ML18093A640

From kanterella
Jump to navigation Jump to search
Forwards Printouts of IBM-PC Diskettes Containing RW-859 Nuclear Fuel Data for Period Ending 871231
ML18093A640
Person / Time
Site: Salem, Hope Creek, 05000000
Issue date: 02/12/1988
From: Corbin McNeil
Public Service Enterprise Group
To:
ENERGY, DEPT. OF
References
NLR-N88020, NUDOCS 8802190014
Download: ML18093A640 (77)


Text

)_ -*

Public Service Electric and Gas Company I

Corbin A. McNeil!, Jr.

  • Senior Vice President -

Nuclear Public Service Electric and Gas Company P.O. Box 236, Han cocks Bridge, NJ 08038 609 339-4800 FEB 1 2 1988 NLR-N88020 Energy Information Administration (EI-53)

u. s. 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 AND 50-354 Puhl ic Service Electric and Gas* Company ( PSE&G) hereby submits the enclosured IRM-PC diskettes for Salem Units 1 and 2 and Hope Creek Generating Station containing the "RW-859 Nuclear Fuel Data" for the period ending December 31, 1987, in accordance with the Nuclear Waste Policy Act of 1982 and the reporting schedule selection Option B (Reference 1).

Also attached are properly certified orintouts of each diskette, with appropriate qualifying comments.

If you have any questions, please contact Mr. Quresh A. Dahodwala at (609) 339-3327.

Enclosures

References:

Sincerely, (1)

Letter from E. Rosenfeld (PSE&G) to Kathy Gibbard (EIA-DOE), Form RW-859 Reporting Schedule Selection Sheet, NFU 88-015, dated January 12, 1988.

,----;~---......,.~ **-----:-----

8802190014 880212 PitR ADOCI\\ 05000272

.P.... ** *********"***.-.. *.. _.ItC II.

Energy Information Administration 2

C Mr. G. w. Rivenbark USNRC Licensing Project Manager -

Hope Creek Mr.

R~ w. Borchardt USNRC Senior Resident Inspector -

Hope Creek Mr. D. C. Fischer USNRC Licensing Project Manager -

Salem Mr. T. J. Kenny USNRC Senior Resident Inspector -

Salem Mr. W. T. Russell, Administrator USNRC Region I Document Control Desk, USNRC Washington, DC 20555 Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 FEB 1 2 1988

PAGE:

Reactor Name: SALEM Reactor Code:4202 RlH59 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 En~rgy 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 relecting 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 choosen, any change in reporting schedule would require DOE concurrence.

For this submission, respondents must submit the revised Form RW-859 by February 15, 1988, for any reactor that has shut down and/or restarted (and involves a fuel status change)

  • during calendar year 1987. Respondents choosing option *a," who have a reactor in an extended shutdown status, wouid 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 fro1 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 resu1ed. Storage-only facilities which do not irradiate fuel shall complete thi~ form be February 15 of each year.

Failure to file after receiving EIA notification may result in criminal fines, civil penalties and otber sanctions as provided by the law. Data being collected on this form ~;re not considered to be confidential.

As described in Article VII! of the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Lelel Radioactive Waste, you also have a contractual oblig~tion to report any ~.?anges in the stat~s of assemblies covered by the one-time fee to the DOE ov Annex B of Appendix G of the Standard Contract.

1y Section 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Title Utility and Rea9tor Data Storage Site D_ita,.

Irradiated Fu~l Tr,acking Cycle Projec~10ns:: -

.1/ '.:<-*r**-.--t,-

Projectio~n/ f.~.'.~er.1anently Discharged Fuel Fuel Consol dat1orData*

Defective :sse~blY Data*:

Couents

/

Appendix A Instructions for Completing the Nuclear Fuel Data Form Appendix B Glossary of Terms Appendix C Software Instructions and Documentation for IBM-PC and Compatible Computers Please refer all questions regarding this form to:

Ms. Kathy Gibbard on (202) 586-1718.

Please return completed forms to:

Energy Information Administration - (EI-53)

U. S. Department of Energy Attn:

RW-859 Mail Stop BG-094 Washington, D.C.

20585 1

PAGE:

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 Reactor Name: SALEM 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, TBl, N20

[HANCOCKS BRIDGE, NJ

[08038 (609-339-3327 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:

[E. S. ROSENFELD

[MANAGER-NUCLEAR FUEL

[P.O. BOX 236

[NUCLEAR DEPT, TBl, N20

[HANCOCKS BRIDGE, NJ (08038 SIGIATUR!a~

Date: 2,h/n-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 frauduleµt statements as to any matter within its jurisdiction.

1. 4 Cycle Number for this report: [ 07 I 1.5 Reactor Operating License Expiration Date:

[ 200809 ) ( CCYYKM). *

1. 6 Projected Reactor Retftellent Date:

[ 201608 ] (CCYYMM)

Ji.;.:~.

~ -**-

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, absent spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?

(200009) (CCYYMM)

PAGE:

3 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 [ 4202 (b) Contributing Reactors

[4202 (b) Optional: Inventory fro1 Contributing Reactors [

2.2 (a) Licensed Site Capacity :

(b) Maximum Established Site Capacity (c) Current Inventory (excluding ( d) )

(d) Number of Canisters (excluding (c))

PllR BllR

[1170]

(1170]

[.

[ 464]

O]

Reactor Name: SALEM 0

0.

HTGR (e)

NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION

PAGE:

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?

(al (Xl No plans to increase (b)

( ) Rod Consolidation (cl

( l Dry Cask storage (d)

( ) Reracking (el

( ) Transshipment (f) Other (Please explain:

(al 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

]

(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 ] tons

PAGE:

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

~uring 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 fro1 or to your site or which have changed ownership during the la~t reporting period.

