ML19211C186

Notifies That DOE Certificate of Compliance 6386 Has Been Revised to Include Unirradiated D2W Fuel Cells as Authorized Contents of Model 235R001.Forwards Revised Certificate

ML19211C186
Person / Time
Site:	07106386
Issue date:	12/13/1979
From:	Oosterman C ENERGY, DEPT. OF
To:	NAVY, DEPT. OF
References
15002, NUDOCS 8001110040
Download: ML19211C186 (9)

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Manager, Pittsburgh Naval Reactors Office Manager, Schenectady Naval Reactors Office MODEL 235R001 NEW FUEL SHIPPING CONTAINER - REVISION TO THE CERTIFICATE OF COMPLIANCE TO INCLUDE D2W FUEL CELLS AS AUTHORIZED CONTENTS; FORWARDING OF Department of Energy Certificate of Compliance USA /6386/BF has been revised to include unirradiated D2W fuel cells as authorized contents of the Model 235R001 new fuel shipping container. Specifically, Naval Reactors memorandum G#6373 dated September 4, 1979 requested Nuclear Regulatory Commission concurrence that two side or central D2W fuel cells with control rods or two corner 02W fuel cells, unrodded, be included as authorized contents of the Model 235R001 new fuel shipping container. The Naval Reactors memorandum stated that the shipment of two D2W fuel cells per container, with four containers per transport vehicle will have a safety margin as great as previously authorized fuel cells for the Model 235R001 container and complies with Code of Federal Regulations (10CFR71) shipping requirements.

Nuclear Regulatory Commission memorandum FCTC:JEJ 71-6386 dated December 3,1979 (Enclosure 1) concurred that the shipment of D2W fuel cells in the Model 235R001 container, with two cells per container and up to four containers per transport vehicle complies with 10CFR71 requirements. Accordingly, Naval Reactors has issued Revision 6 to Certificate of Compliance USA /6386/BF which is forwarded for use as Enclosure (2).

yi; The action taken by this memorandum is considered by the Government to be within the contractual scope of the applicable prime contract t

and does not authorize any delay in delivery or additional cost to the Government, either direct or indirect.

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Division of Naval Reactors L._

Enclosures:

(1) U. S. Nuclear Regulatory Ccamission Memorandum FCTC:JEJ 71-6386 dated December 3, 1979 (2) Certificate of Compliance USA /6386/BF (DOE-NR)

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General Manager, Bettis (w/o enclosures)

General Manager, KAPL (w/o enclosures)

Manager, Shipping Container Analysis, Bettis Manager, Fuel Shipping Containers, KAPL

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A Dr. W. E. Mott, Director, Division of Environmental 4

Control Technology, DOE (3) (w/ enclosure (2)

R$'O D. A. Nussbaumer, Fuel Cycle and Material Safety,

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1. 1' Manager, Special Nuclearliateffits. KAPL IE C. Oddis, PNR

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_ __ _. 7 U.S. DEPARTMENr OF ENERGY m

u n dit CERTIFICATE OF COMPLIANCE EHCLOSU3E{ 2 )to For Radioactive Materials Pacu;es 43.

la. Cert.ficate fLmber 1b. Revision No.

Ic. Pacnage ice-tification No.

Id. Page No.

' le. Total No. Pages.

USA /6336/BF(DOE-NR) 6 USA /6386/3F(DOE-NRJ L _,

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Inis certificate is issued to satisfy Sections 173.393.s.173.394.173.395. and 173.39G of the Department of Tr.in. portal on Hararcous '

b r.l. ti;riais Regulations (49 CFR 170-1831.

u 218 Ih.: p.schaging and contents described en item 5 below, meets the saf ety starid4'ds set to<in.n Subpari C r f Tit.e 10. Cute of Fedeial H 'ijutJtions. Part 71, Packaging of Radioacteve Material f or Transpori and Transpoe tasion of fladioact.w.'.! ate..a. User Certain

,t C Ja ed. E ions.

