CE 16 x 16
C1616C
CE System 80
C8016C
Ft. Calhoun
XFC14C
St. Lucie
XSL16C
B-10
NUCLEAR FUEL DATA SURVEY
FORM RW-859
WE Reload Fuels – Reload fuel sold by WE for CE power plants (prior to their purchase of ABB CE).
Assembly Class
Fuel Code
CE 14 x 14
C1414W
CE 16 x 16
C1616W
CE System 80
C8016W
Ft. Calhoun
XFC14W
St. Lucie
XSL16W
CE Turbo – CE Turbo fuels are reload fuels sold by Westinghouse and used in power plants built by Combustion
Engineering. Turbo fuels are distinguished by erbium integral burnable absorbers, an advanced fuel pellet
design, axial blankets, Zircaloy mixing grids, and a Guardian debris-resistant grid.
Assembly Class
Fuel Code
CE 14 x 14
C1414WCT
CE 16 x 16
C1616WCT
CE System 80
C8016WCT
Ft. Calhoun
XFC14WCT
St. Lucie
XSL16WCT
Table 3.8 Westinghouse (for General Electric plants)
QUAD+ Design – A licensed version of the ABB Atom water cross fuel – 4 individual 4 x 4 arrays are separated
by a water cross in a single assembly.
Assembly Class
Fuel Code
GE BWR/4-6
G4608W
CE ABB Atom Design – A 10 x 10 version of the ABB Atom water cross fuel – 4 individual 5 x 5 arrays are
separated by a water cross in a single assembly.
Assembly Class
Fuel Code
GE BWR/4-6
G4610C
SVEA 96 Designs – Westinghouse SVEA 96 fuel designs are used in GE BWR plants. Each fuel assembly has
four 5x5 sub-bundles separated by a double-wall structure that forms an internal water cross. Each sub-bundle
consists of 24 fuel rods and a single water rod.
Assembly Class
Fuel Code
GE BWR/2,3
G2310W
GE BWR/4-6
G4610W
B-11
NUCLEAR FUEL DATA SURVEY
FORM RW-859
SVEA 96 Optima Designs – Westinghouse SVEA 96 Optima fuel designs are used in GE BWR plants. Each
fuel assembly has four 5x5 sub-bundles separated by a double-wall structure that forms an internal water cross.
Each sub-bundle consists of 24 fuel rods and a single water rod. Optima fuel use a larger diameter fuel rod and
pellet and have twelve part-length fuel rods.
Assembly Class
Fuel Code
GE BWR/2,3
G2310WO
GE BWR/4-6
G4610WO
Table 3.9 Westinghouse (for Westinghouse plants)
WE Standard – Standard fuel from Westinghouse for original WE 14x14 and WE 15x15 Class reactors.
Standard fuel used stainless steel guide tubes.
Assembly Class
Fuel Code
WE 14 x 14
W1414W
WE 15 x 15
W1515W
LOPAR – “Low Parasitic” or LOPAR fuel for WE 14x14, WE 15x15, and WE 17x17 Class reactors. LOPAR uses
Zircaloy for guide tubes. In WE 17x17 reactors, LOPAR fuel is sometimes referred to as Standard fuel.
Assembly Class
Fuel Code
WE 14 x 14
W1414WL
WE 15 x 15
W1515WL
WE 17 x 17
W1717WL
South Texas
XST17WL
OFA – “Optimized Fuel Assemblies” or OFA fuel uses Zircaloy for spacer grids and has a smaller fuel pellet and
fuel rod diameter. As a result, the initial U loading is lower than for Standard and LOPAR fuels.
Assembly Class
Fuel Code
WE 14 x 14
W1414WO
WE 15 x 15
W1515WO
WE 17 x 17
W1717WO
South Texas
XST17WO
Vantage 5 – Vantage 5 fuel from Westinghouse offers a set of 5 optional features. These features include
integral zirconium diboride neutron absorbers, natural uranium axial blankets, intermediated flow mixers,
removable top nozzle, and increased discharged burnup. Vantage 5 fuels use the Zircaloy spacers and the
smaller fuel pellet and fuel rod found on OFA fuels.
