ML18094B329
| ML18094B329 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek, 05000000 |
| Issue date: | 02/14/1990 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | ENERGY, DEPT. OF |
| References | |
| NLR-N90030, NUDOCS 9003090358 | |
| Download: ML18094B329 (92) | |
Text
-*
'f Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer FEB 1 4 l990 NLR-N90030 Energy Information Administration (EI-53)
United states Department of Energy ATTN:
RW-859 Mail Stop BG-094 Washington, DC 20585 Gentlemen:
DOE NUCLEAR FUEL DATA FORMS RW-859 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272. 50-311, 50-354 Public Service Electric and Gas Company (PSE&G) hereby submits the enclosed IBM-PC diskettes for Salem Units 1 and 2 and Hope Creek Generating Stations containing the "RW-859 Nuclear Fuel Data" for the period ending December 31, 1989, in accordance with the Nuclear waste Policy Act of 1982.
Also attached are properly certified printouts of each diskette with appropriate qualifying comments.
If you have any questions, please contact Mr *. Quresh z. Dahodwala at (609) 339-1271.
Enclosures
(
Sincerely, 9003090358 900214 PDR ADOCK 05000272 R
PNU
'\\
I
I Energy Information Administration NLR-N90030 c
Mr. J. c. Stone Lice~sing Project Manager -
Mr. c. Y. Shiraki 2
Salem Licensing Project Manager -
Hope Creek Mr. T. Johnson Senior Resident Inspector Mr. W. T. Russell,* Administrator Region I USNRC Document Control Desk Mr. Kent Tosch, Chief FEB 1 4 1i190 New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
RW-859 U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 20585 NUCLEAR FUEL DATA FORM Reactor Name: SALEM Reactor Code:4202 FORM APPROVED OMB No. 1901-0287 (EXPIRES 12/31/90 )
Data on this mandatory form are collected under authority of the Federal Energy Administration Act of 1974 115 USC Section 761 et. seq.), and the Nuclear Waste Policy Act of 1982 (42 USC 10101 et. seq. l. This form should be completed by all owners of commercial nuclear power plants that are in operation and by all other owners of spent nuclear fuel. This form should also be completed by all those who have possession of irradiated nuclear fuel from commercial nuclear power plants.
This form shall be submitted (a) 90 days after a cycle startup with data reflecting the status at cycle startup or (b) once each year, by February 15, with data that reflects the status as of December 31 of the preceding year.
A respondent may choose either reporting option, but once chosen, any change in reporting schedule would require DOE concurrence. Respondents choosing option "a,*
~ho have a reactor in an e~tended shutdown status, would be required to submit the form only if the shutdown extends to 365 days, and thereafter, only if a fuel status change occurs (e.g., discharging fuel from the core). Only one form need be submitted if the fuel status change occurs in preparation for an impending startup, i.e.,
when the regular schedule is resumed. Storage-only facilities which do not
- rradiate fuel shall complete this form by February 15 of each year.
Failure to file after receiving 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 assemblies covered by the one-time fee to the DOE on Annex B of Appendix G of the Standard Contract.
Section 1.0 2.0
- 3. 0 4.0 5.0 6.0
- 7. 0
- 8. 0 Title Utility and Reactor Data Storage Site Data Irradiated Fuel Tracking Cycle Projections Projections of Permanently Discharged Fuel Fuel Consolidation Data Defective Assembly Data Comments Appendix A Instructions for Completing the Nuclear Fuel Data Form pendix B Glossary of Terms endix C Software Instructions and Documentation for IBM-PC and Compatible Computers Please refer all questions regarding this form to:
Ms. Kathy Gibbard on (202) 254-5559.
Please return completed forms to:
Energy Information Administration - (EI-53)
.I
Attn:
RW-8j~
Mdll
~top 3G-0~4
,Was~~n;(OD, D.C.
20585 2
Reactor Name: SALEM 1.1 Utility Name:
Mailing Address:
NUCLEAR FUEL DATA FORM 1.0 UTILITY AND REACTOR DATA
[PUB SVC ELEC & GAS CO (80 PARK PLAZA
[NEWARK, NJ
[ 07101 1.2 Person who may be contacted periodically to verify information provided on this form:
Name:
Title:
Mailing Address:
Telephone Number:
[Q. Z. DAHODWALA
[SENIOR STAFF ENGINEER
[P.0. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ
[08038 (609-339-1271 1.3 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 not required).
Name:
Title:
Mai ling Address:
[L. A. MURRAY
[MANAGER-NUCLEAR FUEL (ACTING)
[P.O. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ
[08038 SIGNATURE:~ Date:.J..~-f 0 TITLE 18 USC 1001 makes it a crime for any person to knowingly and willfully make to any department or agency of the United States Government any false, fictitious, or fraudulent statements as to any matter within its jurisdiction.
1.4 Cycle Number for this report: [ O~ ]
1.5 Reactor Operating License Expiration Date:
[ 200809 ] (CCYYMM) 1.6 Projected Reactor Retirement Date:
[ 201608 l (CCYYMM) 1.7 Based on your company's current plans for spent fuel storage, what is the date when you estimate you would not be able to operate this reactor, without spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?
[200103] (CCYYMM)
NUCLEAR FUEL DATA FORM 2.0 STORAGE SITE DATA Complete Section 2.1 and 2.2 for each storage site.
Please be sure to use the "PICTOGRAM" in conjunction with this section.
2.1 Storage Site Description (al Storage Site ID [ 4202 (bl Contributing Reactors (4202 (bl Optional: Inventory from Contributing Reactors PWR BWR 2.2 la) Licensed Site Capacity :
(117 0 l (bl Maximum Established Site Capacity
[1170 l (cl Current Inventory (excluding (di)
[ 5 40 l (d) Number of Canisters (excluding le))
0 l Reactor Name: SALEM HTGR (e)
- NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Storage Site Data (continued) 2.3 Does your company have plans to increase its storage capacity at this site?
(a)
(
No plans to increase (b)
) Rod Consolidation (cl
( ) Dry Cask storage (d)
( )
Re racking (el
( ) Transshipment
( f)
Other (Please explain:
SEE COMMENTS SECTION 2.4. (a)
What is the maximum cask weight that can presently be received and handled at this storage site (keeping in mind receiving bay floor loading, rail spur or road bed limits, crane capabilities, etc. l [
110
] Tons.
(b)
What is the limiting factor? [CRANE CAPABILITY 2.5 (a)
Have you conducted studies to determine if the maximum weight cask that may be processed can be increased?
[NJ (bl If Yes to 2.5(a), is it feasible to increase the maxiumum weight cask that may be processed? [ ]
(c) If Yes to 2.5(b), what was the estimated maxiumum cask weight?
[
0 ] tons
Section 3.0 Irradiated Fuel Tracking Complete Section 3.1 for each grouping of assemblies for which no subsequent irradiation is planned or which were permanently discharged during the last reporting period, and which have these common characteristics:
Same initial enrichment Same cycle/reactor location Same current location Same owner Same fuel/vendor type Complete Section 3.2 for all other assemblies discharged from the reactor during the last reporting period (i.e., temporarily discharged).
List in Section 3.3 any assemblies which were reported as permanently discharged on previous submissions but which were reinserted for irradi-ation during this reporting period.
Complete Section 3.4 for any irradiated assemblies which have been shipped from or to your site or which have changed ownership during the last reporting period.
