ML20031A551
| ML20031A551 | |
| Person / Time | |
|---|---|
| Issue date: | 07/08/1981 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Resnikoff M Sierra Club |
| Shared Package | |
| ML20031A553 | List: |
| References | |
| FOIA-81-215 NUDOCS 8109240024 | |
| Download: ML20031A551 (4) | |
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k NUCLEAR REGULATORY COMMISSION /[
o WASHINGTON, D. C. 20555
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O July 8,1981 4
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- Mr..Marvin Resnikoff.
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-Sierra Club Radioactive Waste Campaign 3164 Main Street IN RESPONSE REFER Buffalo, NY 14214 TO F0IA-81-215
Dear Mr. Resnikoff:
4 This is in ~ reply to your letter dated June 1,1981, in which you requested,
' pursuant to the Freedom of Information Act, a copy of the proposed shipping route between Chalk River, Ontario and Savannah River, South Carolina.
You indicated it was your understanding that these shipments will be routed through Sault St. Marie and enter northern Michigan.
You requested copies of all correspondence between Nuclear Assurance and the NRC regarding these proposed shipments.
Finally, you requested that if Nuclear Assurance'has inquired about barge shipments through the St.
Lawrence Seaway, you wished to have this information as well.
-In response to your request, the documents listed on Appendix A hereto are released to you in their. entirety and a copy of each document is enclosed. Appendix A documents one and two were previously released to the NRC Public Document Room located at 1717 H Street N.W., Washington, D.C.-as NRC accession numbers 8105130297 and 8103240616, respec tively.
-Pursuant to Exemption 4 of the Freedom of Information Act (5 U.S.C.
=-552(b)(4)) and 10 CFR 9.5(a)(4) of the Commission's regulations, we are withholding the Canadian portion of the route specified in document one of Appendix'B. This document contains information which was obtained in confidence from a foreign source.
Under these conditions the Canadian portion of the route contained in the document is protected from mandatory public disclosure under the alternative test set out in National Parks and Conservation Association v. Morton, 498 F.2d 765 (D.C. Clr.1974).
Under that test, a record can be withheld because disclosure would impair the Government's ability to obtain necessary information in the future.
It is our view that a breach of understanding between the NRC and a foreign ' source could in the future inhibit the free flow of
-information to the NRC and could interfere with our mission.
Document-two of Appendix B contains unclassified safeguards information.
The statutory authority for withholding this information is found in Section 147 of the Atomic Energy Act (42 U.S.C. 2167). This information is being withheld from public disclosure pursuant to exemption (3) of the Freedom of Infoi. nation Act (5 U.S.C. 552(b)(3)) and 10 CFR 9.5(a)(3) of the Commission's regulations.
Copies of the non-exempt portions of documents one and-two of Appendix B are enclosed.
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ARESNIKOS1-215. PDR m
- "~Mr. Marvin Resnik;ff',.
i We wish to inform you that the NRC's publication NUREG-0750, Public Information Circular for Shipment of Irradiated Reactor Fuel, which
~contains maps of the routes used for spent fuel shipments, is currently undergoing its first revision and it is scheduled to be published in August, 1981.
The NRC has received no documents from Nuclear Assurance Corporation in regard to barge shipments.
This completes action on your request.
Sincere.ly,
/'Divisio JC.Felton, Director n of Rules and Records Office of Administration
Enclosures:
As stated e
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Re: F01A-81-215 1.
(RESNIK0FF) 2 Appendix A 1.
3/27/81 Letter.to C. Stephens from J. R. Shea, " Federal Register Notice". (w/ enclosures') NRC Accession No. 8105130297 (3 pages) 2 3/10/81 Letter to Director, Export / Import and International Safeguards, NRC, from C. R. Johnson, Nuclear Assurance Corporation,
Subject:
Import License Application for Spent Ncclear Research Fuel
- Assemblies: G arnment (Canada) to Government (U.S.) Transaction.
ISNM 81005 (w/ enclosures) NRC Accession No. 8103240616 (22 pages)
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(RESNIX0FF) s.
. Appendix B NA;..u 9'
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5/15/81 Letter to G. W. McCorkle from F. L.' Danese, Nuc1 car Assurance Corporation (3 pages) 4 2.
6/24/81 Letter to F. L. Danese, from G. W. McCorkle w/ enclosures (26pages) e 1
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WASWNGTON,0. C. 70555
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4,..v MAR 2 71981 Mr. Chase Stephens Docketing and Service Station Office of the Secretary FEDERAL REGISTER NOTICE Enclosed for your transmission to the Office of the Federal Register for filing and publication are two signed copics of a Federal Regist;'r_ Notice as follows:
UNITED STATES NUCLEAR REGULATORY COMMISSION APPLICATIONS FOR LICENSES TO EXPORT / IMPORT NUCLEAR FACILITIES OR MATERIALS Also transmitted herewith are 12 additional confomed copies of the notice for your use. A highlights listing of this notice is not required (Exemption 71-1).
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Enclosures:
Notice and 14 copies (E
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APPLICATIONS FOR LICENSES TO EXPORT / IMPORT NUCLEAR FACILITIES OR MATERIALS Pursuant to 10 CFR 110.70(b) "Public Notice of Receipt of an application,"
please take notice that the Nuclear Regulatory Commission has received the following applications for export / import licenses.