PAGE:

Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharge Fuel

.a) Group Name

[3 (Optional)

(b)

Number of Assemblies

( 1 (c)

Cycle No.:

(07 l (d)

Cycle End Date:

(19871002] (CCYYMMDD)

(el Group Location

[ 4202] (See Appendix A, Table 2, Storage Site Codes)

(f) Contract Nu11ber

( 4480] (See Appendix A, Table l, Contract Numbers)

(g) Fuel/Vendor Type

[WST] (See Appendix A, Table 3, Fuel/Vendor Types)

(h)

Nominal Assembly Weight, in Kilograms of initial heavy metal:

[ 461.000]

Kilograms (i)

Nominal Initial Enrichment:[ 3.300 J (Percentage by weight to the nearest tenth percent}

(j)

Does this group employ varying enrichments within an assembly ? [NJ (Y /Nl (kl If you answered yes to question J.l(j}: If the maximum pellet enrich1ent is one percent (or greater than one percent~ above the nominal enrichment reported in question J.l(i}, please specify the 1aximum pellet enrichment:

[ O. 000 ] (percentage by weight to the nearest tenth percent).

Average Assembly Burnup: [

44 - ] GWD/MTU (ml Comments:

(NOTE:

Your comments will be printed in the comments section).

PAGE:

Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharge Fuel al Group Name

[6

] (Optional)

(bl Number of Assemblies

[10 (cl Cycle No.:

[07 l (d)

Cycle End Date:

[19871002] (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

[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 tenth percent)

(j)

Does this group employ varying enrichments within an assembly ? [NJ (Y/N)

(kl 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).

Average Asse1bly Burnup: [

36

] GWD/MTU (m)

Comments:

(NOTE:

Your comients will be printed in the co11ents section).

PAGE:

Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Pernanently Discharge Fuel a)

Group Nate (7

I (Optional)

(b)

Number of Assemblies

[ 8 (c)

Cycle No.:

[07 I (d)

Cycle End Date:

[19871002) ( 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

[WST] (See Appendix A, Table 3, Fuel/Vendor Types)

(h)

No1inal Assembly Weight, in Kilograms of initial heavy metal:

[ 459.000)

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)

(k) 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 I [percentage by weight to the nearest tenth percent).

Average Assembly Burnup: [

41

] GWD/MTU (m)

Colllents:

[NOTE:

Your comments will be printed in the comments section) *

?AGE:

9 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharge Fuel

  • 1*1 Group Nam:

[SA l (Optional)

(b)

Number of Assemblies

[40 (c)

Cycle No.:

[07 l (d)

Cycle End Date:

[19871002] (CCYYMMDD)

(e)

Group Location

[4202] (See Appendix A, Table 2, Storage ~ite Codes)

(f) Contract Number

[4480] (See Appendix A, Table l, Contract Numbers)

(g)

Fuel/Vendor Type

[WST] (See Appendix A, Table 3, Fuel/Vendor Types)

(h)

Nominal Asse1bly Weight, in Kilograms of initial heavy metal:

[ 461.000]

Kilograms (i) Nominal Initial Enrichment: [ 3.400

] (Percentage.by weight to the nearest tenth percent)

(j)

Does this group e1ploy varying enrichments within an assembly ? [NJ (Y/N)

(k) If you answered yes to question 3.l(j): If the maximum pellet enrich1ent 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: [

37

] GVD/MTU (11)

Couents:

(NOTE:

Your comments will be printed in the co1111ents section).

~ *. '.

l

PAG-E:

10 Reactor Name: SALEM NUCLEAR FUEL DATA FORM Section 3.1 Group Description for Permanently Discharge Fuel Group Name

[SB

  • l (Optional)

Number of Assemblies

[26 l (c)

Cycle No.:

[07 l (d) Cycle End Date:

[19871002] (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

[WST] (See Appendix A, Table 3, Fuel/Vendor Types)

(h)

Nominal Asse1bly Weight, in Kilograas of initial heavy metal:

[ 460.000]

Kilograms (i) Nominal Initial Enrich1ent:[ 3.800

] (Percentage by weight to the nearest tenth percent)

(j)

Does this group employ varying enrichments within an assembly ? [NJ ( Y /N)

(k) If you answered yes to question 3.l(j): If the maximu1 pellet enrichment is one percent (or greater than one percent) above the nominal enrichment reported in question 3.l(i), please specify the maximu1-pellet_enrichment:

[ 0.000 ] (percentage by weight to the nearest tenth percent).

~) Average !sselbly Burnup: [

34

] GWD/MTU (1)

Co11ents:

(NOTE:

Your comaents will be printed in the comments section)

  • PAGE:

11 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility) for C55 the assemblies in this grouping: (For example: 5201/D36 is unique and not to be confused with 5203/D36J List of unique assembly identifiers for group ID: 3 1

PAGE:

12 NUCLEAR FUEL DATA FORM Reactor Name: SALEM 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/D36)

List of unique assembly identifiers for group ID: 6 F12 F23 F29 F30 F31 F36 F44 F49 FSO F51 1

PAGE:'

13 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 confus*d with 5203/036)

List of unique assembly identifiers for group ID: 7

.GS Gl9 G37 G38 G45 G48 G49 G51 1

PAGE:

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 assenbly identifiers for group ID: SA Hl H2 HJ H4 HS H6 H7 HS H9 HlO Hll H12 H14 HlS H17 H18 H19 H20 H21 H22 H23 H24 H26 H27 H28 H29 H30 H31 H32 H34 H35 H36 H38 H39 H40 H43 H44 H45 H47 H48

15 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.1 (n) List the unique fuel assembly identifiers (within the utility) for the assemblies in this qroupinq: (For example: 5201/036 is unique and not to be confused with '5203/036)

List of unique ass*ell.bly identifiers for qroup ID: SB H53 H54 H55 H56 H57 H58 H59 H61 H62 H64 H65 H66 H67 H68 H69 H?O H71 H72 H73 H76 H78 HSO H81 H82 H83 H84 1

PAGE:

16 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.2 Listi~g 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.:

[07 J

[b)

Cycle End Date:

[19871002]

(c)

Number of Assemblies: [ 16 1

[d) List the unique fuel assembly identifiers for the *assemblies meeting this description:

F06 F15 F32 F33 F35 F38 F46 F54 G53 G54 G55 G56 H74 H75 H77 H79

PAGE:

17 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.3 Chanqes in Permanently Discharqed Status List any assemblies which were reported as permanently discharged (on he* October 1983 Annex B submission I 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 meetinq this description:

NO ASSEMBLIES CHANGED THEIR ANNEX B STATUS DURING THIS REPORTING PERIOD

  • 1

18 Reactor Name: SALEM NUCLEAR FUEL DATA FORK 3.4 Shipment and Change of Ownership of Irradiated Fuel r any assemblies which during the last reporting period were shipped 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.