Reactor Name: SALEM NUCLEAR FUEL DATA FORM S~ction 3.1 Group Description for Permanently Discharged Fuel (al Group Name
[10.0 ] (Optional)
(b)
Number of Assemblies
[ 3 l (c) Cycle No.:
[08 ]
(d)
Cycle Shutdown Date:
(198904 ] (CCYYMMDD)
(e)
Group Location
[4202] (See Appendix A, Table 2, Storage Site Codes)
If) Contract Number
[4480] (See Appendix A, Table 1, Contract Number~)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 465.000]
Kilograms (i)
Nominal Initial Enrichment: ( 3.800
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [NJ (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
Ill Average Assembly Burnup: [
17
] GWD/MTU (m)
Comments:
(NOTE:
Your comments will be printed in the comments section).
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[6A (Optional!
(bl Number of Assemblies
[ 8 (c)
Cycle No.:
[08 ]
(d)
Cycle Shutdown Date:
[198904 ] (CCYYMMDDI te)
Group Location
[4202] (See Appendix A, Table 2, Storage Site Codes)
(f) Contract Number
[4480] (See Appendix A, Table 1, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 459.000]
Kilograms (i)
Nominal Initial Enrichment: [ 3.400
] [Percentage by weight to the nearest ten~h percent)
[j)
Does this group employ varying enrichments within an assembly ? [NJ ( Y /NI If you answered yes to question 3.l[j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l[il, please specify the maximum pellet enrichment:
[ 0.000 ] [percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
40
] GWD/MTU
[m)
Comments:
[NOTE:
Your comments will be printed in the comments section).
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[6B (Optional)
(b)
Number of Assemblies
[ 4 (cl Cycle No.:
[08 ]
(d)
Cycle Shutdown Date:
[198904 ] (CCYYMMDD)
(e)
Group Location
[4202] (See Appendix A, Table 2, Storage Site Codes)
( f) Contract Number
[4480] (See Appendix A, Table 1, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 458.000]
Kilograms (il Nominal Initial Enrichment: [ 3.400
] (Percentage by weight to the nearest tenth percent)
(j)
Doe~ this group employ varying enrichments within an assembly ? [N] (Y/Nl If you answered yes to question 3.l{j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(il, please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
{l) Average Assembly Burnup: [
38
] GWD/MTU (ml Comments:
(NOTE:
Your comments will be printed in the comments section).
9 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel la)
Group Name
[7.0 (Optional)
(b)
Number of Assemblies
[ 1 (cl Cycle No.:
[08 ]
(d)
Cycle Shutdown Date:
[198904 ] (CCYYMMDDl le)
Group Location
[4202] (See Appendix A, Table 2, Storage Site Codes)
( f) Contract Number
[4480] (See Appendix A, Table l, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(hl Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 458.000]
Kilograms (i)
Nominal Initial Enrichment: [ 3.400
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [N] (Y/N)
If you *answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
41
] GWD/MTU (m)
Comments:
(NOTE:
Your comments will be printed in the comments section).
10 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[SA (Optional)
(b)
Number of Assemblies
[ 4 (cl Cycle No.:
[08 ]
(d)
Cycle Shutdown Date:
[198904 ] (CCYYMMDD)
(el Group Location
[4202] (See Appendix A, Table 2, Storage Site Codes)
(f) Contract Number
[4480] (See Appendix A, Table 1, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] [See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 462.000]
Kilograms (i)
Nominal Initial Enrichment: [ 3.400
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [NJ (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
Ill Average Assembly Burnup: [
35
] GWD/MTU (ml Comments:
(NOTE:
Your comments will be printed in the comments section).
11 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[9.0
[Optional)
[b)
Number of Assemblies
[ 5 5 (c)
Cycle No.:
[OB ]
[d)
Cycle Shutdown Date:
[198904 ] [CCYYMMDD)
[e)
Group Location
[4202] [See Appendix A, Table 2, Storage Site Codes)
[ f)
Contract Number
[4480] [See Appendix A, Table l, Contract Numbers)
[g)
Fuel/Vendor Type
[17 WST] [See Appendix A, Table 3, Fuel/Vendor Types)
[h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 465.000]
Kilograms
[i)
Nominal Initial Enrichment: [ 3.800 I [Percentage by weight to the nearest tenth percent)
[j)
Does this group employ varying enrichments within an assembly ? [N] [Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent [or greater than one percent) above the nominal enrichment reported in question 3.l[i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
35
] GWD/MTU
[m)
Commenfs:
[NOTE:
Your comments will be printed in the comments section).
~AGE:
12 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: !For example: 5201/036 is unique and not to be confused with 5203/036)
List cf unique assembly identifiers for group ID: 10.0 Kl?
K32 K41
-GE:
3.1 ( n)
F02 F18 13 Reactor Name: SALEM NUCLEAR FUEL DATA FORM List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 6A F03 F04 F05 F08 F48 F56
-GE:
3.1 ( n)
F07 14 Reactor Name: SALEM NUCLEAR FUEL DATA FORM List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 6B F28 F40 F53
~GE:
3.1 (n)
G15 15 Reactor Name: SALEM NUCLEAR FUEL DATA FORM List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/036 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 7.0
'E:
3.1 ( n l Hl6 16 Reactor Name: SALEM NUCLEAR FUEL* DATA FORM List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: BA H33 H42 H46
.GE:
17 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 9.0 Jl8 J30 J39 J42 J60 J61 J62 J04 JlO Jl2 Jl5 J25 J28 J33 J37 J55 J65 J74 J78 Jl6 J23 J27 J53 J58 J66 J68 J70 J75 J80 JOJ J13 J22 J32 J43 J71 JOl J21 J36 J38 J41
.9 J54 J56 J7 3 J82
. Jl9 J20 J29 J44 J 47 J52 J63 J83 J84 Jl7
4'GE:
18 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.2 Listing of Temporarily Discharged Fuel NOTE: Temporarily discharged fuel is defined as fuel which was irradiated in the previouse cycle (cycle N) and not in the following fuel cycle (cycle N+l), and which you have definite plans to irradiate in a subsequent fuel cycle.
(a) Cycle No.:
[08 ]
lb) Cycle End Date:
[198904 ]
(c)
Number of Assemblies: [ 13 (d) List the unique fuel assembly identifiers for the assemblies meeting this description:
GOl GlO Gl3 Gl6 G30 G33 G34 G39 K24 K28 K34 K48 K67
~GE:
19 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.3 Changes in Permanently Discharged Status List any assemblies which were reported as perraanently discharged Ion the October 1983 Annex B submission) but which have been reinserted during the last reporting period.
NOTE:
These data are to be supplied when the assembly is actually reinserted into the reactor, not when you make a decision to reinsert a permanently discharged assembly.
NOTE:
When the assemblies listed below are again permanently discharged they must be reported in Section 3.1.
List the unique fuel assembly identifiers for the assemblies meeting this description:
NO ASSEMBLIES CHANGED THEIR ANNEX B STATUS DURING THIS REPORTING PERIOD.
.GE:
20 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.4 Shipment and Change of Ownership of Irradiated Fuel For any assemblies which during the last reporting period were shipped to another storage site or which changed ownership, attach photocopies of the DOE Form 741 (including the unique assembly identifiers, consis-tent with prior Form RW-859 submittals) completed for the transfer.
NOTE:
These assemblies must have been reported as permanently discharged.
If no DOE Form 741 reflects the shipment or change of ownership of irradiated fuel (for example, movement of irradiated fuel to another on-site storage facility), complete the following:
Group Description for Permanently Discharged Fuel Which Changed Storage Site or Ownership:
NO SHIPMENT DATA ENTERED INTO THE SYSTEM.
.GE:
21 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.0 Cycle Projections 4.1 (al lb) le)
[d) le)
CYCLE CYCLE NUMBER OF NUMBER OF CYCLE BURNUP NUMBER SHUTDOWN UNIRRADIATED REINSERTED
!EFFECTIVE FULL DATE ASSEMBLIES ASSEMBLIES POWER DAYS)
[CCYYMMDD)
INSERTED IN CYCLE N+ 1 08 IN) (Actual) 198904 84 352 09 (Actual/Projected)
IN + 1) 199010 76 12 421 10IN+2) 199204 76 431 11 (N + 3) 199309 72 437 12(N+4) 199503 76 447 13 IN + 5) 199609 80 469
.TE: Cycle "N" is the cycle whose shutdown prompted submission_ of this form as reported in question 1.4.