2c in. certificate does not relieve the consignor from comphance mth any requ.rement of the regulations of the U S. DeperErrent of TJosportation or other opphcable regulatory agencies including the government of ar'y countey through or.r:f o *sisc"I trie umCkage

.viet be t'ansported.

J. This cergif.cate is issued on the basis of a safety analysis report of the package design or appucations-O n Prepm ed by (Name and address).-

(2) Title and identif. cat on of report or appbcation-M) Datt.

.;attis Atomic Power Laboratory Safety Analysis Report for

_liating pg. 6 i'. 0.

Box 79, W. Mifflin, Pa.

15122 Packaging for the Model 235R001

gr., Refueling Engineering & Operations Module Shipping and Storage Container I

nolls Atomic Power Laboratory (See listing pg. 6)

$. 0. Box 1072, Schenectady, NY 1230L

'ttentign: Ffgr.. CCN Reactor Servicin7 3 CO'.DirioNS Tn. cest.hcate is conditional upon the fulfuhng of the requirements of subpart O of 10 CFR 71, as apphcable, ano the cand.tions specif.ed in.ien 5 below.

5. Descr.pt.on of Packaging and Authorned Contents. Model Number, Fissue Class. O!Pe Corriitions, and Ref erences:

a.

Description of Packaging - Title - Model 235R001 Model Shlooine and Stora7c Container the Model 235h001 shipping Container was originally designed to protect nonirradiated fuel modules of the AlC/A4W type.

Subsequently, the container was adapted to ship (L) AlW-3 fuel modules using a strongback, (2) partial AlW-R3 fuel ec11s using Module Support Assemblies, (3) S8G fuel cells (either standard size or partial) by use of a special frame assembly, cradle clamps, (4) S3C-3 refueling cells using celt cuprort assemblies, (5) D1C Core 2 Cell Assemblies and RFA s using special frame assemblies.

(6) A4W/AIG fuel clusters using a codified A4W/ALG fuel cell shipping f rame, (7)

ASMPP Spare Modules using a Module Support Assembly or (8) D2U side, central or corner fuel cells. The container structure is horizontal, having an oblong cross section and is fabricated from carbon steel sheet type (AISI 1010, 0.104 inch th4..:k).

The container is 313 inches long and weights approximately 4,500 pounds, er.pty.

Che cross section is essentially 17 inches radius separated by 1.5 inches giving

.mproximate inside dimensions of 35.5 inches high by 33 inches wide.

d j[}g (1) AlW Fuel Cell in Model 235R001 Gr 3 Container e The upper cover is removed to load and unload the AlW-3 strongback/codule g assembly. The strongback/ module assembly is suspended within the lower d section of the container structure from 14 elas:ic shear mounts. The maximum C e _o n of u uaoce-13 Decenter 1979 , 6b E spes.,ran Date None t FOR THE U s. DEPARTMENT OF E*MGY la Adar.u tof DOE tuurne O*t.cel 7b. s.gnatum. Nanie..ond Totte (of DOE ku.ro., n. Offocuan Division of Naval Reactors U.S. Department of Energy [ Washington, D.C. 20545 [J. W. Vaug an, Deputy Director BO A rm o rm r o n a r r1 -._,/ Division of Naval Reactors 1 m