1

PAGE:

19 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.0 Cycle Projections 4.1

.(a)

(b)

(c)

(d) -

(e)

YCLE CYCLE NUMBER OF NUMBER OF CYCLE BURNUP NUMBER SHUTDOWN UNIRRADIATED REINSERTED (EFFECTIVE FULL DATE ASSEMBLIES ASSEMBLIES POWER DAYS)

(CCYYMM)

INSERTED IN CYCLE N+l 07 (N Actual) 19871002 84 438 08 (N + 1) 198903 84 17 423 09 (N + 2) 199009 84 471 10 (N + 3) 199112 68 387 11 (N + 4) 199304 80 413 12 (N + 5) 199409 84 439 NOTE: Cycle "N" is the cycle whose shutdown prompted submission of this for as reported in question 1.4.

NOl'E: Reinserted assemblies are defined as previously irradiated asse1blies which were not inserted in the last cycle (cycle N),

but which are inserted in this cycle (cycle N+l).

. PAGE:

20 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.2 Asselbly identifiers for unirradiated assemblies inserted.into cycle N+l 2 List the unique assembly; identifiers for the assemblies counted in question 4.1,.coluu (c) for the current cycle (N+l).

KOl K02 K03 K04 KOS K06 K07 KOS K09 KlO Kll K12 K13 K14 Kl5 Kl6 K17 K18 Kl9 K20 K21 K22 K23 K24 K25 K26 K27 K28 K29 K30 K31 K32 K33 K34 K35 K36 K37 K38 K39 K40 K41 K42 K43 K44 K45 K46 K47 K48 K49 KSO 1

K52 K53 K54 KSS K57 K58 K59 K60 K61 K62 K63 K64 K65 K66 K67 K68 K69 K70 K71 K72 K73 K74 K75 K76 K77 K78 K79 KSO K81 K82 K83 K84

PAGE':

21 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.3 Assembly identifiers for irradiated assemblies reinserted into cycle N+l 3 List the unique assembly identifiers for the assemblies counted in question 4.1, coluan (d).

FOS F28 F40 F53 GOl GlO GlL GlS Gl6 G30 G33 G34 G39 H16 H33 H42 H46

- l

PAGE:

22 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel se projections of permanently discharged fuel shall be reported on a up basis, where a group is defined in Section 3.0. This information reflects the_ current plans of your company.

NOTE:

Nominal 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 Asse1blies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU}

CYCLE: [ 08 l ( H + 1 )

6 8

3.400 42 6

4 3.400 40 7

g 3.400 30 SA 4

3.400 36 g

56 3.800 38 1

PAGE:

23 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Per1anently Discharged Fuel ese projections of permanently discharged fuel shall be reported on a roup basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.

NOTE:

Nominal 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 No1inal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 09 l ( N + 2 )

3 1

3.300 26 3.400 32 9

16 3.800 45 10 64 3.800 38 t

1

PAGE:'

24 Reactor Name: SALEM NUCLEAR FUEL DATA FORK 5.0 Projections of Permanently Discharged Fuel ese projections of pernanently discharged fuel shall be reported on a up basis, where a group* is defined in Section 3.0. This information fleets the current plans of your company.

NOTE:

Nominal 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:

[ 10 l ( N + 3 )

1 3.300 23 58 3.400 40 SA 4

3.400 36 9

12 3.800 38 10 20 3.800 44 11 52 4.000 36

PAGE:

25 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel ese projections of permanently dis~harged fuel shall be reported on a roup basis, where a group is defined in Section 3.0. This information_

reflects the current plans of your company.

NOTE:

Nominal Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GWD/MTU.

Group Ma11e Nu11ber of No1inal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 11 I ( N + 4 )

1 3.300 28 7

4 3.400 43 SA 4

3.400 43 SB 4

3.800 47 11 32

4. 000 45 12A 8

4.000 35 12B 24 3.600 35

PAGE:

26 Reactor. Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Per1anently Discharged Fuel ese projections of permanently discharge~ fuel shall.be reported on a roup basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.

,NOTE:

Nominal Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GllD/MTU.

Group Name Number of Nominal Initial Average Assemblies Enrichment Discharge 8urnup in the Group (Optional)

(Discharged)

(lleight Percent)

(GllD/MTU)

CYCLE: [ 12 ].. ( N + 5 )

3 1

3.300 32 12A 20 4.000 42 128 8

3.600 39 13A 32 4.000 34 138 28 3.600 37 1

PAGE:

27 Reactor Name: SALEM NUCLEAR FUEL DATA FORM

  • 6.0 Fuel Consolidation Data 6.1 If your company consolidated fuel asse1blies 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 fro1 the above consolidation [ 0 ] canisters.

t

PAGE:

28 NUCLEAR FUEL DATA FORM Reactor Name: SALEM 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.

-~*-

PAGE:

29 NUCLEAR FUEL DATA FORM 8.0 COMMENTS orm

Reference:

[2.2e-ll Please note that 29 cells *out of 1170 cells are unusable for SNF storage. 127 cells are swollen, 1 is capped and 1 contains Bora! Rack Specimen). [continued below]

Form

Reference:

[ 2. 2e-2]

Additionally, 25 cells are unavailable for SNF storage.