A copy of each application is on file in the Nuclear Regulatory Commission's Public Document Room located at 1717 H Street, N.W., Washington, D.C.
A request for a hearing or a petition for leave to intervene may be filed within 30 days after publication of this notice in the FEDERAL REGISTER.
Any request for hearing or petition for leave to intervene shall be served by the requester or petitoner upon the applicant, the Executive Legal Director, U'.S. Nuclear Regulatory Commission, Washington, D.C. 20555, the Secretary, U.S. Nuclear Regulatory Commission and the Executive Secretary, Department of State, Washington, D.C. 20420.
In its review of applications for license to export production or utilization facilities,specialnuclearmaterialorsourcematerial,notic'edherein,the Comission does not evaluate the health, safety or environmental effects in the recipient nation of the facility or material to be exported.
OR lHE NUCLEAR REGUI qRY C05'J11SSION Syd
/ oseph D. Lafleur, Deputy Director Office of International Programs Dated this day MAR 2 7193I g 1 )iv D
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o At Bethesda, Maryland
?)Ob Attachment cf ) GD, '
i.:,,ppi..uis q-late of Application Ilaterial lii Kilngrantis Country lata R::calv:d Total Total
'f pplication ilumber Matcrial Typ3 Element Isotcpa End-Usa Destin~: Lion '
4 ransnuclear, Inc.
3.30% Enriched 14.031.000 456.008 Routine reload fuel for Sweden anium Ringhals 2.
f4 L5NM01795~
iltsubishi International 3.25% Enriched 37.655 1,224 Rnutine reload fuel for Japan 33/09/81 Uranium Ohi Unit 1.
33/1 7/81 C Iif.01798 W
Welcar Transport &
Natural Uranium Unlimited To DOE enrichment plants From Canada Storage, Inc.
Quantities for enrichment purposes.
32/27/81 33/05/81 15NM81004 hclear I.ssuranca Corp.
89% Enriched 32.009 17.440 For reprocessing of v ent From Canada 03/10/81 Uranium fuel assemblies at DOE 33/13/81 Savannah River Plant.
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h Nuclear Assurancb Corporation 1
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14041325-4200 Telex: 549567. 542703 715 Hm:m Dr.w Gr.nnd.lan:sen Cyor.w:> 8tS01 (3331245 0 20 1
TW1910929G334 Wehrpbaste 9
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S001 Zunch Sr.< erland (0I)470844 Telex $7275 March 10, 1981 CRJ/81/35/ETS
.rSWlh 8M5 Director b
Export / import and International Safeguards U.S. Nuclear Regulatory Commission Washington, D.C.
20055-
Subject:
Import License Application for Spent Nuclear Research Fuel Assemblies; Government (Canada) to Government (U.S.) Transaction Gentlemen:
The Nuclear Assurance Corporation, as transportation agent for the ' Canadian Government, hereby makes application for an import license under 13CFR 110.34, to import no more than eighteen'(18) kilograms (17,439.7 grams initial e. :-
mate) of U-235 as spent nuclear research reactor fuel for delivery to U.S.
DOE, Savannah River Project, to be processed under contract DE-AC09-76-SR01033, Mod. 3.
Similar shipments, of spent fural from Chalk River Nuclear Laboratories in Ontario, Canada, to SRP, Aiken, South Carolina. have been routinely made since 1966.
These shipments were made in NL Industries Legal Weight Truck Cask System #6502, which is now operated by Nuclear Assurance under lease agree-ment.
t Data in support of our request for an import license is attached as Appendix A to this i.etter If further information is required, please contact me.
.- jj Sincerely, C
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fG NUCLEAR ASSURANCE CORPORATION R-N
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. Johnson i-Vice Pr sident S
Engineering & Transportation Ser A
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1 APPENDIX A "
Application for Import License:
Shipments of Irradiated Research Reactor Fuel Assemblies from Chalk Diver to Savannah River Project
- 1, 10 C/R 110.34 (a)
Nuclear Assurance Corporation o
24 Executive Park West-Atlanta, Georgia 30329
~ ATTENTION:
C. R. Johnson (b)
From:
Chalk River Nuclear Laboratories Chalk River, Ontario, Canada (c)
For:
Chalk River Nuclear Laboratories Atomic Energy of Canada, Limited (AECL)
Chalk River, Ontario, Canada P0: JK0J1J0 (d) To:
Department of Energy Savannah River Plant Dunbarton, South Carolina (USA) l The spent fuel assemblies are to be repe ocessed at SRP.
(e) Starting date of proposed shipsesRs:
NAC proposes to start the' first shipment about May 15; 1981.
.( f) Completion date of proposed shipments:
NAC anticipates a total of six (6) shipments from Chalk River to SRP.- The final shipment is expected to be complete about seven (7) weeks.Af ter the first shipment.
(g) Description of Special Nuclear Material to be imported:
The materials to be imported are irradiated NRU-and NRX-type fuel assemblies used at the AECL Chalk River Research Laboratories.
~The chemical / physical fonn is solid U-Al fuel rods which 1.
originally contained uranium enriched to 93 weight percent U-235.
