ML20134D599
| ML20134D599 | |
| Person / Time | |
|---|---|
| Site: | 07106601 |
| Issue date: | 01/30/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20134D598 | List: |
| References | |
| NUDOCS 9702050270 | |
| Download: ML20134D599 (5) | |
Text
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& 80 CERTIFICATE OF COMPLIANCE
'*7' FOR RADIOACTIVE MATERIALS PACKAGES U
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- 1. L CERTif1CATE NUMBER
- b. REVISION NUMBER c PACKAGEIDENTIFICAT10N NUMBER
- d. PAGE NUMBER e TOTAL NUMBER PAGES g
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p 6601 26 USA /6601/A 1
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- 2. PREAMBLE
- s. 'Dus ternficate is issued to certify that the packaging and contents described in hem 5 below, meets the applicable safety standards set fonb in Title 10, N
N Code of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Material."
- b. This certificate does not relieve the consignor from comphance with any requirement of the regulations of the U.s. Department of Transportation or other N
N apphcable regulatory agencies, including the government of any country through or into which the package will be transported.
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N 3 THIS CERT!FlCATE IS ISSUED ON THE D ASIS OF A SAfl.TY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
- a. ISSUED TO f %me and AddrrnJ b 'llTLE AND IDENTIFICATION OF REPORT OR APPLICATION.
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Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application g
g 140 Stoneridge Drive dated August 23, 1985, as supplemented.
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Columbia, SC 29210 g
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71-6601 p
- c. DOCKET NUMBER g
- 4. CONDITIONS g
g This certificate is conditional upon fulfilhng the requirements of 10 CFR Pan 71, as applicable, and the conditions specified below.
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5.
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(a)
Packaging g
l (1)
Model No.: CNS 8-120A l
l (2)
Description l
I E
The packaging is a steel-encased, lead shielded shipping cask which I
weighs approximately 70,000 pounds when loaded. The cask is 73.5 inches N
I in diameter by 92 inches high, with ~n effective cavity 62 inches in U
a N
diameter by 75 inches long.
Gamma shielding equivalent to 4.5 inches of I
I lead is provided by lead and steel. The outer shell is fabricated of I
8 two, 3/4-inch thick steel plates' and the inner shell of 1/2-and 1/4-inch I
N thick plates. The cavity is closed and sealed by thirty-two,1-3/4-inch I
E bolts and a silicone 0-ring within a recessed groove on the flange of the I
b cask. A steel collar encircles the outer shell in the lid area.
U 8
Shackles are used for lifting the packaging and the lid. Tie-down is N
D accomplished through a steel structure which.is not attached to the N
N package. The lid provides several threaded and sealed access plugs and a
b the base has a drain line.
N R
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(3)
Drawings N
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D The package is constructed in accordance with Chem-Nuclear Systems, Inc.
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Drawing No. 29008-1, Sheet 1 Rev. 2, and Drawing No. 29008-1, Sheet 2, 4
b Rev. 2.
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p Page 2 - Certificate No. 6601 - Revision No. 26 - Docket No. 71-6601 d
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5.
(b)
Contents N
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(1)
Type and form of material g
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p Process solids, either dewatered, solid, or solidified, or solid a
y reactor components, in secondary containers, and limited to the g
g following:
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(i)
Materials in which the radioactivity is essentially uniformly g
g distributed and in which the estimated average concentration g
g per gram of contents does not exceed:
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E 0.0001 millicurie of radionuclides for which the A,05 curie; quantity g
b in Appendix A of 10 CFR Part 71 is not more than 0.
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g 0.005 millicurie of radionuclides for which the A quantity in g
2 g
Appendix A of 10 CFR Part 71 is more than 0.05 cuiie, but not l g 9
more than 1 curie; or g
l 0.3 millicurie of radionuclides for which the A q Appendix A of 10 CFR Part 71 is more than 1 curie uan+.ity in g
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l (ii) Objects of nonradioactive material externally contaminated l
g with radioactive material, provided that the radioactive g
al material is not readily dispersible and the surface g
g contamination, when averaged over an area of I square meter, g
does not exceed 0.0001 millicurie (220,000 disintegrations per minute) per square centimeter of radionuclides for which the g
5 A quantity in Appendix A of 10 CFR Part 71 is not more than g
2 5
I 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per square centimeter for other radionuclides.
l (2)
Maximum quantity of material per package l
5 Greater than Type A quantity of radioactive material, not to E
5 exceed 2,000 times a Type A quantity, 40 thermal watts, and 20,000 0
pounds including weight of the contents, secondary container (s)
E 8
B and shoring. The contents may include fissile materials provided U
B the mass limits of 10 CFR 571.53 are not exceeded.