These cells contain non-fuel-bearing irradiated materials 110 cells - BPR!s + RCCAs, 5 cells ~ Hubs of BPR!s and RCCAs

, 3 cells - Thimble Baskets, 3 Cells - Trash Bskts,[contd.]

Form

Reference:

[2.2e-3]

1 cell - Thilble Tubes, 1 cell - chopped rodlets, 1 cell -

Irradiated Specimen Basket and 1 cell contains du1my fuel asse1bly). These cells may be available for SNF storage upon ship1ent of such non-fuel-bearing materials.

m

Reference:

[2.4a-1]

Please note that 110 tons is the 1axi1u1 cask weight including its contents that can be handled at this reactor site.

Fora

Reference:

[2.4a-2]

Software BUG: Nulber entered for 2.4(a) is not labeled "tons" in the printout.

For1

Reference:

[2.4b Limit is cask handling crane capability

  • Reactor Name: SALEM

PAGB:

30 NUCLEAR FUEL DATA FORM 8.0.COMMENTS orm

Reference:

[3.l(g)]

Software BUG:

Only three of the five letter Fuel/Vendor Type "17WST", "iST" appear in printed output.

Form

Reference:

[3.l[i)]

Software BUG: No1inal enrich1ent cannot be entered immed.

after a Section 3.1 Group Description is added. Software user must co1e back later and edit this quantity in order to enter value.

Form

Reference:

[J.2[d)]

Software BUG:

Bad to use the DBASE program to relove extra records fro1 the file ASMBiORK.DBF.

Then the file was packed by DBASE.

Then used the "Initialize Index Files" option of Ri859 software. Problem went away

  • rm

Reference:

(3.3 Section 3.3 is blank because there are no revisions to the Annex B per1anently discharged F/A status since the 1987 report.

Form

Reference:

(3.4 Section 3.4 is blank because F/As have not been shipped to any other storage site or changed ownership.

Form

Reference:

[4.l(b)J'.,

'*:;,-,,<<,~,,

    • ~~.~~~;:~i~*~*.
  • Software BUG: The sofware reqJests. CCYYMMDD for the shutdown date although the printout is labeled CCYYMM. The value given for the current cycle is used for printout of ite1 3.l[d) when 3.l[c) is the current cycle
  • Reactor Name: SALEM 1

PAGE:

31 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form

Reference:

(5.0-1 )

Software BUG:

Only integer quantities can be entered for Section 5.0 average discharge burnup, GWD/MTU.

Form

Reference:

(5.0-2 ]

Software BUG: Records in file "GROUP.DBF" with group field blank were marked for deletion and then the DBASE "PACK" command was given. This made lines with *o* assemblies in a blank group disappear from the printout.

Form

Reference:

[ 6. 0 Fuel assemblies from Salem 1 have not been consolidated since the last report.

~*

Reference:

[7.0-1 I Fuel assembly G46 has been classified as defective by PSE&G as it has grid damage. It was a te1porarily discharged F/A from Cycle 6 and planned for reinsertion in Cycle 8.

However, no mention of it was made in Section 7.0 [contd.]

Form

Reference:

(7.0-2 ]

because it did not fall under any category described in Appendix A of Section 7.0.

Form

Reference:

[8.0 Software BUG:

Some comment portions of question responses become lost. Users will find it best just to add these comments directly to Section 8.

t Reactor Name: SALEM

PAGE:

32 NUCLEAR FUEL DATA FORM Reactor Name: SALEM 1

8.0 COMMENTS

  • .')

PAGE:

1 RW-859 U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 20585

. NUCLEAR FUEL DATA FORM Reactor Name: SALEM Reactor Code:4203 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 use Section 761 et. seq.}, and the Nuclear Waste Policy Act of 1982 (42 use 10101 et. seq.}. This form should be co1pleted 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 fro1 commercial nuclear power plants.

This form shall be submitted (a) 90 days after a cycle startup with data

.relecting the statul 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 choosen, any change in reporting schedule would require DOE concurrence. For this submission, respondents must sub1it the revised For1 Ri-859* by February 15, 1988, for any reactor that has shut down and/or restarted (and involves a fuel status change) during calendar year 1987. Respondents choosing option "a,* who have a reactor in an extended shutdown status, would be required to sub1it the form only if the shutdown extends to 365 days, and thereafter, only if a fuel status change occurs (e.g., discharging fuel fro1 the core). Only one for1 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 fora be February 15 of each year.

Failure to file after receiving EIA notification 1ay result in cri1inal fines, civil penalties and other sanctions as provided by the law. Data being collected on this for1 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 1racking Cycle Project~;m~*t:,)

Projections of!ferlanently Discharged Fuel Fuel consolid~~J,p_;;;pa'ta~

Defective Asselbly*Data:

Couents Appendix A Instructions for Completing the Nuclear Fuel Data Form Appendix B Glossary of Ter1s Appendix C Software Instructions and Docu1entation for IBM-PC and.Co1patible Computers

  • Please refer all questions regarding this for1 to:

Ms. Kathy-Gibbard on (202) 586-1718.

Please return completed for1s to:

Energy Information Ad1inistration - (EI-53)

U. S. Department of Energy Attn: RW-859 Mail Stop BG-094 Washington, D.C.

20585 I

HGE:

Reactor Name: SALEM NUCLEAR FUEL DATA FORM 1.0 UTILITY AND REACTOR DATA

.1.1 Utility Name:

Mailing Address:

[PUBLIC SERV. ELEC. AND GAS CO.