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APPENDIX A "
(Continued) 2.
These spent fuel assemblies contain no more than trace quantities of plutonium.
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'{h) Maximum Quantity of Special Nuclear ~ Material to be imported:
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Summary:
Original U-235 Post lrradiation U-235 Type rod Weight / rod (gm)
Weight-Total (gm)
.125 NRU 495 10,130.7 p.
28 NRX 550 7,309.0 Total U-235 17,439.7 grams l
Total U (U-238, U-236, & U-235) 32,008.4 grams Detailed information on each fuel assembly is attached as Exhibit A (NRX) and Exhibit B (NRU)..
(1) Mode of Transport:
The proposed six (6) shipments from AECL to SRP will be by legal weight truck in NL Indu,tries' Cask System !6502.
HRC -has issued Certificate of Compliance #9103, Revision 1, for the 1
NL 6502 Cask, which has an expiration date of May 31, 1983. Also attached in Exhibit C is IAEA and Canadia'n endorsement of the NRC Certificate of Compliance, and copies of correspondance recuesting renewals of these items.
J (j) - The enriched uranium was. acquired fran the USA, fuel was fabricated by AECL, utilized in a research reactor at Chalk River by the Canadians and is now being returned to the USA (SRP) fer fuels reprocessing.
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SHIPMEtiTS OF 1RRADI.ATED REACl0R FUEL ASSEMBLIES MATERIAL TO BE IMPORTED:
Spent nuclear fuel assemblies from Atomic Energy'of Canada, limited's Chalk River tiRU and tiRX Reactors.
FROM: Chalk River Nuclear Laboratories, Chalk ' liver, Ontario, Canada T0:
U.S. ERDA Savannah River Plant, Dunbarton, South Carolina, USA FOR:
The Spent Fuel to be shipped is owned by Atomic Energy of Canada, Limited (AECL), A Crown Corporation of Canada SY:
tiuclear Assurance Corporation 24 Executive Park West Atlante, Georgia 30329 USA Acting as transportation contract for Atomic Energy of Canada, Limited 1.
10,CFR 70.22 a (1)
A.
Applicant's fiame:
fluclear Assurance Corporation B.
State in Which Company is incorporated:
Delaware C.
Address of Principal Office:
24 Executive Park West Atlanta, Georgia 30329 USA D.
Principal Officers:
P. F. Schutt President J. R. Donnell Vice President M. H. Chaffin Treasurer C. B. Woodhall Vice President d Corporate Secretary E.
Address of All Principal Officers:
24 Executive Park West Atlanta, Georgia 30329 USA F.
Citizenship of All Principal Officers:
All citizens of USA G.
fio control or ownership is exercised by any alien, foreign corporation, or foreign government.
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II.
10 CFR 70.22 a (2)
A.
Activity for Which Import License is Requested:
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A total of six. shipments of irradiated NRX rods and NRU rods is planned utilizing one shielded transportation cask (known as 'the NL 6502 Cask System). The shipments'will originate from Chalk River Nuclea'r Laboratories (CRNL), Chalk River, Ontario, Canada ~and terminate at the U.S. ERDA Savannah River Plant, South Carolina, where the fuel rods will be reprocessed under U.S. ERDA contract with AECL No. DE-AC09-76-SR01033, Mod. 3, Batch 6.
B.
General Plan for Carrying Out the Activity:
The sh -lded cat.k provided by Nuclear Assurance Corporation '{NAC) under lease from NL Industries, Inc., will be loaded rerotely underwater in the CRNL loading pool.
The loadings will ca performed by qualified CRNL personnel.
The CRNL staff is familiar with the cask loading operation having had evoerience with several previous loadings of similar fuel elements into this cask since 1966.
An NAC representative will be present at the initial leading to provide technical assistance, consultation, and guidance and will be on call if assistance is required at subsequent loadings.
Tri-State Motor Transit Company is the carrier.
Drivers are 2
trained in accordance with 10 CFR73 and will be equipped with film badges and a radiation monitoring meter and will periodically measure and record te perature, and radiation levels of the load in transit.
The shipments will be made as fissile class III with exclusive use of the vehicle and Radioactive Yellow III labeling.
The route is preassigned, and cognizant authorities will be,
notified of the shipment in advance.
The shipper is Atomic Energy of Canada, Ltd.
The consignee is the U.S. ERDA Savannah River Plant, E. I. DuPont de Nemours, Inc.,
Dunbarton, South Carolina. The point of entry into the USA is either Sault Ste. Marie, Michigan, or Ogdensburg, New York.
Unloading of the cask will take place at the RB0F site (244-H) of the' Savannah River Plant.
III.
10 CRF 70.22 a (3) r.
1.
The Period of Time for Which' the License is Requested:
The shipments are scheduled to commence as soon as import authority is granted. A total of six successive shipments will follow approximately one week apart.
It is desirable to complete all six shipments prior to July 1, 1981.
This license application is requested for the period through July 30, 1981, or upon completion of the shipment of 32 kg.
SNM, whichever occurs first.
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IV.
10 CFR 70.22 a (4)
Description of Special Nuclear Material To Be Imported:
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A.