NOTE:
Reinserted assemblies are defined as previously irradiated assemblies which were not inserted in the last cycle (cycle N),
but which are inserted in this cycle (cycle N+l).
.GE:
22 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.2 List the unique assembly identifiers for the assemblies counted in question 4.1, column (c) for the current cycle IN+ll.
LOl L02 L03 L04 L05 L06 L07 L08 L09 LlO Lll L12 L13 L14 L15 L16 L17 L18 L19 L20 L21 L22 L23 L24 L25 L26 L27 L28 L29 L30 L31 L32 L33 L34 L35 L36 L37 L38 L39 L40 L41 L42 L43 L44 L45 L46 L47 L48 L49 L50 L52 L53 L54 L55 L56 L57 L58 L59 L60 L61 L62 L63 L64 L65 L66 L67 L68 L69 L70 L71 L 7 2 L 7 3 L74 L75 L76
23 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.3 List the unique assembly identifiers for the assemblies counted in question 4.1, column (d).
F06 F15 F32 F33 F35 F46 F54 G56 H13 H25 H37 H41
24 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/HTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 09 l I N + 1 )
3.400 40 SA 3.400 32 BA 3.400 37 29 3.800 42 10 48 3.800 34
25 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE:
Initial Enrichment in weight percent is to be reported to the nearest tenth.
Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTUl CYCLE:
[ 10 J I N + 2 )
3.300 24 SB 3.400 41 BB 3.800 47 10 28 3.800 41 11B 36 3.600 36 11A 12 4.000 35
41fGE:
26 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE:
Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
27 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information
, reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group
[Optional)
[Discharged)
(Weight Percent)
(GWD/~'!.Jl CYCLE:
[ 12 l ( N + 4 )
3.300 25 3.400 33 12A 24 4.000 48 12B 12
- 4. 400 45 13A 4.400 42 13B 28 3.800 38
.GE:
28 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 13 l ( N + 5 )
10 3.800 33 13A 32 4.400 47 13B 3.800 50 14A 40
- 4. 400 35
29 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 6.0 Fuel Consolidation Data 6.1 If your company consolidated fuel assemblies from this reactor since the last report, list the unique assembly identifiers of the assemblies that were consolidated.
NO ASSEMBLIES WERE CONSOLIDATED DURING THIS REPORTING PERIOD.
6.2 How many canisters of fuel bearing components were produced from the above consolidation [ 0 ] canisters.
30 Reactor Name: SALEH NUCLEAR FUEL DATA FORM 7.0 Defective Assembly Data Please list the assemblies that were permanently discharged during the last reporting period and which are classified as defective as described in Section 7.0, Appendix A (Page A-6) or which are currently classified as defective and were not reported as such on previous submissions.
NOTE: These assemblies MUST have also been described in Section 3.1.
NO ASSEMBLIES WERE LISTED AS DEFECTIVE DURING THIS REPORTING PERIOD.
31 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[1.6 Retirement date reflects company plans for plant life extension. This date reflects 40 years from the startup date.
Form
Reference:
[1.7(A)]
The calculation of the date in section 1.7 does not take into account storage spaces needed for an "operational' full core discharge capability. Note that an operational full core discharge allows for discharge of 193 fuel assemblies Form
Reference:
[1.7(B)]
from the core into the pool and it also makes available quate #of spaces needed to store dummy assemblies, rces, tools, specimens and account for bad cells that may
- be unavailable for spent fuel storage. Defining the full Form
Reference:
[l.7(C)]
core discharge capability for Salem 1 as equivalent to 300 spaces, then Salem 1 will lose this capability beginning cycle 14 (Sept - Nov, 1996). This is the critical date for Salem 1.
Form
Reference:
[2.2 28 cells are unusable due to fuel rack problems.
27 cells are presently used for storing non-fuel bearing components.
This leaves a total of 575 cells available for SNF storage.
Please factor this information in your study.
Form
Reference:
[2.3(f)]
. A study is ongoing to determine the best alternative available to meet PSE&G needs to increase on-site storage
.ability.
Reactor Name: SALEM
32 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[2.4(b)]
Limiting factor is crane capability. Note that 110 tons is the maximum cask weight and the weight of its contents including tolerances that can be handled at this site.
Form
Reference:
[3.3 There are no changes to ANNEX B submission.
Form
Reference:
[3.4
~el assemblies have not been shipped to any other site or
~anged ownership.
Form
Reference:
[5.0 For all cycles, the total number of permanently plus temporarily discharged fuel assemblies from cycle N equals the total number of unirradiated plus reinserted fuel assemblies inserted in cycle N + 1.
Form
Reference:
[7.0 No fuel assemblies are classified as defective for DOE purposes of transporting and disposal from the last outage.
Reactor Name: SALEM
- .If.
.GE:
Reactor Name: SALEM Reactor Code:4203 R\\H59 U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 20585 FORM APPROVED NUCLEAR FUEL DATA FORM OMB No. 1901-0287 (EXPIRES 12/31/90 )
Data on this mandatory form are collected under authority of the Federal Energy Administration Act of 1974 !15 USC Section 761 et. seq.), and the Nuclear Waste Policy Act of 1982 (42 USC 10101 et. seq. l. This form should be completed by all owners of commercial nuclear power plants that are in operation and by all other owners of spent nuclear fuel. This form should also be completed by all those who have possession of irradiated nuclear fuel from commercial nuclear power plants.
This form shall be submitted (a) 90 days after a cycle startup with data reflecting the status at cycle startup or (b) once each year, by February 15, with data that reflects the status as of December 31 of the preceding year.
A respondent may choose either reporting option, but once chosen, any change in reporting schedule would require DOE concurrence. Respondents choosing option "a,"
who have a reactor in an extended shutdown status, would be required to submit the form only if the shutdown extends to 365 days, and thereafter, only if a fuel status change occurs (e.g., discharging fuel from the core). Only one form need be submitted if the fuel status change occurs in preparation for an impending startup, i.e.,
when the regular schedule is resumed. Storage-only facilities which do not irradiate fuel shall complete this form by February 15 of each year.
Failure to file after receiving 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 assemblies covered by the one-time fee to the DOE on Annex B of Appendix G of the Standard Contract.
Section i.O 2.0 Title Utility and Reactor Data Storage Site Data Irradiated Fuel Tracking Cycle Projections
- 3. 0 4.0
- 5. 0 6.0
- 7. 0
- 8. 0 Appendix A Appendix B
~ppendix c Projections of Permanently Discharged Fuel Fuel Consolidation Data Defective Assembly Data Comments Instructions for Completing the NuclP.ar Fuel Data Form Glossary of Terms Software Instructions and Documentation for IBM-PC and Compatible Computers Please refer all questions regarding this form to:
Ms. Kathy Gibbard on (202) 254-5559.
Please return completed forms to:
Energy Information Administration - IEI-53)
U. s.
n~n~rtmant of Enarav
httn:
RW-859 Mail Stop 3G-094
- washrngto.~. D.C.
- 20585 1.1 Utility Name:
Mailing Address:
Reactor Name: SALEM NUCLEAR FUEL DATA FORM 1.0 UTILITY AND REACTOR DATA
[PUBLIC SERV. ELEC. AND GAS CO.
[80 PARK PLAZA
[NEWARK, NJ 07101
[
1.2 Person who may be contacted periodically to verify information provided on this form:
Name:
Title:
Mailing Address:
Telephone Number:
[Q. Z. DAHODWALA
[SENIOR STAFF ENGINEER
[P.0. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ 08038
[
[609-339-1271 1.3 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 not required).
