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pdfINSTRUCTIONS FOR COMPLETING ANNEX B TO
STANDARD REMITTANCE ADVICE FOR PAYMENT OF FEES
Section 1.0 Identification Information
1.1 Utility name, address, and ID number. The ID number comes from Table 1 of these instructions.
1.2 Person to be contacted for clarification of information
provided in this annex.
1.3 Reactor Name. Enter the name of the reactor
covered in this annex. Only one reactor may be
covered in this annex.
1.4 Assigned Reactor ID. Enter the two digit code to
identify this reactor unit. See Table 1 at the end of
these instructions.
1.5 Self-explanatory
1.6 Self-explanatory
Section 2.0 Discharged Nuclear Fuel Fee Calculation
2.1 Initial loading (kgU). For discharged nuclear fuel.
This includes all fuel assemblies not in the reactor
core at midnight between April 6/7, 1983. The entry
in the first column should be the sum of the initial
loading masses (in kilograms of Uranium) of assemblies which, at midnight between April 6/7, 1983,
discharge, had burnup from 0 to 5000 Megawatt
Days Thermal per Metric Ton of Uranium (MWDT/
MTU). Entries for the other columns are the sums of
initial loading masses for assemblies with higher
burnup on that date.
2.2 Fee rate (preentered).
2.3 Fee (dollars). The product of initial loading (2.1.)
and the fee rate (2.2.).
2.4 Total Fee (dollars). The total fee due for discharged
nuclear fuel is the sum of the four burnup category
fee figures (2.2.).
Section 3.0 In-Core or Temporarily Removed Fuel
3.1 The fee for in-core or temporarily removed nuclear
fuel is the sum of all of the fees calculated for each
individual in core or temporarily removed nuclear fuel
assembly. The fee for an individual assembly is
calculated using the methodology described in Article
VIII, Section A.3 of the contract. The fees for
individual assemblies are to be included in the data
supplied on the magnetic tape, below).
Section 4.0 Total Fee Due
4.1 The Principal ($). The sum of 2.4 and 3.1
The Principal for this reactor must be added to the
Principal for all other reactors operated by the
Purchaser and the sum entered on line 2.7a of the
Remittance Advice.
4.2 Enter the interest as calculated according to the
particular payment option selected for the payment of
the Spent Nuclear Fuel (SNF) fee (see Article VIII
section B.2 of the Contract). The interest for this
reactor must be added to the interest for all other
reactors operated by the Purchaser and the sum
entered on line 2.7b of the Remittance Advice.
4.3 Total SNF fee due for this reactor (Sum of 4.1 and
4.2). The total SNF fee due for this reactor must be
added to the total SNF fees for all other reactors
operated by the Purchaser and the sum entered on
line 2.7c of the Remittance Advice.
Section 5.0 Burnup Methodology Calculation
5.1 Enter the common name and version identification of
the computer code (or other calculational technique)
used to determine assembly burnup. If more than
one code is used for the assemblies from this
reactor, please identify all codes used.
5.2 Please list the documentation supporting the code(s)
used giving the document number and the title.
Please list all documentation available for the version
of the code used. The documentation referenced
should
describe
the
procedures
for
normalizing/scaling code parameters and the interfaces with other calculation procedures (e.g., lattus
physics codes). This list should be provided as an
attachment.
INSTRUCTIONS FOR PROVIDING NUCLEAR FUEL
ASSEMBLY DATA FOR ANNEX B TO STANDARD
REMITTANCE.ADVICE FOR PAYMENT OF FEES
Section 6.0
6.1 If the respondent cannot adhere to the specifications presented, below, or is unsure whether any
restrictions apply to his submission, please contact
the DOE's Energy Information Administration, Nuclear and Alternate Fuels Division at (202) 2871966.
A determination can be made regarding the DOE's
capability to compensate for any deviation from
the prescribed format. Data on fuel assemblies
from different nuclear reactor-units from a single
purchaser may be combined in a single file.
6.2 Specific Data Format
This section describes the nuclear fuel assembly
data format. Data on all assemblies which were
owned by the purchaser as of midnight April 6/7,
1983, and which had been irradiated by that date
should be included.
Information:
Utility
ID
Reactor
ID
Assembly
ID
Assembly
Status
Initial
Loading
Burnup
Fee
1-2
5-6
11-24
25
26-40
46-60
66-80
Record
Position:
(a)
(b)
(c)
(d)
Utility ID - Please enter the appropriate two digit
utility ID number from table 1.
Reactor ID - Please enter the appropriate two digit
reactor ID number from Table 1. This code must
be entered in the second field for all fuel
assemblies for that reactor. Also enter this two
digit code in line 1.4 of this annex. Assemblies
irradiated in two or more reactors should use the
Reactor ID for the core in which they were located
or from which they were last removed as of
midnight April 6/7, 1983. (Optional: Reactor ID's
for other cores in which the assembly had been
irradiated may be inserted in record positions 7-8
and 9-10).
Assembly ID – Enter the assembly identification
number, left justified.
Assembly Status - This refers to the assemblies
status as of midnight April 6/7, 1983.
For assemblies irradiated in only one reactor, use:
D – For discharged nuclear fuel
I – For in core nuclear fuel
T – For temporarily removed nuclear fuel
For assemblies irradiated in two or more reactors, use:
X – For discharged nuclear fuel
Y – For in core nuclear fuel
Z – For temporarily removed nuclear fuel
(e)
(f)
(g)
Initial Loading - Enter the mass (in whole grams)
of Uranium initially loaded in the fuel assembly,
before any irradiation in any reactor, right justified.
Burnup - Enter the assembly's total burnup (since
assembly's fabrication) as of midnight April 6/7,
1983, in units of Megawatt Days Thermal per
Metric Ton of Uranium (MWDT/MTU) in whole
numbers, right justified.
Fee - Enter the fee for this assembly in dollars and
cents, right justified with a period between the
dollars and the cents. The fee for each assembly
is calculated using methodology in Section A.2
applies to discharged nuclear fuel; the
methodology in Section A.2 applies to discharged
nuclear fuel; the methodology in Section A.3
applies to in core or temporarily removed nuclear
fuel as of midnight April 6/7, 1983.
File Type | application/pdf |
File Title | OCR Document |
Author | Readiris |
File Modified | 2006-05-22 |
File Created | 2006-05-22 |