Name of SNM:
Irradiated NRU and HRX assemblies of fuel el,ements containing metallic Uranium enriched to approximately 93 wt.% in the isotope U235 prior to irradiation.
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.B.- Quantity of fuel assemblies to be Shipped:
28 - NRX Rods with initial U-235 weight of "approximately 550 grams l
per rod. Total post-irradiation U-235 content, 7,309 grams.
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125 - NRU Rods with initial U-235 weight of approximately 495 grams per rod. Total post-irradiation U-235 content, 10,130.7 grams.
C.
Chemical fonn of SNM:
U-Al with the Uranium enriched to 93 wt.% in the isotope U-235 prior to irradiation.
]
D.
Phys):al form of SNM:
Solid U-Al fuel rods.
E.
Isotopic content - post-irradiation:
This informat
' is tabulated by fuel type in i; pendix A.
)
1 This spent fuel contains no more than trace quanti'ies of l
plutonium, i
V.
10 CFR 70.22 a (6)
Technical Qualifications of Personnel to Engage in the Proposed '
1 Activities:
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The technical representative for the transportation contractor is the-j undersigned, who is Vice President, Engineering and Transport Services, i
for Fuclear Assurance Corporation. Qualifications include 25 years in i
the nuclear industry, two years in spent fuel transportation, plus a j
degree in Metallurgical Engineering.
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1 Since its first shipment in May,1966, from CRNL to the Savannah River -
')
Plant, it is estimated that the NL 6502 Cask System has made 90 trips j
and carried about 1,900 irradiated reactor fuel assemblies from the NRU 3
and NRX. reactors.
h Operators highly experienced in handling this cask will be working with j
it in loading, transport, and unloading.
I VI.
10 CFR 70.22 a (7)
I Description of Eauipment:
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The racioactive shipping container equipment to be used for all six shipments is NL Industries' Cask System No. 6502.
The cask is a
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circular cylinder with integral support structure and exterior
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H.
1 attachments approximately 156 inches Tong by 33-1/2 inches in diameter, excluding attachments.
It is constructed as a stainless steel, lead-filled weldment with stainless steel piping.
A portion of the,
cask body shielding is depleted Uranium.
As shipped, the cask r6sts horizontally on its integral supporting structure at each end, and the supporting structure is bolted to a separate structure attached to the vehicle. deck.
- l. metal screen enclosure surrounds the cask in transport to serve 'as a sunshade and a guard against tampering.
NRC has issued Certificate of Compliance No. 9103, Rev.1, for the NL 6502 Cask System.
This Certificate is dated September 30, 1977, and a copy is attached.
VII.
10 CFR 70.22 a'(8)
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Safety Procedures:
A set of Operating Instructions for the NL 6502 Cask System is provided to users of the cask system.
The operating instr;uctions are a section.
of the Safety Analysis Report, upon which the Certificate of Compliance is based.
The Safety Analysis Report contains a fuli analysis of equipment design and safety fee:ures especially in reference to shipping irradiated reactor fuel assemblics from the Chalk River site to the Savannah River Plant.
See Docket 71-9103 for details.
VIII.
Regarding Program for Control of and Accounting for Special Nuclear Material Possessed in a Quantity Exceeding One Effective Kilocram:
The proposed import shipments will proceed directly from origin at the CRNL facility of the shipper, AECL, to the consignee's Savannah River Plant faility of the U.S. ERDA without intervening stops.
The i
container will. be sealed by the consignor and opened only by the consignee. Thus, the program fcr control of and accotatability for the special nuclear material to be transported will be that of CRNL and the Savannah River Plant.
NAC provides a Record and Report Form for each such shipment. The Record and Report Form with shipper's section completed accompanies each shipment and, when the unloading site portion is completed, becomes the permanent reco.d for each shipment.
Information necessary to initiate an NRC Form 741 will accompany each shipment.
, Physical Protection Plan:
Exemption from physical protection of the material described in Section IV of this application is claimed referencing the regulation in 10 CFR 73.6 (b).
The dose rate of the contents of any one shipment will be greater than 100 R at a distance of 3 feet, without shielding.
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h C. R. Johnson Vice President, Engineer.ing I, Transportation Services Nuclear Assurance Corporation
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- 3. Docliet No.
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11002405
- i. u,,,e Nuclear Assurance Co: poration 4.ueense No.
24 Executive Park West IStN81005 M
w *m Atlanta, Georgia 30329 3,g,,;,,,,,,,,,,
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ATTN:
Charles R. Johnson April 1,1982
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E. Country where ship.
- 7. Quantity and type of rnaterial rne nt originates URANIUM:
33.0 kilograms uranium containing up to
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Canada 18.0 kilogram:: U-235 as spent NRX and NRU R
Reactor fuel.
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The licensee shall obtain all infomation from the foreign exporter necessary
'k to complete the shipper's portion of Fom NRC-741, " Nuclear Material Trans-actions Report."
If the licensee is the receiver of the material, he 'shall e
record both the shipper's and receiver's infonnation on the Fom NRC-741 and f'
transmit pursuant to Section 70.54 of 10 CFR Part 70.