[L. A. MURRAY Name:
Title:
Mailing Address:
[MANAGER-NUCLEAR FUEL (ACTING)
[P.O. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ 08038
[
SIGNATURE:~
TITLE 18 USC 1001 makes it a crime for any person to knowingly and willfully make to any department or agency of the United States Government any false, fictitious, or fraudulent statements as to any matter within its jurisdiction.
1.4 Cycle Number for this report: [ 04 ]
1.5 Reactor Operating License Expiration Date:*
[ 200809 ] (CCYYMM) 1.6 Projected Reactor Retirement Date:
[ 202004 ] (CCYYHMl
- 1. 7 Based on your company's current plans for spent fuel storage, what is the date when you estimate you would not be able to operate this reactor, without spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?
[200503] (CCYYMM)
tjGE:
NUCLEAR FUEL DATA FORM 2.0 STORAGE SITE DATA Complete Section 2.1 and 2.2 for each storage site.
Please be sure to use the "PICTOGRAM" in conjunction with this section.
2.1 Storage Site Description (a) Storage Site ID [ 4203 lbl Contributing Reactors
[4203 (b) Optional: Inventory from Contributing Reactors [ 308 PWR BWR 2.2 (a) Licensed Site Capacity :
[1170 J (b) Maximum Established Site Capacity
[1170 J (c) Current Inventory (excluding (d))
[ 3 0 8 J (d) Number of Canisters (excluding (cl l 1 J Reactor Name: SALEH HTGR (e)
- NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION 2
2.3 2.4 2.5 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Storage Site Data [continued)
Does your company have plans to increase its storage capacity at this site?
(a)
( ) No plans to increase lb)
( ) Rod Consolidation (c)
( ) Dry Cask storage (d)
( ) Reracking (e)
( ) Transshipment (f) Other (Please explain:SEE COMMENTS 2.J(f)
(a)
What is the maximum cask weight that can presently be received and handled at this storage site (keeping in mind receiving bay floor loading, rail spur or road bed limits, crane capabilities, etc. ) [
110
] Tons.
(b)
What is the limiting factor? [crane capability (a)
Have you conducted studies to determine if the maximum weight cask that may be processed can be increased?
[NJ (b) If Yes to 2.5(a), is it feasible to increase the maxiumum weight cask that may be processed? [ ]
(c) If Yes to 2.S(b), what was the estimated maxiumum cask weight?
[
0 J tons
Section 3.0 Irradiated Fuel Tracking Complete Section 3.1 for each grouping of assemblies for which no subsequent irradiation is planned or which were permanently discharged during the last reporting period, and which have these common characteristics:
Same initial enrichment Same cycle/reactor location Same current location Same owner Same fuel/vendor type Complete Section 3.2 for all other assemblies discharged from the reactor during the last reporting period (i.e., temporarily discharged).
List in Section 3.3 any assemblies which were reported as permanently discharged on previous submissions but which were reinserted for irradi-ation during this reporting period.
Complete Section 3.4 for any irradiated assemblies which have been shipped from or to your site or which have changed ownership during the last reporting period.
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[3.0 (Optional)
(b)
Number of Assemblies
[ 2 (c)
Cycle No.:
[04 ]
(d)
Cycle Shutdown Date:
[19880800] (CCYYMMDD)
(e)
Group Location
[4203] (See Appendix A, Table 2, Storage Site Codes)
[ f)
Contract Number
[4480] (See Appendix A, Table 1, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 460.000]
Kilograms (i)
Nominal Initial Enrichment: [ 3.100
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [N] (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
Ill Average Assembly Burnup: [
32
] GWD/MTU (ml Comments:
(NOTE:
Your comments will be printed in the comments section).
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[4.0 (Optional)
(bl Number of Assemblies
[ 2 8 (c)
Cycle No.:
[04 ]
Id)
Cycle Shutdown Date:
[19880800] ICCYYMMDD)
(e)
Group Loe a ti on
[4203] (See Appendix A, Table 2, Storage Site Codes)
( f)
Contract Number
[4480] (See Appendix A, Table l, Contract Numbers)
(g)
Fuel/Vendor Type
[ 17 WST J (See Appendix A, Tab 1 e 3, Fuel/Vendor Types l (h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 459.000]
Kilograms Ii)
Nominal Initial Enrichment: [ 3.400
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [NJ (Y/Nl If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent I.
(1)
Average Assembly Burnup: [
38
] GWD/MTU (ml Comments:
(NOTE:
Your comments will be printed in the comments section).
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel I al Group Name
[SA
[Optional) lb)
Number of Assemblies
[ 42 le)
Cycle No.:
[04 ]
[d)
Cycle Shutdown Date:
[19880800] [CCYYMMDD)
I el Group Location
[4203] (See Appendix A, Table 2, Storage Site Codes)
If l Contract Number
[4480] !See Appendix A, Table l, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
[h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 460.000]
Kilograms Ii)
Nominal Inicial Enrichment:[ 3.800
] !Percentage by weight to the nearest tenth percent) ljl Does this group employ varying enrichments within an assembly ? [NJ IY/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent [or greater than one percent) above the nominal enrichment reported in question 3.l[il, please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
Ill Average Assembly Burnup: [
37
] GWD/MTU
[m)
Comments:
[NOTE:
Your comments will be printed in the comments section).
2
Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[SB (Optional)
(b)
Number of Assemblies
[ 3 (cl Cycle No.:
[04 ]
(d)
Cycle Shutdown Date:
[19880800] ICCYYMMDD)
(e)
Group Location
[4203] (See Appendix A, Table 2, Storage Site Codes)
( f)
Contract Number
[4480]. (See Appendix A, Table 1, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 464.000]
Kilograms
[i)
Nominal Initial En.richment: [ 3.400
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [NJ (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
39
] GWD/MTU Im)
Comments:
(NOTE:
- Your comments will be printed in the comments section).
10 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name (6.0 (Optional!
(bl Number of Assemblies
[ 5 (cl Cycle No.:
[04 ]
(d)
Cycle Shutdown Date:
[19880800] (CCYYMMDD)
(e)
Group Location (4203] (See Appendix A, Table 2, Storage Site Codes)
( f) Contract Number
[4480] (See Appendix A, Table l, Contract Numbers)
(g)
Fuel/Vendor Type
[17 WST] [See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 465.000]
Kilograms (i)
Nominal Initial Enrichment: [ 3.800
] (Percentage by weight to the nearest tenth percent)
[j)
Does this group employ varying enrichments within an assembly ? [NJ (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent [or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 0.000 ] (percentage by weight to the nearest tenth percent).
Ill Average Assembly Burnup:
[
22
] GWD/MTU (m)
Comments:
(NOTE:
Your comments will be printed in the comments section).
11 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: [For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 3.0 N05 N19
12 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/036)
List of unique assembly identifiers for group ID: 4. 0 P03 P06 P07 P09 P12 P14 P16 Pl8 P21 P22 P28 P30 P31 P33 P34 P39 P42 P45 P53 P54 P55 P56 P58 P59 P65 P67 P69 P72
13 Reactor N~me: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 5A ROl R06 R07 R08 R09 RlO Rll R13 R14 R16 R19 R20 R21 R22 R24 R25 R27 R28 E29 R30 R31 R34 R35 R36 R37 R42 R43 R44 R45 R46 R47 R48 R49 R50 R51 R52 R54 R55 R57 R58
.0 R62
14 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility! for the assemblies in this grouping: (For example: 5201/036 is unique and not to be confused with 5203/036)
List of unique assembly identifiers for group ID: SB R81 R82 R84
15 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 lnl List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/036 is unique and not to be confused with 5203/036)
List of unique assembly identifiers for group ID: 6.0 S55 S82 S80 Sl7 S23 2
16 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.2 Listing of Temporarily Discharged Fuel NOTE: Temporarily discharged fuel is defined as fuel which was irradiated in the previouse cycle (cycle Nl and not in the following fuel cycle [cycle N+l), and which you have definite plans to irradiate in a subsequent fuel cycle.