Assembly Class
Fuel Code
WE 14 x 14
W1414WV5
WE 15 x 15
W1515WV5
WE 17 x 17
W1717WV5
South Texas
XST17WV5
B-12
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Vantage 5 Hybrid – Vantage 5 Hybrid fuel from Westinghouse combines the advanced neutronic characteristics
of Vantage 5 fuel with the larger diameter fuel rod associated with LOPAR fuel. This results in an increased
quantity of uranium in the assembly.
Assembly Class
Fuel Code
WE 14 x 14
W1414WV5H
WE 15 x 15
W1515WV5H
WE 17 x 17
W1717WV5H
South Texas
XST17WV5H
Vantage 5+ – Vantage 5+ fuel from Westinghouse combines ZIRLO (a zirconium-niobium alloy) cladding with
the advanced neutronic characteristics of Vantage 5 fuel.
Assembly Class
Fuel Code
WE 14 x 14
W1414WV5+
WE 15 x 15
W1515WV5+
WE 17 x 17
W1717WV5+
South Texas
XST17WV5+
Performance+ – Performance+ fuel is designed for power plants built by Westinghouse. Performance+ Fuel is
distinguished by a removable top nozzle with easy aligning and engaging features; axial blankets; enriched
annular axial blankets; intermediate flow mixer grids to enhance departure-from-nucleate-boiling margins; and
extensive use of ZIRLO™ in cladding, instrumentation and guide thimbles, structural girds and intermediate flow
mixers; zirconium diboride integral burnable absorbers; mechanical modifications that enhance fuel performance
at extended burnups; and triple protection against debris-induced fuel rod damage.
Assembly Class
Fuel Code
WE 14 x 14
W1414WP+
WE 15 x 15
W1515WP+
WE 17 x 17
W1717WP+
South Texas
XST17WP+
Robust Fuel Assemblies – Robust Fuel Assemblies (RFA) are designed for power plants built by
Westinghouse. The features of the RFA include the use of gadolinia as a neutron absorber and an inconel
protective grid at the bottom of the fuel assembly.
Assembly Class
Fuel Code
WE 14 x 14
W1414WR
WE 15 x 15
W1515WR
WE 17 x 17
W1717WR
South Texas
XST17WR
B-13
NUCLEAR FUEL DATA SURVEY
FORM RW-859
RFA 2 – Robust Fuel Assemblies - 2 are designed for power plants built by Westinghouse. In addition to RFA
features, the RFA-2 grid design provides improved resistance to fuel rod fretting.
Assembly Class
Fuel Code
WE 14 x 14
W1414WR2
WE 15 x 15
W1515WR2
WE 17 x 17
W1717WR2
South Texas
XST17WR2
B-14
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Step 4: For single-reactor assembly classes, find the appropriate Schedule in the following table. Use the
descriptions to identify the fuel codes for the assemblies and input this code into the appropriate field in the RW859 Nuclear Fuel Survey form.
Table 4 Single Reactor Assembly Class List
Assembly Class
Description
Fuel Code
BIG ROCK POINT
Advanced Nuclear Fuel-manufactured 9 x 9 fuel
XBR09A
Advanced Nuclear Fuel-manufactured 11 x 11 fuel
XBR11A
GE-manufactured 7 x 7 fuel (center melt fuel)
XBR07G
GE-manufactured 8 x 8 fuel (center melt fuel)
XBR08G
GE-manufactured 9 x 9 fuel; includes E, EG, F, MEG, and PEG fuels
XBR09G
GE-manufactured 11 x 11 fuel; includes B, C, D1 and D2 fuels.