If the licensee is not the receiver of the material, he shall provide the shipper's information to h
the receiver of the material for inclusion on the receiver's Form NRC-741.
3 2.
The licensee shall notify the appropriate regional Safeguards Branch, Office of Inspection and Enforcement, imediately, by telephone or telegram, if entry
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of any~ import shipment authorized by this license is refused by the U.S. Customs-Service.
l 3.
For import shipment of 350 grams or more of uranium-235 contained in uranium enriched in the uranium-235 isotope 20% or above, the licensee'shall promptly e
notify the appropriate Inspection and Enforcement Regional Office, by telephone, telegram or teluype, upon receiving r.otification that an import shipment has entered the country, gi.ing the date that the import entered and the estimated time or arriva1 t'.c
- tated destination.
4 This' license authorized import only and does not authorize the receipt, physicaf possession, or use of the nuclear material.
5 The material to be imported uno'er this license shall be protected in transit while within U.S. jurisdiction in ac.cordance with the requirements of 10 CFR 73 and the licensee's approved security plan, as appropriate.
Irradiated reactor j
(CONTINUED ON PAGE 2) i n,, tne u.s. riuc.t z. a a r.cu.r.: on y cc.:..::ssic:,
March 10, 1981
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James B. Devine. Assistant Director MAY 0 51981 t.n j a.
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-e s U.S. NUCLEAR RECetATORY CUMISSION SPECIAL NUCI. EAR F5TERIAL IMPORT LICENSE SUPPLEMENTARY SHEET
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5 fucl which has a total external radiation dose rate in excess of 100 rems par hour at a distance of three feet from any accessible surfece without intervening shielding shall be transported over routes apprtived in advance by the U.S. Nuclear Regulatory Comission.
The licensee shall notify the appropriate Inspection and Enforce: rent Office of the 6.
anticipated tir.a of arrival at the port of entry at least seven days prior to any taport shipr.ent authorized by this license.(ir. accordance with 10 CFR 73.72),
f0f. TdE U.S. HUCLEAR REGULATORY CG'.HISSION 02isinni sicnee w 3ccco ?.. ir '--
James B. Devine. Assistant Director Export / Import and Internatione.i. Safeguards Office of International Procrams (k:te of Application _ March 10, 1981 W.te of Issuance
- DE E Di_s tribution:
Licensee (original + 1 copy)
[E License file JNMSS(2)
License issued file GProco/0R00 PDR KVann/0R00 ACC
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Corp Attinu. Georgi 4 30329 24 Ezrcutrvo Parm West
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( % 3) 245-4320 TWX: 9109296334 Weinb'ergstrasse 9 B001 Zurich. Smtzenanc (01) 470644 Teles. 57275 March 4,1981 FLD/89/16/ETS Atomic Energy Control Boani Radioisotope and Transportation Section P. O. Box 1049 Ottawa, Canada K1P SS9 Attention:
Mrs. Gilmour
Subject:
Renewal of Canadian Endorsement (E53) for Type B Fissile Radioact'ive Material Package Design and Shipment Approval Certificate USA /9103/B( )F. Rev. 1.
Dear Mrs. Gilmour:
The.% clear Assurance Corporation respectfully requests the renewal of the Canadian t.naarsement of the r:odel NLI-6502 shipping package.
The current endorsement expires on April 18, 1981.
River, Canada to DOE's Savannah River Plant in Sout move is to occur in May of this year.
This planned It is requested that the subject. certificate be issued with an expiration dat'e of a May 31, 1983.
The certificate would then have the same expiration date as the Nuclear Regulatory Corrmission Certificate of Compliance No. 9103, Revision 1.
For your information and use, enclosed are copies of the ' current Canadian Endorsement,' the current IAEA Certificate (USA /9103/B( )F, Rev. 1), the cur-to the U.S. Department of Transportation requesting ren Certificate.
Please let me know if additional information is required.
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Yours truly, NUCLEAR ASSURANCE CORPORATION M p.s.., e.' a F. L. Danese FLD:1wb Enclosure es.
m-qpum:Efegy Lom'w.pon ce con' SG J
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P.O. Box 1046 C.P.1046 Or.awa. Canada Or.awa. Canada
. a, 30-10-2 K1P SS9 K1P SS9 Revisicn 1.
1 CANADIM EEXIiSDGE (ES3) FOR TYPE'B FISSILE RADIC%CTIVE M;TD1I4L PACKAGE DESIGN AND SHIPICE APPROVAL CERTIFICA*IE USA /9103/B( )F
'Ihis certifies that the package design for the Naticnal Lead Industries Inc. fedel NLI-6502 apprcr/ed by the USA Departncnt of Transport (US DOT) under IAEA Certificate of Carpetent Authority USA /9103/B( )F granted to Naticnal Lead Industries Irr., Barnell, South Carolina is hereby appn:wed for shipnent in Canada by road, rail and trarine transport subject to IAEA (1) and the Canadian regulations (2) (3) (4) (5) as appropriate, for the transport of radioactive material.
Each shipper under this authorization, other than the criginal -applicant, shall register his identity with the Atcmic Energy Co7 trol Board prior to the first use of this authorizaticn and shall certify that he possesses the necessary instructicns of the package for shipnent.
