ML19331C244
| ML19331C244 | |
| Person / Time | |
|---|---|
| Site: | 07105957 |
| Issue date: | 07/28/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19331C243 | List: |
| References | |
| NUDOCS 8008140439 | |
| Download: ML19331C244 (6) | |
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Farm NRC.618 U.S. NUCLEAR. REGULATORY COMMISSION II CERTIFICATE OF' COMPLIANCE 10 CFR n For Radioactive Materials Packages 1.Lil Certificate N 1.(t,) R vision No.
1.( )
fi on No.
1.(d) Pages No. 1.(e) Total g Pages
- 2. PREAMBLE 2.tal This certificate is issued to satisfy Sections 173.393a.173.394.173.395, and 173.396 of the Department of Transportation Haanrdous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), es amended.
2.lb)
The packaging and contents deseibed in item 5 below, rneets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations. Part 71. **Pockaging of Radioactive Materials for Transport and Transportation of Radioactive Meterial Under Certain Conditions."
2.(c)
This certif cate does not relieve the consignor from complia~s with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies. including the government of any country through or into which the package wdl be transported.
- 3. This cartificate is issued on the basis of a safety analysis report of the package design or applicatiert-3.fal Prepared by (Name and address):
3.fb)
Title and identification of report or application:
Battelle Columbus Laboratories Battelle Columbus Laboratories application 505 King Avenue dated June 11, 1980.
Columbus, OH 43201 3.(c) ooeket No.
- 4. CONDITIONS This cartificate is conditional upon the fulfilling of the requirements of Subpart 0 of 10 CFR 71, as applicable. and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents. Model Number, Fissile Class. Other Conditions, and
References:
(a) Packaging (1) Modirl No.:
BMI-l (2) Description
'A steel-encased lead shielded shipping cask.
The basic cask body is a cylinder 33.37 inches in diameter by 73.37 inches high formed by two concentric stainless steel shells whose annular region is fil. led with lead.
The outer 1/2-inch thick shell has a 0.12-inch thick plate spot welded to it, providing a 0.06-inch thick air gap insulator.
The inner shell is 15.5 inches inside diameter by 54 inches inside length.
The cask lid is a stainless steel weldment having 7.75 inches of lead shielding.
Tne cask lid is secured to the cask by twelve steel studs which are welded to the cask body.
Cask appurtenancies include a drain line with ne'edle valve and plug, pressure gauge, and a pressure relief valve. The total cask weight, includin,g maximum contents of 1,800 lbs, is 23,660 lbs.
(3) Drawings The cask is constructed in accordance with the following Battelle Memorial Institute (BMI) Drawing Nos.:
0001, Rev. B; and 0003, Rev. B.
l 8008140430
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Page 2 - Certificate No. 5957 - Revision No. 6 - Docket No. 71-5957 5.
(a) Packaging (continued)
(4) Product Containers The various authorized product containers are constructed in accordance with the following Drawing Nos.:
(i)
Inner can assembly as shown in BMI Drawing No. 00-000-421, Rev. C.
(ii) Basket Assembly as shown in BMI Drawing No. 0004, Rev. B.
l (iii) Fermi Fuel Element copper casting assembly as shown in BMI Drawing No. 0049, Rev. to May 12, 1966.
(iv) Basket Assembly as shown in BMI Drawing No. 1020, Rev. B.
(v) Basket Assembly defined by BMI Drawing No. 0004, Rev. B, as modified by BMI Drawing No. 00-00-236, Rev. A.
(vi) Basket Assembly and storage can defined by BMI Drawir.g No.
00-000-391, Rev. C, and Atomic International Drawing No. AIHL, 580R 0019-01, Rev. A, respectively.
(vii) BMI-l Cask Basket Spacer for ALRR Converter Fuel; Ames Laboratory Research Reactor, Drawing No. RRM 245, Dated 4/3/77.
(viii) Basket Assembly as shown in BMI Drawing No. 0004, Rev. B, as modified by BMI Drawing No. 00-001-376, Rev. A, and fuel canister as shown in BMI Drawing No. 00-001-375, Rev. O.
(b) Contents (1) Type and form of material (i)
Intact irradiated MTR or BRR fuel assemblies containing not more than 200 grams U-235 per assembly prior to irradiation.
Uranium may be enriched to a maximum 93 w/o in the U-235 isotope. Active fuel length shall be 25 inches.
(ii)
Intact irradiated Enrico Fermi Core. A fuel assembly containing not more than 4.77 kgs U-235 prior to irradiation.
Uranium may be enriched to 25.6 w/o in the U-235 isotope.
(iii) Greater than Type A quantities of radioactive material which may include uranium enriched in the U-235 isotope, U-233, plutonium, as metal, evides, or compounds which are thermally stable up to 60CAF.
Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor ele 11ents.
(iv) Greater than Type A quantities of byproduct material in special form.
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Page 3 - Certificate No. 5957 - Revision No. 6 - Docket No. 71-5957 (b) Contents (continued)
(1) Type and form of material (continued)
(v) Greater than Type A quantities of byproduct material in normal form as metal, oxides, or compounds which are thermally stable up to 600 F.
3 (vi) Irradiated Triga Type III fuel assemblies containing not more than 40 grams U-235 per assembly prior to irradiation. Uranium may be enriched to a maximum 20 w/o in the U-235 isotope.
Active fuel length shall be 15 inches for stainless steel clad assemblies and 14 inches for aluminum clad assemblies.
(vii) Irradiated S80R fuel elements 0.56-inch OD by 18.7 inches long by 0.010-inch wall thickness of Haste 11oy-N.
The fuel material is UZrH fully enriched in U-235.