(a)
Cycle No.:
[04 ]
(bl Cycle End Date:
[19880800]
(cl Number of Assemblies: [ 14 (d)
List the unique fuel assembly identifiers for the assemblies meeting this description:
P04 P13 P27 P29 P43 P66 R02 R12 R23 R32 R38 R53
- R56 R59
17 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.3 Changes in Permanently Discharged Status List any assemblies which were reported as permanently discharged Ion the October 1983 Annex B submission) but which have been reinserted during the last reporting period.
NOTE:
These data are to be supplied when the assembly is actually reinserted into the reactor, not when you make a decision to reinsert a permanently discharged assembly.
NOTE:
When the assemblies listed below are again permanently discharged they must be reported in Section 3.1.
List the unique fuel assembly identifiers for the assemblies meeting this description:
NO ASSEMBLIES CHANGED THEIR ANNEX B STATUS DURING THIS REPORTING PERIOD.
18 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.4 Shipment and Change of Ownership of Irradiated Fuel For any assemblies which during the last reporting period were shipped to another storage site or which changed ownership, attach photocopies of the DOE Form 741 (including the unique assembly identifiers, consis-tent with prior Form RW-859 submittals) completed for the transfer.
NOTE:
These assemblies must have been reported as permanently discharged.
If no DOE Form 741 reflects the shipment or change of owrr2rship of irradiated fuel (for example, movement of irradiated fuel to another on-site storage facility), complete the following:
Group Description for Permanently Discharged Fuel Which Changed Storage Site or Ownership:
NO SHIPMENT DATA ENTERED INTO THE SYSTEM.
.GE:
19 4.1 (al (b)
CYCLE CYCLE NUMBER SHUTDOWN DATE
( CCYYMMDD) 04 (N) (Actual) 19880800 05 (Actual/Projected)
(N + ll 19900300 06 (N + 2) 19910900 07 (N + 3) 19930400 08 (N + 4) 19940900 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.0 Cycle Projections ic)
(d)
( e)
NUMBER OF NUMBER OF CYCLE BURNUP UNIRRADIATED REINSERTED (EFFECTIVE FULL ASSEMBLIES ASSEMBLIES POWER DAYS)
INSERTED IN CYCLE N+ 1 84 464 84 10 384 76 432 80 437 80 442 09 (N + 5) 19960300 80 464
~TE: Cycle "N" is the cycle whose shutdown prompted submission of this form as reported in question 1.4.
NOTE:
Reinserted assemblies are defined as previously irradiated assemblies which were not inserted in the last cycle (cycle N),
but which are inserted in this cycle (cycle N+l).
.AGE:
20 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.2 List the unique assembly identifiers for the assemblies counted in question 4.1, column (c) for the current cycle (N+l).
TOl T02 T0.3 T04 TOS T06 TO?
TOB T09 TlO Tll T12 T13 T14 T15 T16 T17 TlB T19 T20 T21 T22 T2J T24 T25 T26 T27 T28 T29 T30 T31 T32 T33 T34 T35 T36 T37
- T38 T39 T40 T41 T42 T43 T44 T45 T46 T47 T48 T49 TSO
.1 T52 T53 T54 T55 T56 T57 T58 T59 T60 T61 T62 T63 T64 T65 T66 T67 T68 T69 T70 T71 T72 TH T74 T75 T76 T77 T78 T79 T80 T81 T82 T83 T84
21 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.3 List the unique assembly identifiers for the assemblies counted in question 4.1, column (d).
POl P02 P15 P20 P26 P44 P50 P52 P68 R83
22 Reactor Name: SALEM NUCLEAR FUEL DATA FORM S.O Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percen~ is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group
[Opt i ona ll
[Discharged)
[Weight Percent)
(GWD/MTU)
CYCLE:
[ 0 s l [ N + 1 )
4.0 9
3.400 38
23 Reactor Name: SALEM NUCLEAR FUEL.DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
. NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth.
Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 06 l I N + 2 l 3.0 3.100 29 4.0 12 3.400 34 4.0 3.400 42 6.0 16 3.800 44 7A 4.000 35 7B 36 3.600 36
24 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 07 l I N + 3 I 4.0 3.400 43 5A 3.800 35 7A 32 4.000 43 SA 20 4.000 35 BB 28 3.800 38
25 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge 8urnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 0 8 J ( N + 4 )
- 3. 0 3.100 36 5A 3.800 35 7A
- 4. 000 49 8A 12 4.000 49 88 3.800 42 9A 20 4.000 36 98 32 3.800 39 2
26 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE:
Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
I Discharged)
(Weight Percent)
(G~D/MTU)
CYCLE:
[ 09 l I N + 5 )
2.0 2.600 38 4.0 3.400 40 BA 4.000 38 9A 12 4.000 50 9B 3.800 43 lOA 16 4.000 43 lOB 32 3.800 39
27 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 6.0 Fuel Consolidation Data 6.1 If your company consolidated fuel assemblies from this reactor since the last report, list the unique assembly identifiers of the assemblies that were consolidated.
NO ASSEMBLIES WERE CONSOLIDATED DURING THIS REPORTING PERIOD.
6.2 How many canisters of fuel bearing components were produced fro~ the above consolidation [ 0 ] canisters.
28 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 7.0 Defective Assembly Data Please list the assemblies that were permanently discharged during the last reporting period and which are classified as defective as described in Section 7.0, Appendix A (Page A-6) or which are currently classified as defective and were not reported as such on previous submissions.
NOTE: These assemblies MUST have also been described in Section 3.1.
NO ASSEMBLIES WERE LISTED AS DEFECTIVE DURING THIS REPORTING PERIOD.
29 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[1.6 Retirement date reflects company plans for plant life extension. This date reflects 40 years from the startup date.
Form
Reference:
[1.7(A)]
The calculation of the date in section 1.7 does not take into account storage spaces needed for an "operational" full core discharge capability. Note that an operational full core discharge allows for discharge of 193 fuel assemblies Form
Reference:
[l.7(B)]
from the core into the pool and it also makes available equate #of spaces needed to store dummy assemblies, urces, tools, specimens and account for bad cells that may
- be unavailable for spent fuel storage. Defining the full Form
Reference:
[1.7!Cl]
core discharge capability for Salem 2 as equivalent to 300 spaces, then Salem 2 will lose this capability beginning cycle 12 (Aug - Oct, 2000). This is the critical date for Salem 2.
Form
Reference:
(2.2 19 cells are unusable because of fuel rack problems.
20 cells are used for storage of non fuel bearing components.
This leaves a total of 823 cells available for SNF storage.
Please factor this info in your study. (continued)
Form
Reference:
[2.3 (fl]
. A study is ongoing to determine the best alternative available to meet PSE&G needs to increase on-site storage
.pability.
Reactor Name: SALEM
GE:
30 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[2.4(b) I Limiting factor is crane capability. Note that the 110 tons is the maximum cask weight and the weight of its contents including tolerances that can be handled at this site.
Form
Reference:
(3.3 There are no changes to the ANNEX B submission.
Form
Reference:
(3.4 el assemblies have not been shipped to any other site or anged ownership.