XBR11G
Nuclear Fuel Services-manufactured 11 x 11 fuel
XBR11N
DRESDEN 1
Advanced Nuclear Fuel-manufactured 6 x 6 fuel
XDR06A
GE-manufactured 6 x 6 fuel (Type I)
XDR06G
GE-manufactured 6 x 6 fuel (Type III-B), erbium oxide burnable absorber
XDR06G3B
GE-manufactured 6 x 6 fuel (Type III-F), nonfueled gadolinia burnable absorber rod
XDR06G3F
GE-manufactured 6 x 6 fuel (Type V), gadolinia burnable absorber in selected fuel rods
XDR06G5
GE-manufactured 7 x 7 fuel (stainless steel clad)
XDR07G
GE-manufactured 7 x 7 prototype fuel (SA-1)
XDR07GSA1
GE-manufactured 8 x 8 prototype fuel (PF)
XDR08G
United Nuclear-manufactured 6 x 6 fuel
XDR06U
HUMBOLDT BAY
Advanced Nuclear Fuel-manufactured 6 x 6 fuel
XHB06A
GE-manufactured 6 x 6 fuel
XHB06G
GE-manufactured 7 x 7 fuel (Type I – stainless steel clad)
XHB07G
GE-manufactured 7 x 7 fuel (Type II – Zircaloy clad)
XHB07G2
HADDAM NECK
B&W-manufactured 15 x 15 fuel (stainless steel clad)
XHN15BS
B&W-manufactured 15 x 15 fuel (Zircaloy clad)
XHN15BZ
GULF-manufactured 15 x 15 fuel (stainless steel clad)
XNH15HS
GULF-manufactured 15 x 15 fuel (Zircaloy clad)
XNH15HZ
NUMEC-manufactured 15 x 15 fuel (stainless steel clad)
XNH15MS
NUMEC-manufactured 15 x 15 fuel (Zircaloy clad)
XNH15MZ
WE-manufactured 15 x 15 fuel
XHN15W
B-15
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Assembly Class
Description
Fuel Code
INDIAN POINT 1
WE-manufactured 13 x 14 fuel (non-square array)
XIP14B
B&W-manufactured 14 x 15 fuel (non-square array)
XIP14W
LACROSSE
Allis Chalmers-manufactured 10 x 10 fuel
XLC10L
Advanced Nuclear Fuel-manufactured 10 x 10 fuel
XLC10A
PALISADES
Advanced Nuclear Fuel-manufactured 15 x 15 fuel
XPA15A
Combustion Engineering-manufactured 15 x 15 fuel
XPA15C
SAN ONOFRE 1
Westinghouse-manufactured 14 x 14 fuel (stainless steel clad)
XSO14W
Westinghouse-manufactured 14 x 14 fuel (Zircaloy clad)
XSO14WZ
YANKEE ROWE
Advanced Nuclear Fuel-manufactured 15 x 16 fuel (non-square array)
XYR16A
Combustion Engineering-manufactured 15 x 16 fuel (non-square array)
XYR16C
UNC-manufactured 15 x 16 fuel (non-square array)
XYR16U
Westinghouse-manufactured 17 x 18 fuel (non-square array)
XYR18W
B-16
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX C – ASSEMBLY STATUS CODES
Status Code
Description
Standard intact assembly - blank or no code - This is the default.
N
Non-standard intact assembly
F
Failed assembly with cladding damage or mechanical damage (not canistered)
C
Canistered assembly
R
Canistered fuel rods
P
Canistered fuel debris (pieces)
B
Fuel in a basket
O
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 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 Schedule*
6 inches x 6 inches
9 inches x 9 inches
*The cross Schedule 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.