. [80 PARK PLAZA

[NEWARK, HJ 07101

[

1.2 Person who may be contacted periodically to verify information provided on this form:

Name:

Title:

Mailing Address:

Telephone Hu1ber:

[Q. Z. DAHODWALA

[SENIOR STAFF ENGINEER

[P.O. BOX 236

[NUCLEAR DEPT, TBl, N20

[HANCOCKS BRIDGE, NJ 08038

[

(609-339-3327 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:

[E. S~ ROSENFELD

[MANAGER-NUCLEAR FUEL

. [P.O. BOX 236

[NUCLEAR DEPT, TBl, N20

[HANCOCKS BRIDGE, NJ 08038 srnniu1s: 5 4. ~ate:Hrr 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 Nu1ber for this report: [ 04 ]

1.5 Reactor Operating License Expiration Date:

[ 200809 ] (CCYYMM)

  • '"< *::*~~~.
1. 6 Projected Reactor Retil-e1ent Date:

[ 202004 ] (CCYYMM) \\\\'.';~:~**...

.. -/~:~:-~~-:.;.-.~~r-_ -

1.7 Based on your co1pany's current plans for spent fuel storage, what is the date when you esti1ate you would not be able to operate this reactor, absent spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?

(200403] (CCYYMM)

PAGE:

3 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 (bl Contributing Reactors

[4203 (b) Optional: Inventory from Contributing Reactors [ 0 0

PWR BWR 2.2 (a) Licensed Site Capacity :

[1170]

(b) Maximu1 Established Site Capacity

[1170)

!cl Current Inventory (excluding !di)

[ 224)

!di Number of Canisters (excluding (c) l

1)

Reactor Name: SALEM 0

HTGR

!el

NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION

PA~E:

3 2.4 2.5 4

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)

(X)

No plans to increase (b)

( ) Rod Consolidation (c)

( ) Dry Cask storage (d)

( ) Reracking (el

( ) Transshipment

( f) Other (Please explain:

(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 J

(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 1axiu1um weight cask that may be processed? [ J (c) If Yes to 2.5(b), what.was the estimated maxiumum cask weight?

[

0 J tons 2

PAGE:

5 Section 3.0 Irradiated Fuel Tracking Co1plete Section 3.1 for each grouping of assemblies for which no bsequent irradiation is planned or which were permanently discharged uring 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

  • 1ast reporting period
  • l

PAGS:

Reactor Name: SALEM NUCLEAR FUEL DATA FORM 3.2 Listing of Temporarily Discharged Fuel OTE: 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.:

[04 l (bl Cycle End Date:

[198809 J

(c)

Number of Assemblies: [ 0 2

(d) List the unique fuel assembly identifiers for the assemblies meeting this description:

NO ASSEMBLIES DECLARED AS TEMPORARILY DISCHARGED DURING THIS REPORTING PERIOD.

PAGE:

8 NUCLEAR FUEL DATA FORM Reactor Name: SALEM

  • 3.3 Changes in Permanently Discharged Status st any assemblies which were reported as permanently discharged (on e 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 chey 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.

PAGE:

9 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 another storage site or which changed ownership, attach photocopies f the DOE Form 741 (including the unique assembly identifiers, consis-tent with prior Form RW-859 submittalsl 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

  • PAGE:

10 Reactor Name: SALEM NUCLEAR FUEL DATA FORK 4.0 Cycle Projections 4.1

.al (b)

(cl (dl (e)

CYCLE CYCLE NUMBER OF NUMBER OF CYCLE BURNUP NUMBER SHUTDOWN UNIRRADIATED REINSERTED (EFFECTIVE FULL DATE ASSEMBLIES ASSEMBLIES POWER DAYS l (CCYYKM!

INSERTED IN CYCLE N+l 04 (N Actual) 198809 84 471 05 (N + 1) 199001 84 4

398 06 (N + 2 l 199103 60 367 07 (N + 3) 199209.

84 430 08 (N + 4) 199401 76 412 09 (N + 5) 199504 68 379 NOTE:

Cycle "N" is the cycle whose shutdown pro1pted submission of this for as reported in question 1.4.

, flE: _Reinserted assemblies are defined as previously irradiated assemblies which were not inserted in the last cycle (cycle Nl, but which are inserted in this cycle (cycle N+l).

PAGE':

11 Reactor Name: SALEM NUCLEAR FUEL DATA FORM

4. 2 Assellbly identifiers for u.nirradiated assemblies inserted in to cycle N+l 1.2 List the unique asse1bly. identifiers for the assemblies counted in question 4.1, colulln (c) for the current cycle (N+ll.

NO ASSEMBLIES WERE INSERTED DURING CYCLE N+l 2

PAGE*:

12 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 4.3 Assembly identifiers for irradiated assemblies reinserted into cycle N+l 4,J List the unique assembly identifiers for the assemblies counted in question 4.1, column Id).

NO ASSEMBLIES WERE REINSERTED DURING CYCLE N+l

PAGE:

13 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel hese projections of per1anently.discharged fuel shall be reported on a oup basis, where a group is defined in Section 3.0. This information eflects the current plans of your company.

NOTE:

Nominal Initial Enrichment in weight percent is to be reported to the nearest tenth. Average discharge burnup is to be in GVD/MTU.

Group Name Number of Nominal Initial Average Assemblies Enrich1ent Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GVD/MTU)

CYCLE:

[ 05 l ( N + 1 )

4 4

3.400 38 4

9 3.400 30 SA 12 3.800 42 56 3.600*

38

PAGE:

14 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel hese projections of pernanently discharged fuel shall be reported on a roup basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.

NOTE:

Nominal 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 No1inal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)

!Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 06 l ( N + 2 )

3 4

3.100 35 1

3.100 27 4

16 3.400 40 4

4 3.400 39 SA 8

3.800 34 6

16 3.600 40 7A 12 4.000 33 7B 20 3.600 34 2

PAGE:

15 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged. Fuel ese projections of permanently discharged fuel shall be reported on a roup basis, where a group.is defined in Section 3.0. This information reflects the current plans of your company.

NOTE:

Nominal Initial Enrich1ent in weight percent is to be reported to the nearest tenth. Average discharge burnup is to b~ 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 + 3 )

4 4

3.400 40 SA 1

3.800 34 7A 28 4.000 42 78 16 3.600 47 SA 16 4.000 34 88 8

. 3.600 37

PAGE:

16 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel ese projections of permanently discharged fuel shall be reported on a oup basis, where a group is defined in Section 3.0. This information

- reflects the current plans of your company.

