ML20134H181
| ML20134H181 | |
| Person / Time | |
|---|---|
| Site: | 07106568 |
| Issue date: | 02/04/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20134H180 | List: |
| References | |
| NUDOCS 9702110191 | |
| Download: ML20134H181 (5) | |
Text
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' p NRC FORM 618 U.S. NUCLEAR RE!ULATORY COMM2SION
?m CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES I
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'I.a CERTinCATE NUMBER
- b. REVISION NUMBER
- c. PACKAGE IDENTIRCATION NUMBER d PAGE NUMBER
- e. TOTAL NUMBER PAGES B
6568 10 USA /6568/A 1
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- 2. PREAMBLE E
- s. This certificate is issued to certify that the packaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10.
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Code of Federal Regulations, Pan 71 "Packagmg and Transportation of Radioactive Material."
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- b. This ceruficate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherI applicable regulatory agencies, including the government of any country through or into which the package will be transported.
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- 3. THIS CERTIRCATE IS ISSUED ON THE B ASIS OF A $AFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
- a. ISSUED TO(Name and Address) b TITLE AND IDENTIRCATION OF REPORT OR APPLICATION:
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l-p Chem-Nuclear Systems, Inc.
Tennessee Valle, Authority application g
g 140 Stoneridge Drive dated August 16, 1976, as supplemented.
g Columbia, SC 29210 g
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- c. DOCKET NUMBER 71-6568 g
y 4 CONDITIONS i
g This certificate is conditional upon fulfilling the requirements of 10 CFR Pan 71, as applicable, and the conditioris specified below.
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y (a) Packaging 1
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(1)
Model No.:
LL-60-150 f
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Description l
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The cask is cylindrical in shape 93 inches long and 82.5 inches in I
diameter.
Lead shielding, 3-1/2 inches thick, is encased within the I-N N
inner and outer steel shells that are welded to a laminated steel base I
plate assembly. The cover is a steel plate assembly secured to the top I
E flange by 36 steel bolts.
Encircling the top of the cask is a partial I-I length steel shell of 1/2-inch thickfass. Silicone 0-rings provide seals I
8 at the top cover and at all plugs, lhe inner container is right circular I
steel cylinder with a capacity of ISO cu ft. The total weight, when F.
8 loaded, is approximately 73,000 pounds.
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(3)
Drawings I
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N The packaging is constructed in accordance with the following ATCOR Inc.
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Drawing Nos.: 0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 05268-B-0010, L
B Rev. E; 0568-8-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and L
b 0568-R-0001, Rev. J.
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5 Page 2 - Certificate No. 6568 - Revision No. 10 - Docket No. 71-6568 I
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(b)
Contents r
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Type and form of material r
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p Process solids, either dewatered, solid, or solidified waste, in i
e sealed coitainers, and limited to the following:
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(i)
Materials in which the radioactivity is essentially uniformly I
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distributed and in which the estimated average concentration r
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0.0001 millicurie of radionuclides for which the A quantity I
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in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; r
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0.005 millicurie of radionuclides for which the A, quantity in l
p Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not r
p more than 1 curie; or r
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r 0.3 millicurie of radionuclides for which the A q i
Appendix A of 10 CFR Part 71 is more than 1 curie.uantity in p
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r pI (ii) Objects of nonradioactive material externally contaminated t
p with radioactive material, provided that the radioactive i
gl material is not readily dispersible and the surface q
l Il gI contamination, when averaged over an area of I square meter, r
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does not exceed 0.0001 millicurie (220,000 disintegrations t
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per minute) per square centimeter of radionuclides for which t
g the A, quantity in Appendix A of 10 CFR Part 71 is not more t
g than 0.05 curie,.or 0.001 millicurie t
g (2,200,000 disintegrations par minute) per square centimeter g-J p
for other radionuclides.