C-1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX D – REACTOR AND SPENT FUEL STORAGE SITE IDENTIFICATION CODES
Reactor
ID
Pool
ID
Dresden - Unit 2
1006
1006
Dresden - Unit 3
1007
1007
Dresden (ISFSI)
-
1005D
Reactor
ID
Pool
ID
Arkansas Nuclear One - Unit 1
0401
0401
Arkansas Nuclear One - Unit 2
0402
0402
Arkansas Nuclear One (ISFSI)
-
0401D
Beaver Valley - Unit 1
1601
1601
Duane Arnold
Beaver Valley - Unit 2
1602
1602
Duane Arnold (ISFSI)
Bellefonte - Unit 1
4801
4801
Bellefonte - Unit 2
4802
Big Rock Point
Storage Location
Big Rock Point (ISFSI)
Storage Location
Note
DC
2401
2401
-
2401D
Enrico Fermi 2
1402
1402
4802
Farley - Unit 1
0101
0101
1201
1201
Farley - Unit 2
0102
0102
3901
3901
-
3901D
-
1201D
DC
Fitzpatrick
Braidwood - Unit 1
1001
1001
CP
Fitzpatrick (ISFSI)
Braidwood - Unit 2
1002
1001
CP
Fort Calhoun
3401
3401
Browns Ferry - Unit 1
4803
4803
TC
Fort St. Vrain
4101
4101
Browns Ferry - Unit 2
4804
4803
TC
Fort St. Vrain (ISFSI)
-
4101D
Browns Ferry - Unit 3
4805
4805
GE Morris
-
6601
Brunswick - Unit 1
0701
0701
GE Vallecitos
-
6201
Brunswick - Unit 2
0702
0702
Ginna
4401
4401
Byron - Unit 1
1003
1003
CP
Grand Gulf
2901
2901
Byron - Unit 2
1004
1003
CP
H. B. Robinson
0705
0705
Callaway
5101
5101
Calvert Cliffs - Unit 1
0501
0501
TC
Haddam Neck
Calvert Cliffs - Unit 2
0502
0501
TC
Haddam Neck (ISFSI)
Calvert Cliffs (ISFSI)
-
0501D
DC
1501
Catawba - Unit 1
H. B. Robinson (ISFSI)
-
0705D
5701
5701
-
5701D
Harris
0703
0703
1501
Hatch - Unit 1
2001
2001
Note
DC
DC
DC
DC
DC
DC
TC
Catawba - Unit 2
1502
1502
Hatch - Unit 2
2002
2001
TC
Clinton - Unit 1
2301
2301
Hatch (ISFSI)
-
2001D
DC
Columbia
5302
5302
Hope Creek
4201
4201
-
5302D
DC
Humboldt Bay
3503
3503
Comanche Peak - Unit 1
4901
4901
TC
Idaho National Laboratory
-
7002
Comanche Peak - Unit 2
4902
4901
TC
Indian Point - Unit 1
1101
1101
Cook - Unit 1
5801
5801
CP
Indian Point - Unit 2
1102
1102
Cook - Unit 2
5802
5801
CP
Indian Point - Unit 3
3902
3902
Cooper Station
3001
3001
Kewaunee
5501
5501
Columbia (ISFSI)
Crystal River 3
1701
1701
Lacrosse
1301
1301
Davis-Besse
5001
5001
LaSalle County - Unit 1
1008
1008
TC
-
5001D
LaSalle County - Unit 2
1009
1008
TC
Diablo Canyon - Unit 1
3501
3501
Limerick - Unit 1
3701
3701
TC
Diablo Canyon - Unit 2
3502
3502
Limerick - Unit 2
3702
3701
TC
-
3501D
Maine Yankee
2801
2801
1005
1005
-
2801D
Davis-Besse (ISFSI)
Diablo Canyon (ISFSI)
Dresden - Unit 1
DC
DC
Maine Yankee (ISFSI)
DC
D-1
NUCLEAR FUEL DATA SURVEY
FORM RW-859
Reactor
ID
Pool
ID
McGuire - Unit 1
1504
1504
McGuire - Unit 2
1505
1505
McGuire (ISFSI)
-
1504D
Storage Location
Reactor
ID
Pool
ID
Salem - Unit 1
4202
4202
Salem - Unit 2
4203
4203
San Onofre - Unit 1
4701
4701
4702
4702
Note
DC
Storage Location
Note
Millstone - Unit 1
3201
3201
San Onofre - Unit 2
Millstone - Unit 2
3202
3202
San Onofre - Unit 3
4703
4703
Millstone - Unit 3
3203
3203
San Onofre (ISFSI)
-
4701D
Monticello
3301
3301
Seabrook
5901
5901
Nine Mile Point - Unit 1
3101
3101
Sequoyah - Unit 1
4808
4808
CP
Sequoyah - Unit 2
4809
4808
CP
Sequoyah (ISFSI)
-
4808D
Shoreham
2601
2601
South Texas Project - Unit 1
2201
2201
South Texas Project - Unit 2
2202
2202
St Lucie - Unit 1
1801
1801
St Lucie - Unit 2
1802
1802
Summer
4601
4601
Surry - Unit 1
5203
5203
CP
Surry - Unit 2
5204
5203
CP
Surry (ISFSI)
-
5203D
DC
Susquehanna - Unit 1
3601
3601
TC
Susquehanna - Unit 2
3602
3601
TC
DC
Nine Mile Point - Unit 2