PACDGIIG DESCRIFTION As set out in the attached US D7T certificate USA /9103/B(U)F, the packrging ccnsists generally of a cylindrical steel shell ncminally O.84 m in dicneter and 3.25 m in length ccntaining leac and depleted uraniun shielding material and having 2 lids, one a each end, both O.61 m in diameter and c.': tending 0.13 m into the cask recess.
Fuel mds are ccntained within an apprcximately 0.29 m square by 3.21 m long basket cf stainless steel angle md strap with a full Jength stainless steel clad Boral poiscn plate with two partial poison plates irrorporated in the sides of the basket. - A-fretal -screen encloses the package durir.g transportation and the packcoe gross weight is about 19,200 kg. ' Ibis packaging shall bear the ccnpetent authority identificaticu mark " USA /9103/B( )F".
s I'JIHORIZED BADIOACTIVE CQTTDCS
'Ihe authorized contents censist of either 20 laU or 28 tax irradiated alur.inun-uraniun allcy fuel mds with a maxinun decay heat load of 14,000 BW/h (4100 W) as further limited in U.S. Nuclear Regulatory Ccnmissicn certificate of Ccnpliance No. 9103. 'Ihe average surface heat flux is approxi- -
trately 4CO W/m2, 1
S E PbE?TT Shipnent shall be nude as a Fissile Class III consignment in acccMame with the ccnditicns specified in UStaC approval certificate USA /9103/D( )F -
copy attac ed - and shall be further prepared for shipnent, shipped and carried in a cordan':e with the most recent Canadian regulaticns for road (2) rail (3) m:u Inc (4) and with IAEA regulaticns (1).
'Ih'is certificate authorizes shipTent by road, rail and marine transport.
'Ihis certificate is issued in accordance with the I/EA regalaticns (1) the Atomic Energy Ccntrol Regulaticns (2) and by agreenent with the Car.adian Transportaticn rec 311atory authorities.
~
,,, 'Ihis cortificate expires la April 1981.
A N
f, l-.C:rtificd bys
',,fM Endo'rsed by:
e-
~
1
(
\\
~
[i k.,
d ch J.
G. (fic 1 anus E. J '. F ase Chief - ) Safeguards - Nuclecr Materi'als Dire c r of Operation Licensing Division-Rail Transport Committe Directorate of Licensing Canadian Transport Commiss Atomic Energy Control Board Ottawa, CANADA P.
O. Box 1046 Ottawa, CANADA (Acting competent authority fo'r road transport)
).f 4
G.W.R. Graves - Chairman Board of, Steamship Inspection Ship Safety Branch Canadian Coast Guard Ottawa, CANADA REFERENCES (1)
IAEA " Regulations for the Safe Transport of Radioactive Materia 3 1973 Edition Safety Series No. 6, International Atomic Energy Agency, Vienna STI/ PUS /323.
(2)
Atonic Energy Control Regulations, SOR/74-334 dated 4 June'1974.
(3)
Regulations for the Transportation of Dangerous Commodities by Rail, as issued by the Canadian Transport Commission.
(4)
IMCO " International Dangerous Goods Code" published by the Inter Governmental Maritime Consultative Organization, London.
Refer also,to National Harbours Board and St. Lawrence Seaway Authorit regul'ations as appropriate.
(5)
IATA " Restricted Articles Regulations" Radioactive materials packaged.and shipped in accordance with Part 2 of these regulati are deemed to meet the requirements of Sec. 300 of the Air Regul tions for Ca;.ada.
See Flight Information Manual and Criteria fc the Carriage of Dangerous Goods bnd Magnetized Materials, Civil Aeronautics Branch, Transport Canada.
Aevision 1:
8 June 1978.
Expiry date changed.
W
\\ $
DEPARTMENT OF TRAN ORTATION
..7-
~"
f 1 RESCARCH ANp SPECIAL PROGRAMS ADMINISTRATION
.. a h
WAS HIN GTON. D.C. 30500
~
4%*.. o. /
' IAEA CERTIFICATE OF COMPETENT AUTHORITY
. _}...
Type B Fissile Tladicf)ctive Material Package Design f.
amn.
- ~ ~
Certificate Number USA /9103/BOF.
(Revision.1),
i.1 This establishes that the packaging design described herein, when loaded with the authorized radioactive contents, has I.'
l been certified by the Natic nal Competent Authority of the Unitt
- J-United States as meeting the. regulatory requirement for Type B
% i packaging for fissile radioactive materials as prescribed.in~
ml Regulations and in acco.-dance with as 173.393b and
.-i 173. 39 6 (c) (3 ) of the USA 2 Regulations for the transport of f
radioactive materials.
.I.
- --Package Identification --NLI--6 502. -----
i I
II.
Packaging Description - Packaging authorized by this
.'i certificate consist of a 1/2 inch thick steel shell 33 1/2 inct in diameter and'130 inches in lenoth containing lead and l}
depleted uranium shielding material and having 2 lids,.one ht.
- / }
each end, both 24 1/2 inches in diameter and extending 5 inches
/e into the cask recess.
