ML19242D028

Forwards Request for Approval of Route Between Columbia,Md & Savannah River Plant,Sc for Fourth Spent Fuel Shipment, Planned for 790730

ML19242D028
Person / Time
Site:	University of Missouri-Columbia
Issue date:	07/12/1979
From:	Alger D MISSOURI, UNIV. OF, COLUMBIA, MO
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 7908140377
Download: ML19242D028 (21)

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So- 136 l:'Q Research Reactor Facihty S<! #y[0d RECEWED UNIVERSITY OF MISSOURI nes ircn Pa,a M,,. I1 00 cc a-o a. %ssovi c5203

. -- y.,17 Y'm nw (3m 882a2n July 12,1979

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[ '4 Director Office of fluclear Material Safety and Safeguards U. S. fluclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

Enclosed is our request for route approval between Columbia, Missouri and Savannah River Plant, South Carolina. This request concerns our fourth spent fuel shipment this year which is planned after the 16 July deadline for implementation of fiUREG-0561. An expeditious response would be appreciated so that our target date of 30 July can be met.

If any questions arise, please call Dave McGinty, Reactor Physicist, at 314-882-4011.

Sincerely, N%b e,n Don Alger Associate virector DA:vs Enclosure N.. : 'i. .' O. 5" D /,PJ T, u .*f ~a 1 LL LnLI.N !.

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SHIPMErlTS OF IRRADIATED REACTOR FUELS UtlIVERSITY OF MISSOURI RESEARCll REACTOR Table of Contents A. Cargo Description RR-6, 7, 8

-- Quantity and type of fuel (number of elements).

-- Certificate of Compliance.

-- Loaded weight of trailer .

B. Anticipated Schedule

- - flumber of shipments.

-- Approximate duration of complete transfer.

-- Proposed beginning and ending dates.

C. Route

- Origin and destination (specific locations).

-- Proposed routing

-- Mileage information for each distinct segment.

-- Estimated elapsed time per shipment.

-- Location of planned stop-overs and food and fuel stops.

-- Alternate routes D. Route Overview

-- Route identifica tion.

-- !!ileage chart.

-- LEA identification, jurisdiction and response center.

-- LEA telephone numbers.

-- Monitored CB radio channels.

-- Ef fectiveness of radiotelephone along the route 6 '] Fj } ~, j 1

E. food and fuel Stop l.ocations F. Safe Havens for:

-- Temporary refuge.

-- Emergency assistance.

G. Trip 1.og

-- flames of carriers, drivers and escorts.

-- Dates and times of depar ture and arrival (planned and actual).

-- Dates, times and locations of stops and layovers.

-- Identification of designated central location.

-- Dates, times and locations of status calls to desir;nated location.

-- Deviations fro;a planned route.

-- Other abnor mai occurrences with regard to routes , equip:. ant, vehicles, personnel, weather, traf fic or threa ts.

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0 A. CARGO DESCRIPTI0tl

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SHIPPIf;G DATA A. Cargo Description - continued Gross weight of shipment

1. Cask weight empty 23.310 lbs.

2. Shipping base 6=000 lbs.

3. Fuel load 113 + 390 (basker) lbs.

4. Coolant .

136 lbs.

5. Parts, boxes and yokes N/A _ _ _ . _ lbs.

Gross weight 29.949 lbs.

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UlllVERSIlY OF MISSOURI RESEARCH REACTOR Ship. Date III. Information on Solid Preirradiated l'uclear Fuels ShiBled Design U 23s U23 U233 4 Total Ut.

Element Serial gms oms U,gs of Element

!! umber & Type MURR Plate 773.943 56.583 830.526 6295 i 10 775F55 140RR Plate 773.948 56.437 830.526 6295 i 10 775F62 14URR Plate 774.390 56.680 831.070 6295 i 10 775F66 14URR Plate 775.060 56.940 832.000 6295 1 10 775F75 775F76 14URR Plate 775.220 56.950 832.170 6295 i 10 i

775F78 14URR Plate 775.420 55.970 832.390 6295 i 10 fiURR Plate 775.410 55.620 832.390 6295 1 10 775F95 i4URR Plate _774.980 56.620 831.600 6295 i 10 775F97 Total flo.