3102
3102
North Anna - Unit 1
5201
5201
CP
North Anna - Unit 2
5202
5201
CP
North Anna (ISFSI)
-
5201D
DC
Oconee - Unit 1
1506
1506
CP
Oconee - Unit 2
1507
1506
CP
Oconee - Unit 3
1508
1508
Oconee (ISFSI)
-
1506D
1903
1903
Oyster Creek
Oyster Creek (ISFSI)
-
1903D
1204
1204
-
1204D
Palo Verde - Unit 1
0301
0301
Palo Verde - Unit 2
0302
0302
Palisades
Palisades (ISFSI)
Palo Verde - Unit 3
0303
0303
Palo Verde (ISFSI)
-
0303D
Peach Bottom - Unit 2
3704
3704
Peach Bottom - Unit 3
3705
3705
Peach Bottom (ISFSI)
-
3704D
DC
DC
DC
Susquehanna (ISFSI)
DC
Perry - Unit 1
0901
0901
Pilgrim - Unit 1
0601
0601
Point Beach - Unit 1
5401
5401
CP
Point Beach - Unit 2
5402
5401
CP
Point Beach (ISFSI)
-
5401D
DC
Prairie Island - Unit 1
3302
3302
CP
Prairie Island - Unit 2
3303
3302
CP
Prairie Island (ISFSI)
-
3302D
DC
Quad Cities - Unit 1
1010
1010
TC
Quad Cities - Unit 2
1011
1010
TC
Rancho Seco
Rancho Seco (ISFSI)
River Bend
4501
4501
-
4501D
2101
2101
-
3601D
Three Mile Island - Unit 1
1901
1901
Trojan
3801
3801
-
3801D
Turkey Point - Unit 3
1803
1803
Turkey Point - Unit 4
1804
1804
Vermont Yankee
6001
6001
Vogtle - Unit 1
2003
2003
TC
Vogtle - Unit 2
2004
2003
TC
-
7007
Trojan (ISFSI)
DC
DC
Washington Hanford
DC
Waterford 3
2701
2701
Watts Bar - Unit 1
4810
4810
CP
Watts Bar - Unit 2
4811
4810
CP
Wolf Creek
2501
2501
Yankee Rowe
5601
5601
Yankee Rowe (ISFSI)
-
5601D
DC
Zion - Unit 1
1012
1012
CP
Zion - Unit 2
1013
1012
CP
DC
D-2
NUCLEAR FUEL DATA SURVEY
FORM RW-859
TC:
Transfer Canal
CP:
Common Pool Serving Two or More Reactors
DC:
Dry Storage Site
ISFSI: Independent Spent Fuel Storage Installation
E-2
NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX E – GLOSSARY OF TERMS
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 must be consistent with other
submissions to the DOE/NRC, i.e., Annex B, previous Form RW-859 and DOE/NRC Form 741.
Assembly Type: Each assembly is characterized by a fabricator, rod-array size, and model type. An eightdigit assembly type code is assigned to each assembly type based on certain distinguishing characteristics,
such as the number of rods per assembly, fuel rod diameter, cladding type, materials used in fabrication, and
other design features (See Appendix B, “Identification of Fuel Type Codes.”)
Average Assembly Weight: Average weight in kilograms (kg) of uranium of fresh fuel assemblies in a batch
before they are initially inserted into the reactor core. To be included in a batch the initial uranium content of
each assembly must be within 3 kg of the average weight (BWR assemblies) and within 5 kg of the average
weight (PWR assemblies).
Basket: An open container into which fuel and/or non-fuel components including rods, Schedules of rods,
garbage, debris, etc., are placed.
Burnup: Amount of thermal energy generated per unit mass of fuel, measured in units of gigawattdays
thermal per initial metric ton of uranium (MWDt/MTU), rounded to the nearest gigawatt day.
Canister: A canister is defined as any container designed to confine waste that may be delivered to a
Federal repository .
Cask: A shielded container licensed by the NRC for shipping or storing canistered or uncanistered spent
nuclear fuel and/or canistered high-level waste.
Current Installed Capacity: Total number of assembly storage slots in the spent nuclear fuel pool. Both
occupied and unoccupied slots are included in the current capacity.