i . ~.... 3 EEC.'E( 2 )10 G# 6529 Cert iL tcate of Con.pilanco. No. IfSA/f 386/UF (N!:-t!R) (4) SSG Standard and Partial Fuel Cells in Model 235n001 Gr 5 and cr 6 Containce-m The upper cover is removed to load and unload the standard or partial size p SSC fuct cells into the container inner frame assembly. The frame assembly is suspended within the lower section of the container structure from 14 clastic shear mounts. The fuct cells are restrained in the container by y means of cradle and clamp assemblics bolted to the frame assembly. Fore and aft restraint is provided by securing the control rod holddown device L to the forward stops bolted to the frame assembly. A fuct cell may contain ( either a regular control rod or a poison rod and be fitted with either a L. regular support adapter or a substitute support adapter. The shipping container, loaded with two standard size fuct cells weighs 11,100 pounds. (5) S3G-3 Refueline Cells in Model 235R001 Cr 7 Container The upper cover is removed to load and unload the S3C-3 refueling cells into the container Cell Support Assemblics which are suspended within the lower section of the container structure by 16 elastic shear mounts. The fuct cells are restrained laterally in the container by clamp and cradle assemblic bolted to the side rails of the Cell Support Assembly. Fore and aft restraint is provided by the axial clamp and cradle assembly. The shipping container when loaded with two refueling cells as shown on Westinghouse Drawing 1175J45 has a maximum weight of 10,191 pounds. (6) D1C Core 2 New Fuel Cells and RFAs in Model 235R001 Cr 8 and Gr 9 Containers The upper cover is removed to load and unload the DIG Core 2 fuel cells or RFAs into or out of the container frame assembly. The frame assembly is suspended within the lower section of the container structure from 12 elastic shear mounts for the fuel cells and six clastic shear mounts for the RFAs. The fuel cells are restrained in the frame assembly by means of cradle, adapter and clamp assemblies which also provide fore and aft restraint. Crush tubes at each end of each fuct cell provide for travel limit in the event of an accident. Four RFAs in their container are secured in a shipping fra=c by means of five cla.rps for each RFA. The loaded DIG Core 2 fuel cell container weighs r.o more than 9,616 pounds 7 and loaded RFA container weighs no more than 7,377 pounds. m (7) A4W/ALG New Fuel Cluster in Model 235R001 Cr 10 Containers y b The upper cover is removed to load and unload two A4W/AIC fuel clusters or one fuel cluster and one counterweight into or out of the container '3 frame assembly. The frame assembly is suspended within the container "I base assc=bly by sixteen (16) clastic shear mounts. The fuel clusters or counterweight are restrained vertically and transversely by ten (10) clamp and cradle assemblics and each is restrained longitudinally by a forward stop assembly. A fuel cluster may contain either a normal control rod or a special shipping and storage poison rod. The maximum loaded container weight is 12,421 p.unds. 1738 211 QpAg g Ny e n n ~..,.

... ~ - - - - ~ - - -. - - ~ ~ - - - ~ !.~' ENCLOSURE ( 2 )to ' G# 6529 ss. Certificate of Compliance No. USA /6386/BF (DOE-NR) (8) ASNPP Spare Modules in Model 235R001 Gr 11 Container The upper cover is removed to load and unload the ASNPP spare .' ~- modules into the container module support assembly which is suspended within the lower sectica of the container structure L by 18 elastic shear counts. The module is restrained laterally 1 in the container by clamp assemblies bolted to the side rails of the Module Support Assembly. Fore and aft restraint is / provided by the axial clamp assembly. The shipping container ') when loaded with one ASNPP spare module as shown on Westinghouse Drawing 1203J86 has a maximu= weight of 9,912 pounds. (9) D2W Side, Central or Corner Cells in Model 235R001 Gr 12 & Gr 13 Containers The upper cover is removed to load and unload the D2W fuel cells into or out of the container frame assembly. The fra=e assembly is suspended within the lower section'of the container structure from 22 elastic shear mounts. The fuel cells are restrained in the frame assembly by supports (four of which are integral parts of the frame assembly and two are bolted in place) and caps. Axial restraint is provided by a mid stop which is an integral part of the frame assembly, and by end stops which are bolted in place after the fuel cells are installed. The centainer loaded with side or central cells weighs no more than 11,400 pounds and the container with corner cells weighs no more than 7,700 pounds. b. Authorized Contents The authorized contents for each container are as follows: (1) Model 235R001 Cr 3 Centainer - One AlW-3 module without upper mechanism and with control rod, leadscrew, and control red holddown device (Westinghouse Drawing 951F060) installed on redded type =odules. r (2) Model 235R001 Cr 1 Container - One AlG or A4W reactor cell without upper mechanism and with control red, leadscrew and shipping fixture (General Electric Drawing 105D1550) installed on rodded type modules. (3) Model 235R001 Gr 2 Container - One A4W Reactor Test Assembly (RTA) i (4) Model 235R001 Gr 4 Container - Two AlW-R3 Partial Lower Modules [{ (control rods may be installed in the rodded fuel modules but are not necessary for criticality control during transport). tw 1738 212 ,0