Elements 8 TOTALS 453.8 6,62.672 50,360 l 6,198.371 Entered by y _f/NM Checked by .

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RR-7 UillVERSITY OF MISSOURI I:ESEARCll REACTOR Ill. Information on Solid Irradiated tiuclear Fuels Shipped U23o Pu'

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Element Scrial 1;P237 U 233 gms

!!unber gms gms gms gms glllg,s 5.42 588.862 56.583 0 674.823 29.378 775F55 _,

5.42 589.660 56.437 0 675.349 29.252 775F62 5.42 589.535 56.680 0 675.557 29.342 775F66

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5.42 590.596 56.940 0 676.816 29.280

. 775F75 5.42 590.756 56.950 0 676.986 29.280 775F76 5.42 596.525 56.970 0 681.891 28.396 j

775F78 5.42 588.250 56.620 0 674.500 29.710 l 775F95

! 5.42 587.30 56.620 0- 673.720 29.800 l_ 775F9/

lotal t!o.

Elements _ 8 i

j TOTALS 43.36 4,721.484 453.8 0 5,409.722 234.438

+0RIGN code output indicates less than 0.2 grams per element total plutonium (ORNL-4628).

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UNIVERSITY OF 111SSOURI RESEARCH REACTOR III. Information on Solid Irradiated fluclear fuels Shipped Cooling .,

.unt Seria' Date of Date of Period Decay Nu:nber Initial Final Irrad1- to Irradi- Irradi- ation Shipping fleat Date/4417; Burn-up Load ** Activity ation ation Period

• 7 (days) - days (ful-days { (watts) (curies) 4 19 Ilay 75 19 Dec 77 120 573 (570) 146.890 45.4 1.17x10 775F55 4

19 Dec 77 120 573 (5701 146.260 45.4 1.17x10 775F62 13 Oct 75 4

9 Aug 76 23 Jan 78 120 538 (510) 146.710 52.8 l'.34x10 775F66 4

6 Feb 78 120 524 (510) 146.400 52.8 1.34x10 775F75 27 Feb 77 4

6 Feb 78 120 524 (510 ) 146.400 52.8 1.34x10 775F76 27 Feb 77 13 Feb 78 120 51 7 (510) 141.980 52.8 1. 34 x10^'

775F78 17 Dec 76 0

10 Jan 78 12 Feb 79 120 153' (150) 148.540 301.' 7.30x10 775F95 4

12 Feb 79 120 153 (150) 148.950 301.2 7.30x10 775F97 21 Mar 78 tal !!o.

ents 3 5

TOTALS 1,172.13 904.4 2.23x10

• ' Numbers in parentheses are dr tic

• MURR fuel elements rotate in and out of core. used in determining ORIGN output dat Ibey are not irradiated to . total burnup in a continua un.

• • ileat load c 3 activity calculated based on operating history using the ORIGN code, ORNL-4628.

5 Estimated total activity, (curies of S & y) 2.23 x 10 3,086.7 BM/hr Estimated total decay heat load, (Btu /hr. )

Entered by /#5' [f k/ g.

Checked by A f; - . .

of /10 f k Date . _ 2 7 ,[i l'7'77 4 m sit .I 7 ,,

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Forrn NRC 613 U.S. NUCLE AR REGULATORY COMMISSION I' CERTIFICATE OF COMPLt ANCE

,g CFR 71 For Radioactive Materials Pickages 1.(a) Cet ii e Number 1 (b) Revi on No. 1.(c) Pa gr 1.(d) PaqsNo 1.(e) Totg No. Pages

2. PRE AMBLE 2.fa) This certificate is issued to satisfy Sections 173.333a.173.391,173.37. and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Departrnent of Transportation Dangerous Cargoes Regulations (46 CF R 146-149), as amendn!.