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 startup of the reactor following the subsequent refueling.
Cycle/Reactor History: A group of assemblies that have been irradiated in the same cycles in an individual
reactor and are said to have the same cycle/reactor history.
Defective or Failed Assembly: Describes a fuel assembly that will not fit into a spent fuel rack, cannot be
lifted normally, or has already been canistered. An assembly is classified as defective if it contains any fuel
rods having known or suspected cladding defects greater than pin holes or hairline cracks that would require
canning for shipment under the NRC Director's Decision, DD-84-9, April 1984.
Effective Full-Power Days: The number of effective full power days produced by a unit is a measure of the
unit's energy generation. It is determined using the following ratio:
Heat generation (planned or actual) in megawatt-Days thermal (MWDt)
EFPD =
Licensed thermal power in megawatts thermal (MWt)
Group: A group is a logical grouping of assemblies with similar characteristics. All assemblies in a group
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 type.
Initial Enrichment: Average 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.
Initial Loading Weight: Average weight in kilograms (kg) of uranium of fresh fuel assemblies in a batch
before they are inserted into the reactor core.
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NUCLEAR FUEL DATA SURVEY
FORM RW-859
NRC Licensed Site Capacity: Number of assemblies for which the site is currently licensed to store.
Non-fuel Components: Components, which are not associated with a particular fuel. These include, but are
not limited to, control spiders, burnable poison rod assemblies, control rod elements, thimble plugs, fission
chambers, primary and secondary neutron sources, and BWR channels.
One-Time Fee: As defined in Article VIII of 10 CFR 961 (Schedule A.2.), the fee assessed a nuclear site
operator for spent nuclear fuel (SNF) or solidified high-level radioactive waste derived from SNF, which was
used to generate electricity in a civilian nuclear power reactor prior to April 7, 1983; and which is assessed by
applying industry-wide average dollar per kilogram charges to four distinct ranges of fuel burnup so that
equivalent to an industry-wide average charge of 1.0 mill per kilowatt-hour.
Permanently Discharged Fuel: Spent nuclear fuel for which there are no plans for reinsertion in the reactor
core.
Pool Site: One or more spent fuel storage pools, which have a single cask loading area. Dry cask storage
areas are considered separate sites.
Reconstituted Fuel: Spent nuclear fuel, which has had a defective rod, removed and replaced with another
rod. The recipient fuel assembly is intended to be reinserted into a subsequent fuel cycle. The replacement
rod may be a blank, made of natural uranium, or a rod removed from a donor assembly.
Reinsertion: Reinsertion is the process of putting nuclear fuel that has been irradiated and then removed
from a reactor, back into a reactor for further irradiation. Reinserted assemblies are assemblies that have
been irradiated in a cycle, were not in the core in the prior cycle (cycle N), and which are in the core in the
current cycle (cycle N+1).
Shutdown Date: Month and year of shutdown for fuel discharge and refueling. The date should be the point
at which the reactor became subcritical.
Slot: A physical position in a rack in a storage pool, which is intended to be occupied by an intact assembly
or equivalent (that is, a canister or an assembly skeleton).
Spent Fuel Disassembly 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, under which the
DOE will make available nuclear waste disposal services to those owners and generators.
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 which you have definite plans to irradiate in a subsequent fuel cycle.
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NUCLEAR FUEL DATA SURVEY
FORM RW-859
APPENDIX F – FORM RW-859 DATA COLLECTION SYSTEM INSTRUCTIONS
The Form RW-859 Data Collection Software System will be modified prior to the next data
collection to reflect changes made to the survey form. These instructions will be modified at that
time.
Getting Started
Version 2.2.1 of the Form RW-859 Data Collection System is for use with Microsoft Access 97. Version
2.2.2 is for use with Microsoft Access 2000 or 2002/XP. If you require a different version of the system,
contact EIA.
Insert the Form RW-859 CD into your CD Drive. Using the Windows Explorer or the My Computer icon, open
the CD. Follow the instructions on the computer screen to install the software on your desktop. An 859 icon
will appear on your desktop. Click on this icon to start the system.