Fuel rods are contained within an ei appro/imately 11 1/2 inch square by 128 1/2 inches long basket J.
of stainless steel angle and strap *ith a full length stainlese 3-incorporated in the sides of the basket. steel clad Boral poison A metal screen encloses the package during transportathlon e'nd the package
{.
gross weight is about.45,300 pounds.
III.
Authorized Radioactive Contents - The authorized content consist 'of either 20 NRU or 2'8 NRX irradiated aluminum-u
_ alloy, fuel rods.with_a maximum,, decay heat. load.of lJ.4.,000 'BT
.C _
W
- - further -limited -4.n 17. -E. -Nuclear / Regulatory-Commission.certifi--
il cate of Compliance No. 9103 '(Appendix A).
i
. Shipments.are authorized as Fissile Class III with a maximum of one package per shipment.
IV. ;
General Conditions -
~~
Each user of this certificate must have in his 4.
possession a copy of this certificate.
b.
Each user of this certificate, other_than NL 3
Industries, Inc., Barnwell S. C., shall register his identity in writing to tthe' Office of Hazardous
-l Materia'.s Regulations, II.
S. Department of 'frans
- i. t D.
S. Department of Transportation, Washington, portatio2.
D. C.
t 20590.
.e f.,
a,..
e.
py
-...-....m-
~
~
.....: :. - i.., -.;.-... r --.-
.n y
.,. $ p h) n, 1
Certificate Number USA /9103/B()F Page 2 This certificate does not relieve any consignor c.
,. or carrier from cc:npliance with any requirement of the Government of any country through or into which the package is to be transported.
V.
Marking and Labeling - The package must also boar.th marking USA /9103/B()r as well as the other marking and labe prescribed by the USA Regulations.
72, Exoiration Date - This certificate, unless renewed, expires on April 18, 1981.
This certificate is issued in accordance with the reg' ireme u
of the IAEA and USA Regulations and in response to the October 11, 1977 and May 5,1978 petitions by NL Industries Barnwell, S. C. and in consideration of the associated information provided in U.
S.
Nuclear Regulatory Commission Certificate of Compliance No. 9103 (Appendix A).
Certified by:
l l
y e
.M,
G_ //78 J
b.zL Grella' (DATE)
Chief, R & D Manage:nent Division Office of Program Support Materials Transportation Bureau 1
1
.LSaf ety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1967 Edition" published by the i
, ; International Ato:aic Energy Agency (IAEA), Vienna, Austria.
t
~2Title 49, Code of Federal Regulations, Parts 100-199, USA.
Revision 1 issued to incorporate Rev.1 of NRC Certificate 9 and to extend expiration dater l
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Telec 57275 March 4, 1981 FLD/81/15/ETS Department of Trartsportation Materials Transportation Bureau Office of Hazardous Materials Operations Washington, D. C.
20590
Subject:
Request for IAEA Certificate of Competent Authority Renewal for Model No. NLI-6502 Shipping Package.
Gentlemen:
The Nuclear Assurance Corporation respectfully requests that your office renew the IAEA Certificate of Competent Authority for the shipping package desig-
~
nated NLI-6502.
The current certificate expires on April 18, 1981.
with AECL, to transport spent NRU and NRX research fuel assemblies from River, Canada to DOE's Savannah River Plant in South Carolina.
This planned move is to occur in May of this year.
NAC is presently applying for a renewal of the AECB Endorsement Certificate.
The renewal of the Canadian Endorsement requires the renewal of the IAEA Certificate.
It is requested thas le subject certificate be issued with an expiration date of May 31,1983.
The Trtificate would then have the same expiration date as the Nuclear Regulatory mis'sion Certificate of Complia..ce No. 9103, Revision 1.
For your information and ust enclosed are copies of the current IAEA Certifi-cate (USA /9103/B( )F, Rev.1, ud the current NRC Certificate of Compliance (9103, Rev.1) which expires i / 31, 1981.
Should you have any questions, picase call.
Yours truly, NUCL' EAR' ASSURANCE CORPORATION
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F. L. Danese FLD:lwb Enclosure 1
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-P CERTIFICATE OF COMPLI E
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- 2. PREMABl.E 2.la) This cartificate is issued to satisfy Sections 173.2334.173.3s4.173.395, ard 173.396 of the De* artrrert of Trarncert2 Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10.1 and 146-154100 of o
Tranrportation Cancerous Carsoes Regutetions (46 CFR 146-149),
as amerdad.
2.tb)
The peckaging and corrisnts erscribed in item 5 below, ~ ets the safety itsadsrds set forth in sudoort C o Federst Regulations Part 71. fackaging of Radioactrw Materials for Transport ard Transoortation of Radio Canain Conditions."
2.fc)
This certificate does not relieve the consignor from compliase with arry es.tultemeett of the regula11orrs Trans:ortation or other apolicable reguratory agencias, induding the govvenmefit of any country through or will be transcorte:3.
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- 3. This c:rtificate *o issued on the basis of a safety analysis report of the 3: ck>ga design er applicattors 3.ts)
Preperus by plame and addrezz):
3.bl Title are ieentification cf recort or applicatiors:
HL Industries, Inc.
P. O. Box 2046 NL Industries, Inc. application dated September 7, 1977, as supplement,ed.
Wilmington, Delaware 19899 3.rci cocket No.