Form
Reference:
(5.0 For all cycles, the total number of permanently plus temporarily discharged fuel assemblies from cycle N equal to the total number of unirradiated plus reinserted assemblies inserted in cycle N+l Reactor Name: SALEM 2
R\\H59 U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 20585 NUCLEAR FUEL DATA FORM Reactor Name: HOPE CREEK Reactor Code:4201 FORM APPROVED OMB No. 1901-0287 (EXPIRES 12/31/90 )
Data on this mandatory form are collected under authority of the Federal Energy Administration Act of 1974 (15 USC Section 761 et. seq.), and the Nuclear Waste Policy Act of 1982 (42 USC 10101 et. seq.). This form should be completed by all owners of commercial nuclear power plants that are in operation and by all other owners of spent nuclear fuel. This form should also be completed by all those who have possession of irradiated nuclear fuel from commercial nuclear power plants.
This form shall be submitted (a) 90 days after a cycle startup with data reflecting the status at cycle startup or [bl once each year, by February 15, with data that reflects the status as of December 31 of the preceding year.
A respondent may choose either reporting option, but once chosen, any change in reporting schedule would require DOE concurrence. Respondents choosing option *a,"
who have a reactor in an extended shutdown status, would be required to submit the form only if the shutdown extends to 365 days, and thereafter, only if a fuel status change occurs [e.g., discharging fuel from the core). Only one form need be submitted if the fuel status change occurs in preparation for a~ impending startup, i.e.,
when the regular schedule is resumed. Storage-only facilities which do not irradiate fuel shall complete this form by February 15 of each year.
Failure to file after receiving 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 assemblies covered by the one-time fee to the DOE on Annex B of Appendix G of the Standard Contract.
Section 1.0 2.0
- 3. 0
- 4. 0 5.0 6.0
- 7. 0
- 8. 0 Title Utility and Reactor Data Storage Site Data Irradiated Fuel Tracking
- cycle Projections Projections of Permanently Discharged Fuel Fuel Consolidation Data Defective Assembly Data Comm en ts Appendix A Instructions for Completing the Nuclear Fuel Data Form ppendix B Glossary of Terms ppendix C Software Instructions and Documentation for IBM-PC and Compatible Computers Please refer all questions regarding this form to:
Ms. Kathy Gibbard on [202) 254-5559.
Please return completed forms to:
Energy Information Administration - (EI-53)
Attn:
RW-859 Mail Stop BG-094
- Washingc,on, D.C: 20585 2
1.i Utility Name:
Mailing Address:
NUCLEAR FUEL DATA FORM 1.0 UTILITY AND REACTOR DATA
[PUBLIC SERV. ELEC AND GAS CO.
[80 PARK PLAZA
[NEWARK, NJ 07101
[
Reactor Name: ROPE CREEK 1.2 Person who may be contacted periodically to verify information provided on this form:
Name:
Title:
Mailing Address:
Telephone Number:
[Q. Z. DAHODWALA
[SENIOR STAFF ENGINEER
[P.O. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ
[08038
[609-339-1271 1.3 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 not required).
Name:
Title:
Mailing Address:
[L. A. MURRAY
[MANAGER - NUCLEAR FUEL (ACTING)
[P.O. BOX 236
[NUCLEAR DEPT, N20
[HANCOCKS BRIDGE, NJ
[08038 SIGN!IURE: ~
Date:~
TITLE 18 USC 1001 makes it a crime for any person to knowingly and willfully make to any department or agency of the United States Government any false, fictitious, or fraudulent statements as to any matter within its jurisdiction.
- 1. 4 Cycle Number for this report: [ O~ ]
1.5 Reactor Operating License Expiration Date:
[ 202604 ] (CCYYHM) 1.6 Projected Reactor Retirement Date:
[ 202604 ] (CCYYMM) 1.7 Based on your company's current plans for spent fuel storage, what is the date when you estimate you would not be able to operate this reactor, without spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?
[20120 3] ( CCYYMMl
.1 NUCLEAR FUEL DATA FORM 2.0 STORAGE SITE DATA Complete Section 2.1 and 2.2 for each storage site.
Please be sure to use the "PICTOGRAM" in conjunction with this section.
2.1 Storage Site Description (a)
Storage Site ID [ 4201 (bl Contributing Reactors
[4201 (bl Optional: Inventory from Contributing Reactors [ 496 2.2 la) Licensed Site -Capacity :
(bl Maximum Established Site Capacity (cl Current Inventory (excluding (d))
(d) Number of Canisters (excluding (c))
[1290]
[397 6]
[ 496]
O]
Reactor Name: HOPE CREEK 0
HTGR (el
- NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION
Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM Storage Site Data (continued) 2.3 Does your company have plans to increase its storage capacity at this site?
2.4 2.5 (a)
( ) No plans to increase (b)
( ) Rod Consolidation (c)
I ) Dry Cask storage Id)
I ) Reracking (e)
I ) Transshipment If) Other (Please explain:NOW RACKING POOL TO MAX. CAP.
(a)
What is the maximum cask weight that can presently be received and handled at this storage site (keeping in mind receiving bay floor loading, rail spur or road bed limits, crane capabilities, etc. l [
150
] Tons.
(b)
What is the limiting factor? [CRANE CAPABILITY (a)
Have you conducted studies to determine if the maximum weight cask that may be processed can be increased?
[NJ lb) If Yes to 2.5(a), is it feasible to increase the maxiumum weight cask that may be processed? [ ]
le) If Yes to 2.5(b), what was the estimated maxiumum cask weight?
[
0 ] tons J
Section 3.0 Irradiated Fuel Tracking Complete Section 3.1 for each grouping of assemblies for which no subsequent irradiation is planned or which were permanently discharged during the last reporting period, and which have these common characteristics:
Same initial enrichment Same cycle/reactor location Same current location Same owner Same fuel/vendor type Complete Section 3.2 for all other assemblies discharged from the reactor during the last reporting period (i.e., temporarily discharged).
List in Section 3.3 any assemblies which were reported as permanently discharged on previous submissions but which were reinserted for irradi-ation during this reporting period.
Complete Section 3.4 for any irradiated assemblies which have been shipped from or to your site or which have changed ownership during the last reporting period.
Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[01C02 ] (Optional)
(b)
Number of Assemblies
[152 (c) Cycle No.:
[02 l (d)
Cycle Shutdown Date:
(19890900] (CCYYMMDD)
(e)
Group Location
[4201] (See Appendix A, Table 2, Storage Site Codes)
( f)
Contract Number
[ 4411] (See Appendix A, Table l, Contract Numbers)
(g)
Fuel/Vendor Type
[08 G72] (See Appendix A, Table 3, Fuel/Vendor Types)
(h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 184.920] Kilograms (il Nominal Initial Enrichment: [ 1.630
] (Percentage by weight to the nearest tenth percent)
(j)
Does this group employ varying enrichments within an assembly ? [Y] (Y/Nl If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l[i), please specify the maximum pellet enrichment:
[ 2.000 ] (percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
16
] GWD/MTU (m)
Comments:
(NOTE:
Your comments will be printed in the comments section).
Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharged Fuel (a)
Group Name
[OlDOl ] (Optional)
(b)
Number of Assemblies
[ 112 l (c)
Cycle No.:
[02 l (d)
Cycle Shutdown Date:
[19890900] (CCYYMMDD)
(el Group Location (4201] (See Appendix A, Table 2, Storage Site Codes)
[ f)
Contract Number
[ 4411] (See Appendix A, Table 1, Contract Numbers)
[g)
Fuel/Vendor Type
[08 G72] [See Appendix A, Table 3, Fuel/Vendor Types)
[h)
Nominal Assembly Weight, in Kilograms of initial heavy metal:
[ 184.500]
Kilograms (i)
Nominal Initial Enrichment:[ 2.480
] (Percentage by weight to the nearest ten~h percent)
(j)
Does this group employ varying enrichments within an assembly ? [Y] (Y/N)
If you answered yes to question 3.l(j): If the maximum pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximum pellet enrichment:
[ 3.800 ] (percentage by weight to the nearest tenth percent).