2.(b) The packaging and contents descritw! in itern 5 below, rneers the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations. Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions /

o 7.fc) This cerq%te doer oct rel+n the consigact frc.T. cc.npl.a.~.ce wU o.iy requirement of tne regulations on the dS.tepartrnant of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. This certificare is issued on the basis of a safety analysis report of the package design or application-Preparnt by (Name and address): 3.(b) Title and identification of report or app!ication:

3.(a)

General Electric Comapny General Electric Application dated December 23, 1968, as supplemented.

P.O. Box 460 Pleasanton, CA 94566 -

3 (c) Docket No.

4. CONDITIONS This certificate is conditional upon the fulfilling of the requiremants of Subpart D of 10 CFR 7f, as applicable, and the conditions specified in itern 5 below.

5. Description of Packaging and Authorital Contents, Model Number, fissde Clus Other Conditions, and

References:

(a) Packaging (1) tiodel No. : GE-700 (2) Description A steel encased lead shielded shipping cask enclosed by a double-walled protective jacket of the same shape with a rectangular base-plate. The cask is a double-walled steel circular cylinde% 37-inch-diameter ny 65-inch high with a central cavity .15-inch-diameter by "i-inch high. Approximately 10.25 inches of lead surrcund the

. antral cavity. The cask is equipped with a cavity drain line and lif ting device. Closure is accomplished by a gasketed and bolted steel lead filled plug. The maximum weight of the packaging is 23,000 pounds.

The cask may be modified with a 14-inch high cavity extension. The modified cask is 79 inches high and weighs 28,000. pounds.

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Page 2 - Certificate fio. 5942 - Revision !!o. 2 - Docket !!o. 71-5942

5. (a) Packaging (Continued)

(3) Drawings The packaging is constructed in accordanc.e with the following General Electric Company Drawings tios.:

237E325, Rev. 2 106D4150, Rev. 0 106D4331, Rev. 0 .

195F127, Rev. 0 -

289E646, Rev. 1 789E647,.Rev. 1 -

289E642, Rev. 2 (b). Contents (1) Type and form of material Byproduct, source, and special nuclear material contained in solid or metal oxide form.

(2) Maximum quantity of material per package (i) 740 gm U-235,- provided that the maximum U-235 enrichment does not exceed 6 weight percent; or (ii) 1,200 gm U-235, provided that the fuel material is in the form of MTR-type fuel elements with a minimum active fuel length of 23 inches; or (iii) 220 gm fissile material; or (iv) 1,650 gm U-235, provided that the maximum U-235 enrichment does not exceed 3.5 weight percent and the fuel material is in the form of C3 rods loadcd with 0.376= inch.diametzr pellets

• tith t minimum active fuel length of 37 inches; or (v) those values presented in Figure 1, UO4 Height Limits for Model 700 Shipping Container, of GE application dated February 25, 1970, applicable to fuel material in the form ~ of rods with a minimum pellet diameter of 0.40-in , or (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type feel elements (GETR Fuel) with each element containing no more than 510 gm U-235 and inserted in the spaced stainless s+ eel fuel shipping basket described in GE application dated Iebruary 25, 1970 and GE Drawing flo.105D4150, ".ev. O. }

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Page 3 - Certificate !;o. 5942 - Revision I;o. 2 - Docket ?!o. 71-5947.

5. (b) Cantents (Continued)

(2) flaximum quantity of material per package (Continued)

(vii) 6,200 gm U-235, provided the fuel is. in the form of fiURR TRTR type elements containing not more than 775 gm U-235 per element; loaded and spaced in the stainless steel fuel shipping basket as i described in MURR Drawing ?!o.1228, Sheets 1 tnru 5, Revision 0.

Fuel elements shall have at least 150 days cooling time since last reactor operation. ,

(3) fiaximum quantity of radioactive decay heat per package (i) 6,500 watts for dry shipments, or (ii) 1,500 watts for wet shipments, provided that the cavity shall contain at least a 1,000 cu in air void (at standard temperature and pressure) at the time of delivery to a carrier fer transport.