NOTE:

Nominal 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: [ 08 l ( N + 4 )

3.100 29 SA 12 4.000 38 SB 28 3.600 40 9A 16 4.000 38 98 36 3.800 36

PAGE:

17 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel ese projections of permanently discharged fuel shall be reported on a cup basis, where a group is defined in Section 3.0. This information reflects the current plans of your company.

NOTE:

Nominal 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 Asse1blies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 09 I ( N + 5 )

4 4

3.400 41 5A 1

3.800 33 6

8 3.600 34 SA 4

4.000 46 9A 32 4.000 43 10!

16 4.000 32 lOB 32 3.600 34

PAG'E:

18 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 6.0 Fuel Consolidation Data

~.! If your coapany consolidated fuel asselllies fro1 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 fro1 the above consolidation [ 0 ) canisters.

J

PAG*E:

19 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 7.0 Defective Assembly Data

~lease list the assel1hlies 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.

PAGE:

20 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form

Reference:

-(2.2e-l]

Please note that 19 cells out of 1170 cells are unusable for SNF storage (18 cells are swollen, 1 cell contains Boral Rack Specimen). [continued below]

Form

Reference:

[2. 2e-2]

Additionally, 35 cells are not presently available for SNF storage. These cells contain non-fuel-bearing irradiated materials (26 cells - BPRAs + RCCAs; 3 cells - skeletons from F/A resonstitution; 2 cells ~ secondary [continued]

Fora

Reference:

[2.2e-3]

sources; l cell - Dullly F/A; l cell - fuel rod storage rack; l cell - trash basket; 1 cell - Irradiation Specimen Basket). These cells may be available for SNF storage upon ship1ent of such non-fuel-bearing materials.

orm

Reference:

[2.4(b)]

Limit is cask handling crane capability.

For1

Reference:

[2.4a-1]

Please* note that 110 tons is the maxi1u1 cask weight including its contents that can be handled at this reactor site.

Form

Reference:

[2.4a-2]

Software BUG: Hulber entered for 2.4(a) is not labeled "tons* in the printout

  • t Reactor Name: SALEM

I I.

PAGE:

21 NUCLEAR FUEL DATA FORM 8.0 COMMENTS orm

Reference:

[3.1 Software BUG:

Nothing is Jrinted for Section 3.1. Should print that no permanently discharged fuel changes since last report.

Fora

Reference:

[3.1&2 ]

Actual data for Sections 3.1 and 3.2 is not provided because no fuel movenent occurred during 1987. The next refueling outage (i.e. Cycle 4 to 5) is scheduled to begin in Sept.

1988.

Form

Reference:

[3.3 Section 3. 3 is blank because there are no revisions to the Annex B per1anently discharged F/A status since the 1987 report.

n

Reference:

[3.4 Section 3.4 is blank because F/As have not been shipped to any storage site or changed ownership.

Form

Reference:

[4.1 Please* note.that Cycle 5 has not actually begun. Hence, projected data is provided for Cycle 5.

Fora

Reference:

[4.l(b)

Software BUG: The sofware requests CCYYM!DD for the shutdown date although the printout is labeled CCYYMM.

The value given for the current cycle is used for printout of ite1 3.l(d) when 3.l(c) is the current cycle.

Reactor Name: SALEM 2

PAGE:

22 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form

Reference:

(4.2&3 ]

These sections are blank because no fuel 1ovenent occurred during 1987. Cycle 4 is currently in progress (began 12/20/

86l and is scheduled for shutdown Sept. 1988.

For1

Reference:

[5.0-1 l Software BUG: Only integer quantities can be entered for Section 5.0 average discharge burnup, GWD/MTU.

For1

Reference:

(5.0-2 ]

Software BUG: Records in file "GROUP.DBF" with group field blank were marked for deletion and then the DBASE "PACK" co11and was given. This made lines with *o* assemblies in a blank group disappear fro1 the printout.

~rm

Reference:

(6.0 Fuel assemblies from Sale1 2 have not been consolidated since the last report.

For1

Reference:

(7.0 This section is blank since no refueling or fuel 1ove1ent has occurred during 1987.

No new defects are known since last report.

For1

Reference:

[8.t

_i*-

Software BUG:

So1e.co11ent portions of question responses beco1e lost. Users will find it best just to add these co111ents directly to Section 8.

Reactor Name: SALEM

)

PAGE: -

23 Reactor Name: SALEM NUCLEAR FUEL DATA FORM 8.0 COMMENTS

PAGE:

Reactor Name: HOPE CREEK Reactor Cade:4201 Rll-859 U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 20585 FORM APPROVED NUCLEAR FUEL DATA FORM OMB Na. 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 use 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 co11.1ercial nuclear power plants.

This form shall be submitted (a) 90 days after a cycle startup with data relecting. 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 choasen, any change in reporting schedule would require DOE concurrence. For this submission, respondents must submit the revised Form RW-859 by February 15, 1988, for any reactor that has shut down and/or restarted (and involves a fuel status change) during calendar year 1987. Respondents choosing option "a,* who have a reactor in an extended shutdown status, would be required to *submit the for1 only if the shutdown extends to 365 days, and thereafter, only if a fuel status change occurs (e.g., discharging fuel fro1 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 resuaed. Storage-only facilities which do not irradiate fuel shall complete this form be February 15 of each year.

Failure to file after receiving IIA notification nai 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 asseablies covered by the one-time fee to the DOE on Annex B of Appendix G of the Stan~ard 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 Projecti0ilsi:1;>~:- -

... -...,,--,'~;:.?r_- *~. -,,

Projections of;~2e,i'.,ijneptly Discharged Fuel Fuel consolidatf:~,::Data,.:

Defective Assei'tiij:?o~ef*

Com&ents Appendix A Instructions for-Completing the Nuclear Fuel Data Fon Appendix B Glossary of Terms Appendix C Software Instructions.and Docu1entation for IBM-PC and Compatible Co1puters Please refer all questions regarding this for1 ta:

Ms. Kathy Gibbard on (202) 586-1718.