(1)
Average Assembly Burnup: [
24
] GWD/MTU (m)
Comments:
(NOTE:
Your comments will be printed in the comments section).
.GE:
Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.1 (nl List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/036 is unique and not to be confused with 5203/036)
List of unique assembly identifiers for group ID: 01C02 LYB813 LYB814 LYB815 LYB816 LYB817 LYB818 LYB819 LYB820 LYB821 LYB822 LYB823 LYB824 LYB826 LYB827 LYB828 LYB829 LYB830 LYB831 LYB832 LYB833 LYB834 LYB835 LYB836 LYB837 LYB838 LYB839 LYB841 LYB842 LYB843 LYB844 LYB845 LYB846 LYB848 LYB849 LYB850 LYB851 LYB852 LYB853 LYB854 LYB855
.B856 LYB857 LYB858 LYB859 LYB861
- LYB862 LYB863 LYB864 LYB865 LYB866 LYB867 LYB868 LYB869 LYB870 LYB871 LYB872 LYB873 LYB874 LYB875 LYB876 LYB877 LYB878 LYB879 LYB880 LYB881 LYB882 LYB883 LYB884 LYB885 LYB886 LYB887 LYB888 LYB889 LYB890 LYB891 LYB892 LYB893 LYB894
- LYB895 LYB896 LYB898 LYB899 LYB900 LYB901 LYB902 LYB903 LYB904 LYB905 LYB906 LYB907 LYB908 LYB909 LYB910 LYB911 LYB912 LYB913 LYB914 LYB915 LYB916 LYB917 LYB918 LYB919 LYB920 LYB921 LYB922
.B923 LYB924 LYB925 LYB926 LYB927
Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36)
List of unique assembly identifiers for group ID: 01C02 LYB929 LYB931 LYB932 LYB933 LYB934 LYB935 LYB936 LYB937 LYB938 LYB939 LYB940 LYB941 LYB942 LYB943 LYB944 LYB945 LYB946 LYB947 LYB948 LYB949 LYB951 LYB952 LYB953 LYB954 LYB955 LYB956 LYB957 LYB958 LYB959 LYB960 LYB961 LYB962 LYB963 LYB964 LYB965 LYB966 LYB967 LYB968 LYB969 LYB970 LYB971 LYB97 2
.GE:
10 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel asse11bly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36l List of unique assembly identifiers for group ID: OlDOl LYBOOl LYB002 LYB008 LYB012 LYB016 LYB024 LYB031 LYB032 LYB034 LYB038 LYB042 LYB043 LYB044 LYB045 LYB047 LYB056 LYB057 LYB061 LYB062 LYB064 LYB065 LYB066 LYB067 LYB070 LYB073 LYB074 LYB078 LYB084 LYB087 LYB095 LYB096 LYB098 LYB108 LYB116 LYBll 9 LYB121 LYB123 LYB125 LYB126 LYB130
.137 LYB138 LYB141 LYB142 LYB143
- LYB144 LYB145 LYB146 LYB147 LYB148 LYB150 LYB155 LYB156 LYB157 LYB165 LYB166 LYB167 LYB168 LYB173 LYB176 LYB177 LYB179 LYB182 LYB184 LYB186 LYB188 LYB194 LYB196 LYB199 LYB206 LYB207 LYB212 LYB215 LYB216 LYB217 LYB219 LYB223 LYB230
- LYB231 LYB235 LYB238 LYB240 LYB241 LYB243 LYB244 LYB247 LYB248 LYB250 LYB251 LYB252 LYB254 LYB255 LYB256 LYB257 LYB258 LYB261 LYB266 LYB267 LYB268 LYB269 LYB272 LYB277 LYB278 LYB282 LYB286
.290 LYB297 LYB298 LYB305 LYB306
11 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility) for the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/036)
List of unique assembly identifiers for group ID: 01001 LYB307 LYB308
12 Reactor Name: HOPE CREEK NUCLEAR FUEL* DATA FORM 3.2 Listing of Temporarily Discharged Fuel NOTE: Temporarily discharged fuel is defined as fuel which was irradiated in the previouse cycle (cycle N) and not in the following fuel cycle (cycle N+l), and which you have definite plans to irradiate in a subsequent fuel cycle.
(a)
Cycle No.:
[02 J (bl Cycle End Date:
[19890900]
(c)
Number of Assemblies: [
0 (d)
List the unique fuel assembly identifiers for the assemblies meeting this description:
NO ASSEMBLIES DECLARED AS TEMPORARILY DISCHARGED DURING THIS REPORTING PERIOD.
13 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.3 Changes in Permanently Discharged Status List any assemblies which were reported as permanently discharged (on the October 1983 Annex B submission) but which have been reinserted during the last reporting period.
NOTE:
These data are to be supplied when the assembly is actually reinserted into the reactor, not when you make a decision to reinsert a permanently discharged assembly.
NOTE:
When the assemblies listed below are again permanently discharged they must be reported in Section 3.1.
List the unique fuel assembly identifiers for the assemblies meeting this description:
NO ASSEMBLIES CHANGED THEIR ANNEX B STATUS DURING THIS REPORTING PERIOD.
14 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.4 Shipment and Change of Ownership of Irradiated Fuel For any assemblies which during the last reporting period were shipped to another storage site or which changed ownership, attach photocopies of the DOE Form 741 (including the unique assembly identifiers, consis-tent with prior Form RW-859 submittals) completed for the transfer.
NOTE:
These assemblies must have been reported as permanently discharged.
If no DOE Form 741 reflects the shipment or change of ownership of irradiated fuel (for example, movement of irradiated fuel to another on-site storage facility), complete the following:
Group Description for Permanently Discharged Fuel Which Changed Storage Site or Ownership:
NO SHIPMENT DATA ENTERED INTO THE SYSTEM.
.GE:
15 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.0 Cycle Projections 4.1 (a)
(b)
( c)
(d)
(e)
CYCLE CYCLE NUMBER OF NUMBER OF CYCLE BURN UP NUMBER SHUTDOWN UN IRRADIATED REINSERTED (EFFECTIVE FULL DATE ASSEMBLIES ASSEMBLIES POWER DAYS)
(CCYYMMOD)
INSERTED IN CYCLE N+l 02 (N) (Actual) 19890900 232 462 03 (Actual/Projected)
(N + 1) 19910100 264 417 04(N+2) 19920900 264 520 05(N+3) 19940300 248 47 8 06(N+4) 19950900 232 478 (N + 5) 19970300 232 478
~TE: Cycle "N" is the cycle whose shutdown prompted submission of this form as reported in question 1.4.
NOTE:
Reinserted assemblies are defined as previously irradiated assemblies which were not inserted in the last cycle (cycle N),
but which are inserted in this cycle (cycle N+l).
.GE:
16 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.2 List the unique assembly identifiers for the assemblies counted in question 4.1, column (c) for the current cycle (N+l).