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(2)
Maximum quantity of material per package g
l Greater than Type A quantity of radioactive material with the
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g weight of the package contents and secondary containers not r
y exceeding 12,500 pounds.
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NRc FORM 614A CONDmONS fr<mimwds U.S. NUCLEAR REOULATORY COMMISSION g
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B Page 3 - Certificate No. 6568 - Revision No. 10 - Docket No. 71-6568 I
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6.
(a)
For any package containing water and/or organic substances which could r
D radiolytically generate combustible gases, determination must be made by r
B tests and measurements or by analysis of a representative package such 0
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that the following criteria are met over a period of time that is twice r
B-the expected shipment time:
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(1)
The hydrogen generated must be limited to a molar quantity that t
5 would be no more than 5% by volume (or equivalent limits for other r
p inflammable gases) of the secondary container gas void if present r
p at STP (i.e., no more than 0.063 g-moles /ft3 at 14.7 psia and i
p 70*F); or i
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(2)
The secondary container and cask cavity must be inerted with a r
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diluent to assure that oxygen must be limited to 5% by volume in i
p those portions of the package which could have a hydrogen g
g concentration greater than 5%.
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For any package delivered to a carrier for transport, the secondary r
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container must be prepared for shipment in the same manner in which
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y determination for gas generation is made. Shipment period begins when i
p the package is prepared (sealed) and must be completed within twice the i
g expected shipment time.
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(b)
For any package shipped within 10 days of preparation, or within 10 days g
after venting of drums or other secondary containers, the determination i
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in (a) above need not be made, and the time restriction in (a) above does g
g not apply.
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In addition to the requirements of Subpart G of 10 CFR Part 71:
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Each pac.kage must be maintained in accordance with Reactor Cleanup Cask
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Maintenance Program in the supplement dated February 20, 1991.
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(b)
The package must be prepared for shipment and operated in accordance with I
g the Reactor Cleanup Cask Operating Procedure in the supplement dated L
1 February 20, 1991.
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The package authorized by this certificate must be transported on a motor I
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vehicle, railroad car, aircraft, inland water craft, or hold or deck of a L
sesgoing vessel assigned for sole use of the licensee.
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9.
Fabrication of additional packagings is not authorized.
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10.
The package authorized for use by this certificate is hereby approved for use L-U i
under the general provisions of 10 CFR 671.12.
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Page 4 - Certificate No. 6568 - Revision No. 10 - Docket No. 71-6568 E
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B 11.
Expiration date: April 1, 1999. This certificate is not renewable.
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b REFERENCES E
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D Tennessee Valley Authority application dated August 16, 1976.
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Supplements dated: October 8, 1976; October 5, 1979; October 23, 1980; r
B February 20, 1991; February 29, and September 30, 1996.
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Chem-Nuclear Systems, Inc. supplement dated December 20, 1996.
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e FOR THE U.S. NUCLEAR REGULATORY COMMISSION L
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Cass R. Chappell, Chief i
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Safety and Safeguards t
Date:
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 30eeH001
'+,.....,o APPROVAL RECORD Model No. LL-60-150 Certificate of Compliance No. 6568 Revision No. 10 By letters dated September 30, and December 20, 1996, the Tennessee Valley Authority and Chem-Nuclear Systems, Inc. requested that the certificate holder for Certificate of Compliance No. 6568 for the Model No. LL-60-150 package be changed from the Tennessee Valley Authority to Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Chem-Nuclear Systems, Inc. will be responsible for maintenance of the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 671.91(c). Chem-Nuclear Systems, Inc. stated that the records required by 10 CFR 971.91(c) for the package design will be maintained at their Columbia, South Carolina offices.
Chem-Nuclear Systems, Inc. has been issued Quality Assurance Program Approval for Radioactive Materials Packages No. 0231, under Subpart H of 10 CFR Part 71.
The Certificate has been revised to show Chem-Nuclear Systems, Inc. as certificate holder. These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.
M4 Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date:
02/04/97 4
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