- 4. Cot 4ClitoNS This certificate is corditional upon the fulfiCng of the requirerrants of Subcart D of 10 CFR 71, as apof in he n 5 beIc.v.
- 5. Cascimion of Pacu;ing are Autnoriarc Contents. Mocal Nutr.ber, Fissile C! art. Other Corditions, are References (a)
Packaging (1) Model No.: NLI-6502 (2)
Description lead, and depleted uranium shielded shipping cask., Its.
A steel overall dimensions are 33.5 inches in diameter by 130 inches long.
The loaded cask weighs about 45,300 pounds.
The wall thicknes 09 the cavity and outer shell is 1/2 inch.
The all thichness of the inner shell is 1 inch.
The main body of the cask is divided inte two regions.
The inner region, which is a maximun of 5-3/4 inches thicke contains uranium shielding angles at the four corners the remainder of the shielding region is filled with chemical grade e
lead.
The outer (sacrificial) 3-inch thick region is filled with lower melting point 6'.' antimonial lead.
The cask contains six 5 -(6) fusible " weep holes" around the cask at each end This
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u Page 2 - Certificat(eg ta4 Tio. 9103 - Revision No.1 - Dock'et No. 71-9103
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5.
(a)
(2)
Description (Cont'd) sacrificial region also contains 10 layers of 0.018-in terne pla te.'
The main body of the cask is equipped with'two (2) lids, one on each end.
The two lids are similar in construction, eacDB being 24.5 inches in diameter and extending 5 inches into the cask recess.
The lids, like the main cask body, contain an oute, sacrifical region (2" thick containing ten 0.018-in terne discs with the remaining volume filled with 6% antimonial lead) and an
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inner region (4-5/8" thick) containing chemical grade lead.
The sacrificial region in each lid is fitted with exterior weep ho'les One lid contains a 1/2-inch drain line and valve. 'The other lid contains two 1/2-inch lines for a pressure relief valve with filter and the other line is capped.
u The fuel rods are contained within an approximate ll-1/2. inch sqs by 128-1/2-inch long openwork basket constructed cf stainless steel angle and strap.
The basket has a full-length lid along one side, for horizontal loading, and a lid on one end for vertig unloading.
A vertical, stainless steel-clad Boral poison plate' divides the basket into two, full-length halves, and two partial poison plates are incorporated into the siGcs of the basket.
A metal screen enclosure surrounds the package in transport to se) as a sun-shade and prevent inadvertent use of structural parts of the package, other than the tie-down devices for securing the package to the vehicle during tran port.
The cask rests hnrizontally on its integral supporting structure '
at each end, and the supporting structure is bolted to a separate o
structure attached to the deck of the special trailer provided for its use.
(3)
Drawings The Model No. NLI-6502 shipping package is constructed in accordag National Lead Company Drawings Numbers:
5797-P, Rev. 1 Details-Safety Shield 5'5798-0, Rev. 1 Cask Tie-Down 6502-01, Rev. 5 Basket Details 6502,03, Rev. 4 Latch and Basket Details 6502 '04, Rev. 3 Basket and Lid Assembly 6502-07, Rev. 5 Cask 6502-08, Rev. 4
~ Lid Assembly and Details 1
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Page 3 - Certificate No. 9103
. Revision'No.1 - Docket No. 71-9103 5.
(b)
Contents (1) Tyra and form of material Irradiated NRU-NRX aluminum-uranium alloy fuel rods e'nriched in U-235 istotope with the following specifications.
NRU NRX (MKD Number of elements per rod 12 7
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Maximum U-235 content per rod 495 550 prior to irradiation, g (1.8percm)
(2.0g Minimum average burnup, "
t.5 45 Minimum decay time, days 120 120 (2) Maximum quantity of mater.a1 per package The maximum decay heat load per package not to exceed 14,000 Btu /hr, and 20 NRU fuel rods or 23 NRX fuel rods per package.
(c)
Fissile Class III Maximum number of packages per shipment One(1) 6..
Poison inspection and loading of fuel rods shall be subject to the followir conditions:
(a)
Poison inspection and loading of fuel rods in accordance with Section VII-B.2.(B.)(3.) (pp.,.VII-10 thru VII-1,1) of the application, and (b)
The package shall not be loaded with a mass which exceeds 75" of crit,
, determined by extrapolation to zero reciprocal count rate.
7.
Dummy fuel rods consisting of empty aluminum pipes shall be installed in es fuel rod posi-ion not occupied with fuel.
8.
The cask cavity shall Ge dry (no free water) when delivered to a carrier fc transport.
The cask cont 6n:ts shall be so limited under normal conditions o' trans
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9.
that the dose rate will not exceed 10 mrem /hr at three (3) feet from the external surface of the cask.
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v Pag; 4 - Certificate flo. 9103 - Revision fio.1 - Docket tio. 71-9103 t
10.
Construction of additional packaging is not authorized.
11.
Expiration Date:' May 31, 1983.
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REFEREtiCES NL Industries, Inc. application dated September 7,1977.
Supplement dated:
May 1, 1978.
FOR THE U.S. NUCLEAR REGULATORY C0:411S5 e
f&
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety 3 I9r*
Date-S e
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