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-- - ~ ~. -. [ EllCLOSl!EE(2)to G# 6529 . Certificate of Compliance No. USA /6386/BF (DOE-NR) (5) Model 235R001 Gr 5 Container - One or two standard size S8G clusters, each with regular or substitute support adapter and with control rod or shipping poison red and with control rod holddown device installed per Cencrcl Electric Drawing 299E179 (Note: If only onc cell is shipped per container, a dummy load /GE Dwg. 296E130/is installed for balance). F (6) Fbdel 235R001 Gr 6 Container - One or two partial size S8G clusters, each with regular or substitute support adapter 5 ((. and with control rod or shipping poison red and with control rod holddown device installed per General Electric Drawing 299E179. (Note: If only one cell is shipped per container, a duemy load /GE Dwg. 296E130/is installed for balance). (7) Model 235R001 Gr 7 Container - One or two S3G-3 refueling cells but a maximum of one 0-1 Reactor Cell Assembly per Container. (8) tbdel 235R001 Gr 8 Container - One or two DIG Core 2 new fuel cells each with a control rod shipping plug (GE Dwg. 258E679) installed. (9) lbdel 235R001 Gr 9 Container - Up t four D1G Core 2 RFAs. (10) Model 235R001 Gr 10 Container - One or two A4W/AlC new fuel clusters each with either a normal centrol red or a special shipping end stcrage poison rod installed. (Note: If only one cluster is shipped per container, a counterweight (Westinghouse Drawing 928E039) is installed for talance). (11) Model 235R001 Gr 11 Container - One f ull sized or corner ASNPP module per container. Rodded modules shall hcve the rod holddown per Westinghouse Drawing 123CD58 installed. Fixed rod modules shall have the fixed rod installed and bolted to the manifold. (12) Model 235R001 Gr 12 Container - One or two D2W new fuel cells (either side and/or central) each with a centrol rod and control rod holddown device (Westinghouse Dwg.123F.D01) installed. r t (13) Model 235R001 Gr 13 Container - One or tuo D2R new corner fuel [ cells. j b r.. D *

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p g I ENCLOSURE ( 2 )to x G# 6529 Certificate of Compliance No. USA /6386/BF (DOE-NR) c. Restrictions (1) Shipments will be made in accordance with Fissile Class III I

t requirements, u

(2) Shipments shall consist of materials as listed in 5.b(1) with no more than 18 loaded containers per vehicle or hold; or ] 4 (3) Shipments shall consist of materials listed in 5.b(2), (3), (4), (5) and (6), (7), (8) and (9), (10) or, (12) and (13) with no L_. more than four loaded containers per vehicle or hold. J (4) Shipments shall consist of materials listed in 5.b(11) with no more than four loaded containers per vehicle or hold including no more than one peripheral module per shipment. d.

References:

Technical. Manual - A4W/AlG Reactor Cell and RTA Shipping and Storage Container, NAVSHIPS 0989-030-6000. c. Additional Information Division of listcrials Liccusing memoranda dated Decembc$ 10, 1970 and June 30, 1971 stated that the contents and packa'ging of the Model 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for shipment of A1W-3 fuel modules or AIC, A4W or RTA reactor cells respectively. Directorate of Licensing memorandum dated May 1, 1973 stated that the contents and. packaging of the Model 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for A1W-3 partial lower modules. Naval Reactors memorandum C#5078 dated January 26, 1976 forwarded Bettis letters RAPD-OP(R)C-268 dated July 23,1973, WAPD-0P(R)C-477 dated Decc=ber 31, 1975, and WAPD-0P(L)C-431 dated January 19, 1976 to the Nuclear Regulatory Commission for information. Nuclear Regulatory Connission memorandum FCTh:CRt 71-6386 dated January 6, 1978 stated that the contents and packaging of the Model P 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for S8G s.tandard and partial fuel cells and for S3C-3 refuelinc [' cells. Nuclear Regulatory Commission. memorandum FCTR:JEJ 71-6386 p{ dated March 6, 1978 stated that the contents and packaging of the Model 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for Dlc Core 2 new fuel cells or RFAs. Nuc1 car Regulatory y Commission memorandum FCTR:JEJ 71-63S6 dated March 13, 1978 stated that