(c) Fissile Class III flaximum number of packages per shipment 2

6. The material specified in Paragraph 5.(b)(1) shall be clad, encpasulated, or contained in a metal encasement of such material and construction as to with-stand the combined effects of internal heat load and the 1475 fire with the closure pretested for leak tightness or in accordnace with the statements and representations contained in GE application dated February 4,1969. Shoring may be provided to minimize movement of contents during transport. l

7. The applicant shall confirm annually that the pressure relief valve is operable at 100 psig.

8. When needed, suf ficient antifreeze in the cask shall be used to prevent damage of any component of the package duc. to free:_ir;.

9. The total radioactivity in the coolant shall not exceed the limits specified ir.

10 CFR 571.36(a)(2).

10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).

11. Expiration date: April 30,1980.

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Page 4 - Certificate No. 5942 - Revision flo. 2 - Docket f o. 71-5942 REFEREttCES General Electric application dated December 23, 1958.

Supplements dated: February 4, 8, and 27, 1969; February 25, 1970; and April 4 and June 7, 1972.

Additional References Required for the Contents Limited In Item 5.(b)(2)(vii).

University of flissouri application dated January 10, 1979.  !

Supplement 'da ted: ftay 22, 1979.

FOR THE U.S. f;UCLEAR REGULATORY C0". MISSION h / "

Charles E. MacDonald, Chief Transportation Branch Division of Fuel- Cycle and

!!aterial Safety Date: JUN 1219/S

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B. ANTICIPATED SCHEDULE C. P.0UTE

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SHIPPING DATA B. Anticipated Schedule

1. Date of leaving reactor site 30 July 79

2. Date of arriving at reprocessing site or other. 1 August 79 C. ROUTE Approx. Miles PROPOSED: ,

From Columbia, MISSOURI I-70 125 Mis 5DURI I-55 5 ILLIN0IS I-64 75' ILLIN0IS I-57 45 ILLill0IS I-24 50 KENTUCKY I-24 18 KGillCKY US-67 2 KENTUCKY US-68 50 KENTUCKY I-24 20 TENNESSEE US-41 Al ternate 20 TENNESSEE I-24 _idu GEORGIA I-75 115 GEORGIA I-285 41 GEORGIA 132 I_-20 SDDTH C6ROLINA US-25 IZ To Savannah SOUTH CAROLINA US-278 15 River Plant TOTAL 875 continued on page 2 of Shipping Data I' -J cr ((j 9

Page 2 of Shipping Data C) Route - continued Approx. Miles PROPOSE _D ALTERNATE:

From Columbia, MISSOURI I Mn-47 60 MISSOURI M0 MO-100 20 MIS _SOURI MO-100- I-44 13 MISSOURI I MO -141 13 MISS0_URI M0-141 '-55 8 MISSOURI I MU-?? - ILL-146 100 ILLINOIS ILL-146- ILL-3 4 ILLIt10IS ILL US-fLO]_62 30 KENTUCKY US I-24 43 KENTUCKY I Western Ky Pkwy 36 -

KENTUCKY W.Ky Pkwy - Green River Pkwv -I-65 58 KENTUCKY I Cumberland Pkwy 26 KENTUCKY Cumberland P. - I-75 139 KENTUCKY I US-25E 12 TENNESSEE US-25E- I-81 110 TEtiESSEE I41 I 10 10

!!ORTit-CARILIW I -< 0 I46 60 NORTH CAROLINA I SC US-25 25 To Savannah SOUTH CAROLINA US BYPASS 25 - US-278 140 Ri-verJ1 ant Total 907

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- _ = _ _ _ - _ _ _

Entered by ___ Checked by Of Date

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IflFORMATION FOR SECTI0tlS D, E, APID F WILL BE PROVIDED BY THE f1RC STAFF ACCORDIflG TC fiUREG 0561.

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ROUTE LOG Origin _ Destination

• Time and date arriving Time and date leaving

• flo unauthorized stops en route will be made including off-site truck terminal lay-over at end of haul .