Please return completed forms to:

Energy Information Administration - (EI-53)

U. S. Department of Energy Attn: RW-859 Mail Stop BG-094 Washington, D.C.

20585

PAGE:

Reactor Name: HOPE CREEK 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

[

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, TB1, N20

[HAHCOCKS BRIDGE, NJ (08038 (609-339-3327 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 1ot required).

Name:

Title:

Mailing Address:

[E. S. ROSENFELD

[MANAGER - NUCLEAR FUEL

[P.O. BOX 236

[NUCLEAR DEPT, TBl, N20

[HANCOCKS BRIDGE, NJ

~

SIGNATURE:5d Date: :z..h/<<<:f' l

l l

l l

l 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 Hu1ber for this report: [ 01 ]

1.5 Reactor Operating License Expiration Date:

[ 202604 ] (CCYYMM) 1.6 Projected Reactor Redre1ent 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, absent spent fuel pickup by DOE, because of a lack of storage space for discharged fuel?

(201309] (CCYYMM)

PAGE:

3 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 sectio~.

2.1 Storage Site Description (a) Storage Site ID [ 4201 (b) Contributing Reactors

[4201 (b) Optional: Inventory from Contributing Reactors [

0 0

0 0

PifR BifR HTGR 2.2 (a) Licensed Site Capacity :

[1108]

(b) Maximum Established Site Cap ad ty

[3976]

(c) Current Inventory (excluding (d))

OJ (d) Number of Canisters (excluding (c))

O]

Reactor Name: HOPE CREEK 0

(e)

NOTE: COMMENTS ARE PRINTED IN THE COMMENTS SECTION

PAGE:

2.4 2.5 NUCLEAR FUEL DATA FORK Reactor Name: HOPE CREEK Storage Site Data (continued!

Does your company have plans to increase its storage capacity at this site?

(a I ( l No plans to increase lb)

( l Rod Consolidation (cl

( l Dry Cask storage

( d.l

( ) Reracking (el ( l Transshipment (fl Other (Please explain:Install additional racks.

(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 J

(b)

What is the limiting factor? [SEE COMMENT 2.4.b (a)

Have you conducted studies to determine if the maximum weight cask that 1ay be processed can be increased?

[NJ

{h) If Yes to 2.5(a), is it feasible to increase the 1axiu1um weight cask that may be processed? [ ]

(c) If Yes to 2.5(b), what was the esti1ated maxiu1um cask weight?

[

O J tons I

~

PAGE:

Section 3.0 Irradiated Fuel Tracking Co1plete Section 3.1 for each :grouping of assemblies for which no ubsequent irradiation is planned or which were permanently discharged uring 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 subnissions but which were reinserted for irradi-ation during this reporting period.

Complete Section 3.4 for any irradiated asseablies which have been shipped fro1 or to your site or which have changed ownership during the

- last reporting period.

PAGE:

7 NUCLEAR FUEL DATA FORK Reactor Name: HOPE CREEK 3.2 Listing of Temporarily Discharged Fuel OTE: 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.

!al Cycle No.:

[01 J (bl Cycle End Date:

[198802 ]

(c)

Number of Assemblies: [ 0 (dl List the unique fuel assembly identifiers for the assemblies meeting this description:

NO ASSEMBLIES DECLARED AS TEMPORARILY DISCHARGED DURING THIS REPORTING PERIOD.

PAGE:

Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 3.3 Changes in Permanently Discharged Status

st any assemblies which were reported as permanently discharged (on he 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 actualiy-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 *

.I

PAGE:

9 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORK 3.4 Shipment and Change of Ownership of Irradiated Fuel r any assemblies which during the last reporting period were shipped another.storage site or which changed ownership, attach photocopies of the DOE Form 741 (including the unique asse1bly identifiers, consis-tent with prior Form RW-859 submittals) completed for the transfer.

NOTE:

These assemblies must have been reported as permanently di'scharged.

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 *

~*

PAGg:

10 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.0 Cycle Projections 4.1 a)

(b)

(cl (d)

(e)

CLE CYCLE NUMBER OF NUMBER OF CYCLE BURNUP NUMBER SHUTDOWN URIRRADIATED REINSERTED (EFFECTIVE FULL DATE ASSEMBLIES ASSEMBLIES POWER DAYS)

(CCYYMM)

INSERTED IN CYCLE N+l 01 (H Actual) 198802 764 387 02 (N + 1) 198911 232 0

461 03 (N + 2 I 199109 292 533 OA (Ii + 3) 199309 288 508

, 05 (N + 4 I 199509 288 532 06 (N + 5) 199709 288 532 NOTE:

Cycle "N" is the cycle whose shutdown prompted submission of this for 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 insert~d in this cycle (cycle N+l).

PAGE:

11 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.2 Assembly identifiers for unirradiated assemblies inserted into cycle N+l

.~2 List the unique asse1bly-identifiers for the assemblies counted in question 4.1, column (c) for the current cycle (N+l).

NO ASSEMBLIES WERE INSERTED DURING CYCLE N+l


,------~------------~-

PAGE:

Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 4.3 Asseably identifiers for irradiated assemblies reinserted into cycle N+l 3 List the unique assembly identifiers for the assemblies counted in question 4.1, column (dl.

NO ASSEMBLIES WERE REINSERTED DURING CYCLE N+l

PAGE':

13 NUCLEAR FUEL DATA FORM Reactor Name: HOPE CREEK 5.0 Projections of Permanently Discharged Fuel ese projections of per1anently discharged fuel shall be reported on a up basis, where a group is defined in Section 3.0. This information eflects the current plans of your company.

