ML20008D751

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Certificate of Compliance 5942,Revision 4,for Model GE-700
ML20008D751
Person / Time
Site: 07105942
Issue date: 06/18/1980
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML19320A679 List:
References
19077, NUDOCS 8007020506
Download: ML20008D751 (8)


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CERTIFICATE OF COf#U ANCE For Rad.oective Materials Pechages 1.(a) Ce $d.cate Number 1.lb) Revision No.

1.(c) Package identification No.

1 (d) Pages No. 1.(e) Total No. Pages 942 4

USA /5942/Bf IF 1

1

2. PREAMBLE 2.(a)

This ce.id.cate is issued to satisf y sections 173.393a 173.394.173.395, and 173.396 of the Department of Transportation Hazardous Vate..ats Regulations (49 CFB 170129 and 14 CF R 103) and Sections 146-19-10s and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149). as emended.

2.10)

The pockeging and contents described in item 5 below. meets the safety stendards set forth in Subpart c of Title 10. Code of FMerel Regulat.ons, Part 71, ** Packaging of Radioactive Materials for Transport end Trensportesion of Rad.oective Materiet Under Certa.n Condit.ons.

2.(c)

This certif.cate do-kt relieve the consignor from compliance with any requirement of the reputations of the U.S. Department of Transportai.on or other applicable regwiatory egencies, including the government of any country through oe into which the pockege well be transported.

3. Thes certifecate is issued on the basis of a safety anal'ysis report of the packege design or application-3 (a)

Prepared by (Name and address):

3.(b)

Title and identificaticn of report or opplication:

General Electric Company General Electric Application dated March 18, 1980, P.O. Box 460 as supplemented.

Pleasanton, CA 94566 3.(ci oochei No. 71-5942

4. Co'dD ai tGrd'i Tr.s cc tificate is conditional upon the fulfilling of the requirements of Subpart D of to CFR 71. et applicable, and the condit ons scec4f.ed

.n.iem 5 beio.

5. oev.repi.on of Pac.aains and Authorized Contents. Model Number. Fissile Ctess. Other Conditions. and References-(

(a)

Packaging (1) Model No.:

GE-700 (2) Description A steel encased Icad shielded shipping cask enclosed by a double-walled protective jacket of the same shape with a rectangular baseplate. The cask is a double-walled steel circular cylinder, 37-inch-diameter by 65-inch high with a central cavity 15-inch-diameter by 40-inch high.

Approximately 10.25 inches of lead surround the central cavity.

The cask is equipped with a cavity drain line, pressure relief valve set at 100 psig, and lifting device.

Closure is accomplishe'd by a silicone rubber gasketed and bolted "M1 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 with an additional. silicone rubber gasket. The modified cask is 79 inches high l

and weighs 28,000 pounds.

(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:

237E325, Rev. 2 289E646, Rev. 3 10604150, Rev. 0 289E647, Rev. 1 D1331 Rev. u M 89E642, Rev. 2 I

195F127. Rev. 0 1 GD4059 Rev. 1

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Page 2 - Certificate No. 5942 - Revision No. 4 - Docket No. 71-5942 5.

(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 (1) 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 88 rods loaded with 0.376-inch-diameter pellets with a minimum active fuel length of 37 inches; or (v) those values presented in Figure 1. U0, Weight Limits for Model 700 Shipping Container, of Exhibit A to this application, applicable to fuel material in the form of rods with a minimum pellet diameter of 0.40 inch; or (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel elements (GETR Fuel) with each element containing no more than 510 gm U-235 and inserted in the spaced stainless steel fuel shipping basket described in GE Drawing No.106D4150, Rev. O.

(vii) 6,200 gm U-235, provided the fuel is in the form of MURR TRTR type 3 ements containing not more than 775 gm U-235 per element; loaded and 1

spaced in the stainless steel fuel shipping basket as described in MURR Drawing No. 1228, Sheets 1 thru 5, Revision O.

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

(3) Maximum 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 for transport.

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

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Page 3 - Certificate No. 5942 - Revision No. 4 - Docket No. 71-5792 a

The radioactive material shall be it, the form of fuel rods, or plates, fuel 6.

assemblies, or meeting special form requirements of 10 CFR 571.4(o).

i 7.

Shoring shall be provided to minimize movement of contents during accident conditions of transport.

Prior to each shipment'the silicone rubber lid gasket (s) shall be inspected. This 8.

gasket (s) shall be replaced if inspectiun shows any defects or every twelve (12) months, whichever occurs first. Cavity drain line shall be sealed with appropriate sealant applied to threads of pipe plug.

The applicant shall confirm annually that the pressure relief valve is operable at 9.

100 psig.