STATE CASK C0tlDITI0tl.t;0TES

. TIME . MILEAGE ROUTE Estimated Actual e

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A Specific Precautions:

1. Do not park adjacent to another truck carrying radioactive materials.

2. Do not park nearer than 50 yards to gasoline, petroleu:n products, explosives or chemical trucks.

3. Do not park at filling stations any longer than necessary to fill tanks and while there, always have at least one driver in the cab.

4. Do r.ot park at regular commercial truck depots.

Reviewed by Checked by Of (Ca rr ier)

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I Drwkhaven 516 345-2203 6 . Idaho 203. 5250I11 2 Cak Ridge _ , ,- ' 615 /,S3-3611

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Shipping Instructions to Carriers A. Motification of Departure Time At the time of departure, advise the University of Missouri Research Reactor Facility, Columbia, Missouri, 65211, of the time of departure and any anticipated modification in the scheduled transit by phone (314-882-4011).

B. Notification in the event of delay or required change in route.

The time scheduled for this shipment from departure to arrival is hours. When it is apparent that delays for any reason will increase this time by four (4) hours or more, advise the University of Missouri Research Reactor Facility, Columbia, Missouri, 65211, by phone (314-882-4011) of the new estimated time of arrival and the cause of delay. Any change in route must be cleared with the University of Missouri Research Reactor Facility before making them.

C. Inspection by authorized officials en route.

This shipment is proceeding under the full compliance of all known regulations and with the anthorization of all cognizant authorities. At each port of entry, this Record and Report Form and the Bill of Lading should be presented for the inspection of the responsible authorities and they are to be permitted access to the truck and its load for their inspection purposes. Under no conditions should anyone except the consignee be permitted to release tie-down cables, open parts boxes, or break seals without having written authori-zation from the University of Missouri Research Reactor Facility.

D. Notification in the event of emergency involving the load.

In the event of emergency that involved the shipment, notify:

1. Local fire and police departments.

2. The University of Missouri Research Reactor Facility.

(day) area code 314-832-4011 (nigh t) area code 314-832-4013

3. US ERDA designated regional office (see attichment).

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t Shipping Instructions to Carriers - continued E. Measures to be taken in case of fire or accident.

1. There is no explosion hazard f rom the shipment.

2. There is reasonable time (probably as much as one (1) hour) to take action to avoid any radiological hazard in the event of fire.

3. Keep sightseers back from the shipment - 50 yards.

4. Treat as petroleum fire - use foam type blanketing agent or C0 Avoid direct extinguishers for small fires.

might tend to spread any solid radioactivity.

5. Use ganna radiation survey meters while approaching - not to exceed 10 mr/hr. (These meters are to be acceptable to the University of Missouri Research Reactor Facility and calibrated before each trip.)

F. Route Log. .

The carrier agrees to stop at a safe stopping place (at least 100 yards away from any building) every 50 miles to check tire conditions and other mechanical

' conditions of the truck and to log time and place and results of this inspection.

Additionally, approximately every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the carrier is to inspect the general condition of the shipment and the tie-downs and to monitor for radiation with a survey meter. (Should snow or ice or other material be present and possibly The maximum readings impairing the cooling efficiency, it should be removed.)

permitted are:

1. At surface of cask - 200 mr/hr

2. At 6 ft. from surface - 10 mr/hr

3. In drivers' compartment - 2 mr/hr These readings obtained are to be logged, and the conditions of tie-downs and other data logged. Copy of the log is to be sent on arrival by Air Mail to the University of Missouri Research Reactor Facility, Columbia, Missouri 65211, Should survey meter readings be above those shown, notify the University of Missouri Research Reactor Facility (See D.2 above).

G. Stops en route.

Under no conditions is the truck with this shipment to be lef t unattended.

Every reasonable precaution has been taken to assure the safety of shipment and tie-down system. However, special operation attention is needed to avoid contingent accident by avoiding accident possibilities.

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