NOTE:

Nominal 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 in the Group Enrichment Discharge Burnup (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE: [ 02 l ( N + 1 )

01C02 152 1.633 17 OlDOl 140 2.477 24

PAG~:

14 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projections of Permanently Discharged Fuel

  • ese projections of permanently discharged fuel shall be reported on a oup basis, where a group is defined in Sedtion 3.0. This information eflects the current plans of your company.

NOTE:

Nominal Initial Enrichment in weight percent is to.be reported to the

. nearest. tenth. Average discharge burnup is to be in GWD/MTU.

Group Hue Number of Nominal Initial

-Average Assemblies Enrichment Discharge Burnup in the Group (Optional}

(Discharged}

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 03 l ( N + 2 )

01D02 168 2.477 28 OlEOl 12 2.775 30 02A01 48 2.990 29 l

PAGE:

15 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM

5. 0 Project_ions of Permanently Discharged F1uel se projections of permanently discharged fuel shall be reported on a up basis, 1here a group is defined in Section 3.0. This information reflects the current plans of your company.

NOTE:

Nominal Initial Enrich1ent in 1eight 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 Assellblies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent!

(GWD/M'l'U)

CYCLE: [ 04 l ( Ii + 3 I 02A02 80 2.990 33 02801 104 3.002 34 03A01 36 3.220 31 03801 68 3.220 31 JI

PAGE:

16 NUCLEAR FUEL DATA FORM Reactor Name: HOPE CREEK 5.0 Projections of Peraanently Discharged Fuel

~ ese projections of permane~tly_dis~harged fuel shall be reported on a oup basis, where a group is defined in Section 3.0. This information eflects the current plans of your company.

NOTE:

Nominal Initial Enrich1ent in weight percent is to be reported to the nearest tenth. -Average discharge burnup is to be in GWD/MTU.

Group tiaae Number of Nominal Initial Average Assemblies Enrichment Discharge Burnup in the Group (Optional)

(Discharged)

(Weight Percent)

(GWD/MTU)

CYCLE:

[ 05 l ( N + 4 )

03!02 152 3.220 36 03802 36 3.220 34 04!01 100 3.220 30

PAGE:

17 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM 5.0 Projec~ions of Permanently Discharged Fuel hese projections of permanently discharged fuel shall be reported on a roup basis, where a group is defined in Section 3.0.. This information reflects the current plans of your*co1pany.

NOTE:

Nominal 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 in the Group Enrichment Discharge Burnup (Optional)

(Discharged)

(Weight Percent)

(GWD/MTUI CYCLE:

[ 06 l ( N + 5 )

04801 72 3.220 38 04A02 68 3.220 35 04!03 48 3.220 33 05A01 100 3.220 30

PAGE:

18 Reactor Name: HOPE CREEK NUCLEAR FUEL DATA FORM

6.0 Fuel Consolidation Data 6.1 If your company consolidated fuel *asse1blies from this reactor since the last report, list the unique assembly identifiers of the assemblies that were consolidated.

NO ASSEMBLIES VERE CONSOLIDATED DURING THIS REPORTING PERIOD.

6.2 How nany canisters of fuel bearing components were produced from the above consolidation [ 0 J canisters.

)

PAGE:

19 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 we~e 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.

, PAG'E:

20 NUCLEAR FUEL DATA FORM 8.0 COMMENTS orm

Reference:

[2.3(f) I -

Currently 1078 storage spaces are available to store SNF.

Company plans to install additional racks to increase storage space.

For1

Reference:

[2.4(a)]

Software BUG:

Number entered for 2.4(a) is not labeled

_ *tons* in the pr in tout.

Fora R~ference: [2.4(b)]

Crane capability. -Note that the 150 tons is the maximu1 cask *weight plus its contents that can be handled at this reactor.

ra

Reference:

(3.1 Software BUG: Nothing is printed for Section 3.1. Should print that no permanently discharged fuel changes since last report.

Fora

Reference:

(3.1&2 ]

Actual data for Sections 3.1 and 3.2 is not provided because no fuel movement occurred during 1987. Hope Creek's first refueling outage is scheduled.to.begin-in February 1988.

Fora

Reference:

(3.3 l There is no data for Section 3~3 because Annex B was not sub1itted for Hope Creek fuel.

Reactor Name: HOPE CREEK

PAGE:

21 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Form

Reference:

[3. 4 There is no data for Section 3.4 becuase fuel assemblies have not been shipped from Hope Creek site to any other storage site or changed ownership.

Form

Reference:

(4.l(bl]

Software BUG: The sofware requests CCYYMMDD.for the shutdown date although the printout is labeled CCYYMM.

The value given for the current.cycle is used for printout of item 3.l(dl when 3.l(c) is the current cycle.

For1

Reference:

( 4. 2&3 J Data is not provided for these sections as Cycle 1 is currently in progress. Cycle 1 to 2 refueling outage is scheduled to begin Feb. 13, 1988.

rm

Reference:

(5.0-1 J Software BUG: Only integer quantities can be entered for Section 5.0 average discharge burnup, GiD/MTU.

Form

Reference:

[5.0-2 ]

Software BUG: Records in file "GROUP.DBF" with group field blank were aarked for deletion an.d then the DBASE "PACK' command was given. This aad.e;~Mn~s:.rith *o*cassellblies in

. a blank group disappear froi4the~ifrJiitout~ *

,~

For1

Reference:

( 6. o:

This section is blank because fuel assemblies have not been consolidated at Hope Creek.

t Reactor Name: HOPE CREEK

PAGE:

22 NUCLEAR FUEL DATA FORM 8.0 COMMENTS Fon

Reference:

[7.0 This section is blank because fuel assembly defects are unknown at this time as Cycle 1 is currently in progress.

Form

Reference:

[8.0 Software BUG:

Some comment portions of question responses become lost. Users will find it best just to add these comments directly to Section 8 *

  • :_(.::( :... ~*.- -...:*.*

Reactor Name: HOPE CREEK