(viii)
Intact irradiated CP-5 fuel assemblies containing not more than 176 grams U-235 per assembly prior to irradiation. Uranium may be enriched to a maximum 93 w/o in the U-235 isotope.
Active fuel length shall be 28.5 inches.
(ix) Irradiated Pulstar Zircaloy clad fuel pins containing not more enriched to a maximum 6.0 w/ prior to irradiation.
Uranium may be than 31 grams U-235 per pin o in the U-235 isotope. Active fuel length shall be 24 inches.
(x) Solid nonfissile irradiated hardware which may contain encapsulated fission monitors.
(2) Maximum quantity of material per package The minimum cooling time of each fuel assembly and rod shall be 90 days, maximum decay heat generation per package not to exceed 1.5 kw, and the external dose rate not to exceed 10 mrem /hr 3 feet from the external surface of the cask and:
(i). For the contents described in 5(b)(1)(i):
Twenty-four (24) fuel ass emblies as contained in product containers specified in 5(a)(4)(ii) or 12 fuel assemblies as contained in product containers specified in 5(a)(4)(v).
(ii) For the contents described in 5(M(.)(ii):
One (1) fuel assembly as contained in product container specified in 5(a)(4)(iii).
(iii) For the contents described in 5(b)(1)(iii):
480 grams U-235 or 480 grams Pu-239 or 800 grams U-235 as contained in product container specified in 5(a)(4)(i).
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Page 4 - Certificate No. 5957 - Revision No. 6 - Docket No. 71-5957 5.
(b) Contents (continued)
(2) Maximum quantity of material per package (continued)
(iv) For the contents described in 5(b)(1)(iv):
Gamma sources securely confined in the cask cavity to preclude secondary impacts during accident conditions of transport.
Thermal heat generation rate shall be limited to 200 watts.
(v) For the contents described in 5(b)(1)(v):
Contained in product containers specified in 5(a)(4)(i) and limited as follows:
10 CFR 71 Transport Group Quantity Curies I
1,000 II 8,120 Mixed Fission Products Unlimited III 4,960 IV 11,070 V
8,120 VI and VII 800,000 (vi) For the contents described in 5(b)(1)(vi):
Thirty-eight (38) fuel assemblies as contained in product containers specified in 5(a)(4)(iv).
(vii) For the contents described in 5(b)(1)(vii):
Twenty-four (24) fuel elements per can and six sealed cans per basket as described in 5(a)(4)(vi).
Each of the six cans may contain up to 818 g U-235 and 158 g hydrogen.
The cask is limited to 4.908 kg U-235.
(viii) For the contents described in 5(b)(1)(viii):
Twelve (12) fuel assemblies.
(ix) For the contents described in 5(b)(1)(ix):
Twelve (12) canisters containing 21 fuel pins each, contained within the canister and fuel basket specified in 5(a)(4)(viii).
(Dummy 1
fuel canisters, non-buoyant, shall occupy empty basket positions.)
(x) For_the contents described in 5(b)(1)(x):
Hardware shall De securely confined in the ca n cavity to preclude secondary impacts during accident conditions of transport, thermal heat generation rate shall be limited to 200 watts.
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j Page 5 - Certificate No. 5957 - Revision No. 6 - Docket No. 71-5957 5.
(c) Fissile Class I and III (1) Class I For the contents specified in 5(b)(1)(iii) and limited in 5(b)(2)(iii).
(2) Maximum number of For the contents specified in 5(b)(1)(i),
packages per shipment 5(b)(ii),5(b)(1)(vi),5(b)(1)(vii),5(b)(1)(viii),
as Fissile Class III and 5(b)(1)(ix); and limited in 5(b)(2)(i),
5(b)(2)(ii),5(b)(2)(vi),5(b)(2)(vii),
5(b)(2)(viii), and 5(b)(2)(ix).
One (1) package.
6.
For Item 5(b)(1)(iii), mixtures cf fissile material are authorized, provided the following equation is satisfied:
X Y
Z g
g g
< 1, where
+
+
X = Grams U-233 to be shipped Y = Grams Pu-239 to be shipped I = Grams U-235 to be shipped 7.
Except for contents described in 5(b)(1)(ii) and 5(b)(1)(iv); cad limited in 5(b)(2)(ii) and 5(b)(2)(iv), the cask shall be shipped dry.
8.
If the cask contents of 5(b)(1)(ii) or 5(b)(1)(iv) are shipped wet, the licensee shall confirm that the pressure relief valve is operable (set pressure - 75 psig).
l When needed, sufficient antifreeze in the cask shall be used to prevent damage of any component o' the package by freezing.
9.
Loading and unloading, operations of the contents described in 5(b)(1)(iii) and limited in 5(b)(2)(i11) shall preclude contact of water with the contents.
10.
The presence and effectiveness of the Boral poison plate in the Basket Assemblies as shown in BMI Drawing Nos. 0004, Rev. B, and 00-000-236, Rev. A, shall be verified by neutron measurements prior to first use and records maintained of such verification.
Verification of the presence of the Boral shall be made in each subsequent use.
11.
Prior to each use, adequacy of containment vessel i!. ell be demonstrated by perform-ance of the leak test described in Section 7.1 1.1 of the application.
12.
Gaskets and seals (cask and fuel canister) shall be replaced at least every 12 months or earlier if visible degradation occurs.
13.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12(b).
14.
Expiration date:
July 31, 1985.
Page 6 - Certificate No. 5957 - Revision No. 6 - Docket No. 71-5957 REFERENCE Battelle Columbus Laboratories application dated June 11, 1980.
l i
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JUL 2 81980 Date:
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