10. When needed, sufficient antifreeze in the cask shall be used to prevent damage of any component of the package due to freezing.
11. The total radioactivity in the coolant shall not exceed the limits specified in 10 CFR 571.36(a)(2).
12. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.!2(b).

13.

Expiration date: June 30,1985.

REFERENCES General Electric application dated fiarch 18, 1980.

l Additional Reference Required for the Contents Limited In It.: 5. (b)(2)(vii ).

University of Missouri letter dated March 20, 1980.

A' pen:ix 6-A regarding University of Missouri's quality assurance program is not considered part ot~ this application.

l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

Charles E. MacDonald, Chief i

Transportation Certification Bran:h Division of Fuel Cycle and Material Safety i

1 JUN 181930 Date:

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I PREPARATION OF SOURCE j

- 1.

Build table in cave to hold source.

2.

Install band saw, provide for remote operation.

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3.

Practice use of band saw with dummy basket.

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% Set new support for source, so that source can be lowered onto it.

5.

Close door, set source on new support.

6.

Transfer cable look to new support.

7.

Put source on its side, put basket handles in saw.

8.

Saw cff h= dies.

9..

Return source to well.

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SOURCE SHIPMENT PROCEDURE 1.

Shipping cask arrives.

2.

Inspect, survey and wipe cask jacket, record data.

3.

Remove the 8 each 2" bolts securing the jacket to the base.

4.

Sling jacket and lift off from the cask.

Note: Observe positioning of the cask and jacket on the base and make index marks for later reassembly. (Step 43) 5.

Wipe-test the cask, and inspect in accordance with 10 CFR 71.

6.

Remove the steel spacer from the cask lid lif ting eye (weight - 250 lbs.)

Note: Spacer not included when cask is fitted with the extension cavity.

7.

Remove the 8 each 3/4-10 lid bolts and lid.

Note: Observe the 4" thick gasket inside the metal retaining ring. Use caution during handling to keep the retaining ring and gasket in place.

8.

Survey and wipe-test inside of cask.

9.

Install cask insert.

10.

Replace cask lid.

11.

Locate truck under hoist.

12.

Lif t cask, drive truck out, set cask on concrete.

13.

Lower hoist beam and install door patch beam.

14.

Lif t cask and trolly into cave - set on floor.

15.

Trolly hoists to fixed beam.

16.

Remove beam extension, set on cave flocr.

17.

Raise cask lid with small hoist, practice lowering.

18.

Tie chain leader to lid.

19.

Practice moving lead shot hopper spout.

20.

Practice installing lid on inner container.

l 21.

Remove door patch beam.

22.

Close door.

23.

Raise source and drip dry.

24.

Trolly source to position near cask.

25.

Using manipulators, guide source into cask.

26.

Using manipulators, remove cable hook.

27.

Using manipulators, move lead shot spout over cask.

28.

Using manipulators, open valve on shot hopper.

29.

Using manipulators, level shot and remove spout.

30.

Using manipulators, put lid on inner liner.

31.

Using manipulators, put nuts on to hold inner lid.

32.

Place chain on insert lid to clear cc.i lid seat area.

33.

Lower cask lid.

34.

Open door with careful monitoring.

35.

Monitor and wipe test cask.

36.

Bolt lid on.

37.

Install trolly beam extension.

38.

Reinstall cave door patch beam.

39.

Return hoists to cask area.

40.

Lif t cask and trolly out of cave.

41.

Set cask on concrete.

42.

Raise hoist beam.

43.

Lift cask and set on base on truck. Note index marks (Step 4) to assure proper orientation.

44.

Install steel spacer on cask lid.

45.

Install protective jacket.

1 Note: Observe orientation of jacket to assure fit.

46.

Install 8 each 2" bolts securing jacket to the base.

47.

Do final monitoring and wipe tests.

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I" TRANSPORTATION APPROVALS" 7['

V Docket No.

William O. Miller License Fee Management Branch Office of Administration i

MATERIALS TPANSPORTATION APPROVAL CLASSIFICATION Applicant:

d Cd Approval l'o:

'[9 SM Fee Category ///8/

Application Dated: I///rP /

Received:

Applicant's Classific'at' ion:

'1 The above application for amendment has been reviewed by the NMSS Transportation Branch, in accordance with Section 170.31, and is classified as follows:

1. ' Amendments to Acorovals in Fee Catecories 11A throvoh 11E (a)

Major (b) d!inor I

(c)

Administ -'ive 2

Justification for reclassification:

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The application was filed (a) pursuant to written NRC request and the amendment is being issued for the convenience of the Commission, or (b)

Other (State reason):

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Transportation Bran'ch, !!iSS Date:

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