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the contents and packaging of the Model 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for A4W/ALG (_, new fuct clusters. Nuclear Regulator'/ Commission Memorandum FCTR: JEJ 71-6386 dated September 27, 1978 stated that the contents and packaging of the Model 235R001 ncv fuel shipping container complies with the requirements of 10CFR71 for SSG 0:cl clusters uith regular or substitute support adapters and with regular control rods or poison 1738 214 d'- 90$ ON h, e e4 -pp W=--*

h [ Certificate or comp nance ~* No. USA /6386/BF (DOE-NR) Nuclear Regulatory Commission memorandum 7CTR:JEJ 71-6386 dated May 1, 1979 stated that the contents and packaging for the Model 235R001 Cr 11 new fuel shipping and storage container complies with the requirements of 10 CFR 71 for AS::PP. Nuclear Regulatory Commission memorandum FCTC:JEJ 71-6386 dated December 3, 1979 stated that the contents and packaging of the Model 235R001 new fuel shipping container complies with the requirements of 10 CFR 71 for D2W side, central or corner cells. 3.a(2) and 3.a(3) I a Supporting data which indicates compliance with both the normal and L accident transportation conditions are contained in the following documents: AlG/A4W Reactor Cell or Fuel Cluster in Grous 1, 2, or 10 container KAPL letter A1G 25-159 dated October 2,1970 a. b. KAPL letter AlG 25-181 dated April 9, 1971 KAPL letter AlG 25-191 dated May 11, 1971 c. d. Naval Reactors memorandum NR:RR:DMissel GJ5923 dated February 22, 1978 AlW Fuel Cell in Group 3 or 4 Container o oD Q T oo o 1 ._b ,e w 6 Bettis letter WAPD-CP(R)RD-357 dated August 11, 1970 e. f. Bettis letter WAPD-CP(R)RD-444 dated October 9, 1970 g. Bettis letter b"APD-OP (R) RD-476 dated October 26,*1970 h. Bettis letter WAPD-OP(R) RD-488 dated October 30, 1970 1. Bettis letter WAPD-OP(R)C-94 dated May 16, 1972

j. Bettis letter WAPD-OP(R)C-199 dated Dece-ter 13, 1972 k.

Bettic letter WAPD-OP(R)C-229 dated March 6,1973 1. Bettis letter WAPD-CP(R)C-268 dated July 23, 1973 m. Bettis letter WAPD-OP(R)C-477 dated Dece-icr 31, 1975 Bettis letter WAPD-OP(R)C-481 dated January 19, 1976 n. S8G Standard and Partial Fuel Cells in Grcup 5 or 6 Container Naval Reactors memorandum NR:RR:U"dissel G#5776 dated September 8,1977 o. r p. Naval Reactors memorandum NR:RR:IJMiscel G46095 dated August 17, 1978 S3G-3 Refueling Cells in Group 7 Container i q. Naval Reactors memorandum NR:RR:UNissel G#5776 dated September 8, 1977 DIG Fuel Cells in Group 8 or 9 Container r. Naval Reactors memorandum NR:RR:UMissel G#5903 dated Jan2ary 23,1978 738 215 ASNPP Spare Module in Group 11 Container Naval Reactors memorandum NR:RR:LMWissel G:iG2C8 dated March 8,1979 s. D2U Side, Ccntral or Corner Fuel Cells in Groun 12 or 13 Container bd Naval Reactors memorandum NR;RR:L.".iissel % 373 d t: d Sc-r-ber 4,1979 t. ~ ' '}}