I B
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6.
Except for close fitting contents, wood shoring must be placed between the U
B secondary container (s) (or activated components) and the cask cavity to N
9 prevent movement during normal conditions of transport.
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7.
Prior to each shipment, the lid gasket must be inspected. The gasket must be E
B replaced if inspection shows any defect or every 12 months which ever occurs E
B first.
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D 8.
Prior to each shipment, a determination must be made that closure seal E
D replacement is current with the seal replacement schedule in Section 8.2.2 of N
b the application.
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l pl Page 3 - Certificate No. 6601 - Revision No. 26 - Docket No. 71-6601 r
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9.
The packaging must be leak tested once every 12 months in accordance with r
Section 8.1.3 of the application.
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10.
The drain line and access plugs must be appropriately plugged and sealed prior r
to transport.
r r
y 11.
(a)
For any package containing water and/or organic substances which could r
y radiolytically generate combustible gases, determination must be made by r
p tests and measurements or by analysis of a representative package such t
y that the following criteria are met over a period of time that is twice r
y the expected shipment time:
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(1)
The hydrogen generated must be limited to a molar quantity that t
g would be no more than 5% volume (or equivalent limits for other 1
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inflammable gases) of the secondary container gas void if present 8
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at STP (i.e., no more than 0.063 g-moles /ft at 14.7 psia and g
9 70*F); or g
gl (2)
The secondary container and cask cavity must be inerted with a
[l diluent to assure that oxygen must be limited to 5% by volume in g
g those portions of the package which could have hydrogen greater than g
5%.
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j For any package delivered to a carrier for transport, the secondary
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container must be prepared for shipment in the same manner in which g
8 determination for gas generation is made.
Shipment period begins when 5
r the package is prepared (sealed) and must be completed within twice the l
expected shipment time, g
5 I
(b)
For any package shipped within 10 days of preparation, or within 10 days 5
g after venting of drums or other secondary containers, the determination 5
I in (a) above need not be made, and the time restriction in (a) above does not apply.
I g
B 12.
The package authorized by this certificate must be transported on a motor I
E vehicle, railroad car, aircraft, inland water craft, or hold or deck of a I
seagoing vessel assigned for sole use of the licensee.
L 9
0 9
13.
In addition to the requirements of Subpart G of 10 CFR Part 71:
0 B
I B
(a)
Each packaging must meet the Acceptance Tests and Maintenance Program of E
R Chapter 8 of the application; and I
B 0
B (b)
The package must be operated and prepared for shipment in accordance with r
B the Operating Procedures of Chapter 7 of the application.
L B
E D
14.
The package authorized by this certificate is hereby approved for use under L
b the general license provisions of 10 CFR 571.12.
I B
L b
15.
Expiration date: April 1, 1999. This certificate is not renewable.
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- NRC FORM 618A CONDITIONS inmimwds U.S. NUCLEAR REGULATORY COMMISSION g
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Page 4 - Certificate No. 6601 - Revision No. 26 - Docket No. 71-6601 l
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REFERENCES I
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Chem-Nuclear Systems, Inc., application dated August 23, 1985.
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Supplements dated:
December 30, 1985, January 16, 1991, October 29, 1991, i
p January 7, 1992, and January 29 and March 19, 1996.
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Northeast Nuclear Energy Company supplement dated:
February 9, 1984.
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION g
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Cass R. Chappell, Chief I
g Package Certification Section g
g Spent Fuel Project Office Office of Nuclear Material Safety y
and Safeguards g
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Date:
01/30/97 p
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't UNITED STATES j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, o.C. 30eeHo01 49.....,o l
APPROVAL RECORD Model No. CNS 8-120A Certificate of Compliance No. 6601 Revision No. 26 j
l l
Chem-Nuclear Systems, Inc. identified a typographical error in Certificate of j
Compliance No. 6601, Revision No. 26. The typographical error was an extra "not" in the third paragraph of Condition 5(b)(1)(i). As a result of the j
error, the concentration limit for certain radionuclides was not clear. The Certificate has been revised to correct the typographical error.
'j4'Y M<f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date 01/30/97 4
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