LYT305 LYT306 LYT307 LYT308 LYT309 LYT310 LYT311 LYT312 LYT313 LYT314 LYT315 LYT316 LYT317 LYT318 LYT319 LYT320 LYT321 LYT322 LYT323 LYT324 LYT325 LYT326 LYT327 LYT328 LYT329 LYT330 LYT331 LYT332 LYT333 LYT334 LYT335 LYT336 LYT337 LYT338 LYT339 LYT340 LYT341 LYT342 LYT343 LYT344 LYT345 LYT346 LYT347 LYT348 LYT349 LYT350 LYT351 LYT352 LYT353 LYT354
.T355 LYT356 LYT357 LYT358 LYT359 LYT360 LYT361 LYT362 LYT363 LYT364 LYT365 LYT366 LYT367 LYT368 LYT369 LYT370 LYT371 LYT372 LYT373 LYT374 LYT375 LYT376 LYT377 LYT378 LYT379 LYT380 LYT381 LYT382 LYT383 LYT384 LYT385 LYT386 LYT387 LYT388 LYT389 LYT390 LYT391 LYT392 LYT393 LYT394 LYT395 LYT396 LYT397 LYT398 LYT399 LYT400 LYT401 LYT402 LYT403 LYT404 LYT405 LYT406 LYT407 LYT408 LYT409 LYT410 LYT411 LYT412 LYT413 LYT414
.T415 LYT416 LYT417 LYT418 LYT419
.GE:
17 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.2 List the unique assembly identifiers for the assemblies counted in question 4.1, column (c) for the current cycle tN+ll.
LYT420 LYT421 LYT422 LYT423 LYT424 LYT425 LYT426 LYT427 LYT428 LYT429 LYT430 LYT431 LYT432 LYT433 LYT434 LYT435 LYT436 LYT437 LYT438 LYT439 LYT440 LYT441 LYT442 LYT443 LYT444 LYT445 LYT446 LYT447 LYT448 LYT449 LYT450 LYT451 LYT452 LYT453 LYT454 LYT455 LYT456
- LYT457 LYT458 LYT459 LYT460 LYT461 LYT462 LYT463 LYT464
-465 LYT466 LYT467 LYT468 LYT469 T470 LYT471 LYT472 LYT473 LYT474 LYT475 LYT476 LYT477 LYT478 LYT479 LYT480 LYT481 LYT482 LYT483 LYT484 LYT485.
LYT486 LYT487 LYT488 LYT489 LYT490 LYT491 LYT492 LYT493 LYT494 LYT495 LYT496 LYT497 LYT498
'LYT499 LYT500 LYT501 LYT502 LYT503 LYT504 LYT505 LYT506 LYT507 LYT508 LYT509 LYT510 LYT511 LYT512 LYT513 LYT514 LYT515 LYT516 LYT517 LYT518 LYT519 LYT520 LYT521 LYT522 LYT523 LYT524
. LYT525 LYT52&
LYT527 LYT528 LYT529
.530 LYT531 LYT532 LYT533 LYT534
18 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.2 List the unique assembly identifiers for the assemblies counted in question 4.1, column (c) for the current cycle (N+l).
LYT535 LYT536 LYT537 LYT538 LYT539 LYT540 LYT541 LYT542 LYT543 LYT544 LYT545 LYT546 LYT547 LYT548 LYT549 LYT550 LYT551 LYT552 LYT553 LYT554 LYT555 LYT556 LYT557 LYT558 LYT559 LYT560 LYT561 LYT562 LYT563 LYT564 LYT565 LYT566 LYT567 LYT568
19 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.3 List the unique assembly identifiers for the assemblies counted in question 4.1, column tdl.
NO ASSEMBLIES WERE REINSERTED DURING CYCLE N+l
20 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth.. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTUI CYCLE:
[ 03 l I N + 1 I 01D02 196 2.480 28 OlEOl 68 2.780 29
21 Reactor Naffie: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
!Weight Percent)
(GWD/MTUl CYCLE:
[ 0 4 l ( N + 2 )
01E02 2.780 31 02F01 104 3.000 33 02G01 128 2.990 32 03H01 12 2.990 27
22 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/HTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ os I ( N + 3 )
03H02 44 2.990 31 03101 188 3.000 33 0.000 0.000
23
~eactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
!Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 06 l ( N + 4 )
03H03 2.990 32 03I02 12 3.000 32 04J01 104 3.240 36 04K01 108 3.240 37
24 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel These projections of permanently discharged fuel shall be reported on a group basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.
NOTE: Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.
Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)
(Discharged)
(Weight Percent)
(GWD/MTU)
CYCLE:
[ 07 l ( N + 5 )
04J02 16 3.240 37 04K02 36 3.240 37 05L01 96
- 3. 470 39 OSMOl 84 3.460 38
25 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 6.0 Fuel Consolidation Data_
6.1 If your company consolidated fuel assemblies from this reactor since the last report, list the unique assembly identifiers of the assemblies that were consolidated.
NO ASSEMBLIES WERE CONSOLIDATED DURING THIS REPORTING PERIOD.
6.2 How many canisters of fuel bearing components were produced from the above consolidation [ 0 ] canisters.
~GE:
26 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 7.0 Defective Assembly Data Please list the assemblies that were permanently discharged during the last reporting period and which are classified as defective as described in Section 7.0, Appendix A (Page A-6) or which are currently classified as defective and were not reported as such on previous submissions.
NOTE: These assemblies MUST have also been described in Section 3.1.
NO ASSEMBLIES WERE LISTED AS DEFECTIVE DURING THIS REPORTING PERIOD.
27 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[l.7(A)]
THE CALCULATION OF THE DATE IN SECTION 1.7 DOES NOT TAKE INTO ACCOUNT STORAGE SPACES NEEDED FOR AN "OPERATIONAL" FULL CORE DISCHARGE CAPABILITY. NOTE THAT AN OPERATIONAL FULL CORE DISCHARGE WILL ALLOW FOR DISCHARGE OF 764 BUNDLES FROM Form
Reference:
[1.?(B)]
THE CORE INTO THE POOL AND IT ALSO MAKES AVAILABLE ADEQUATE
- OF SPACES NEEDED TO STORE DUMMY BUNDLES, SOURCES, TOOLS, SPECIMENS AND ACCOUNT FOR BAD CELLS THAT MAY BE UNAVAILABLE FOR SPENT FUEL STORAGE. DEFINING THE FULL CORE DISCHARGE Form
Reference:
[1.7(Cl]
4 ABILITY FOR HOPE CREEK AS EQUIVALENT TO 1000 SPACES, THEN E CREEK WILL LOSE THIS CAPABILITY BEGINNING CYCLE 14 ARCH - MAY 2006). THIS IS THE CRITICAL DATE FOR HOPE CREEK Form
Reference:
[2.3Fl ]
CUREENTLY 1260 STORAGE SPACES ARE AVAILABLE TO STORE SNF.
ADDITIONALLY 30 SPACES ARE AVAILABLE TO STORE CONTROL RODS, CONTROL ROD GUIDE TUBES AND DEFECTIVE FUEL CONTAINERS. PSE&G PLANS TO RACK THE COMPLETE POOL TO ITS MAXIMUM ESTABLISHED Form
Reference:
[2;3F2 ]
SITE CAPACITY WHICH IS 3976.
Form
Reference:
[2.4(Bl]
. LIMITING FACTOR IS CRANE CAPABILITY. NOTE THAT THE 150 TONS IS THE MAXIMUM CASK WEIGHT AND THE WEIGHT OF ITS CONTENTS LUDING TOLERANCES THAT CAN BE HANDLED AT THIS REACTOR E.
Reactor Name: HOPE CREEK
I*
28 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form
Reference:
[3.3 THERE IS NO DATA FOR SECTION 3.3 BECAUSE ANNEX B WAS NOT SUBMITTED FOR HOPE CREEK.
Form
Reference:
[3.4 THERE IS NO DATA FOR SECTION 3.4 BECAUSE FUEL ASSEMBLIES HAVE NOT BEEN SHIPPED FROH HOPE CREEK SITE TO ANY OTHER SITE OR CHANGED OWNERSHIP..
Form
Reference:
[6.0
~EL BUNDLES HAVE NOT BEEN CONSOLIDATED AT HOPE CREEK.
Form
Reference:
[7.0 NO FUEL BUNDLES WERE CLASSIFIED AS DEFECTIVE FROM THE LAST OUTAGE.
Reactor Name: HOPE CREEK