When you reach the startup screen, you will notice that there are 3 buttons: NEXT, REPORT and EXIT. Use
the NEXT button to bring up the system and enter data. Use the REPORT screen to print data. Use the EXIT
key for closing your session.
Entering Data
Select a reactor from the drop-down menu. Click on the NEXT button. Once you have clicked on the NEXT
button, you will see Schedule 1. Use the tabs at the top of the screen to move from Schedule to Schedule.
Observe that there are multiple scroll bars, one or more on the inside and one on the outside. The inside
scroll bars are for moving around within that specific form Schedule or subSchedule. The outside bar is for
scrolling from top to bottom of a Schedule.
Field shaded yellow represent primary keys within the system. You should enter data in all fields shaded
yellow.
At any time if you enter data incorrectly, you may hit the ESC key and your last entry will automatically be
undone. If you receive an error message you may also hit the ESC key to undo your last entry as well. If you
get a “Run Time” error you must EXIT the system then reenter before entering additional data.
Any time you wish to leave the current screen and return to the startup screen, click the EXIT button.
Printing Data
Click on the EXIT button from any Schedule to return to the main screen. Select a reactor from the dropdown menu.
Once you have clicked the REPORT button, click the drop-down menu to select which Schedule you wish to
print and then click the PRINT button. At any time you wish to return to the startup screen, click the CLOSE
button.
Various Functions
Once within the Form RW-859 Data Collection System, there are a variety of ways you may manipulate your
data:
Delete Record. There are a number of options for deleting a record. You may highlight a row (a
black arrow will appear to the left of the row). Pressing DELETE while this arrow is highlighted will
delete the record. You may tab across a row, deleting each entry in that row. This option will leave a
blank row. At the top of your computer screen, there is an EDIT button. Click on it and a drop-down
menu will provide an option to DELETE RECORD. In certain Schedules, a DELETE button has been
added. For example the DELETE CANISTER button in Schedule 4.6 will delete that canister and its
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NUCLEAR FUEL DATA SURVEY
FORM RW-859
contents.
Insert Record. You may insert a record in a number of ways. Click on the Microsoft Access arrow
on the Record line at the bottom of the screen. This will allow you to enter a new record. Click the
INSERT button at the top of the screen and a drop-down menu provides an option to INSERT NEW
RECORD. In some Schedules an ADD button has been added. For example the ADD CANISTER
button in Schedule 4.6 will allow you to enter an additional canister. Note that when you insert a
new record into a data table, that entry will automatically be inserted at the bottom of the table.
Sorting. Microsoft Access does not provide for an easy way to sort data. Based on comments
provided by users on earlier versions of the Form RW-859 survey, the sort sequence for individual
tables has been determined. Schedule 3, which contains detailed assembly-level data, is sorted by
assembly identifier. In all other Schedules, the data appears in the order entered.
Instructions corresponding to individual Schedules of the survey form have been added to the system. Click
on the INSTRUCTIONS button within each Schedule to display these instructions. To close the
INSTRUCTIONS screen click on OK or hit the SPACE bar. To access the footnotes to Schedule 3, click on
the FOOTNOTES button.
Comments pertaining to data in individual Schedules of the survey form should be entered in Schedule 7.
You may access the Comments Schedule either by clicking on the Comments tab at the top of the screen or
by clicking on the COMMENTS button from each Schedule of the form. The RETURN button will return you
to the Schedule of the form you were working on when you exited to enter a comment.
Miscellaneous
Instructions pertaining to each Schedule of the survey form:
Schedule A – Site Operator Data
To be developed after the Form RW-859 Data Collection Software System is modified.
Schedule B - Reactor Data
To be developed after the Form RW-859 Data Collection Software System is modified.
Schedule C - Discharged Fuel Data
To be developed after the Form RW-859 Data Collection Software System is modified.
Schedule D - Storage Facility Data
To be developed after the Form RW-859 Data Collection Software System is modified.
Schedule E - Non-Fuel Data
To be developed after the Form RW-859 Data Collection Software System is modified.
Schedule F - Comments
To be developed after the Form RW-859 Data Collection Software System is modified.
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| File Type | application/pdf |
| File Title | RW-859 Revised (10/2001) |
| Author | Jaynie Moore |
| File Modified | 2006-09-11 |
| File Created | 2006-09-11 |