ML20134D630
| ML20134D630 | |
| Person / Time | |
|---|---|
| Site: | 07109262 |
| Issue date: | 01/30/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20134D620 | List: |
| References | |
| NUDOCS 9702050281 | |
| Download: ML20134D630 (3) | |
Text
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p NRC FORM 618 U.S. NUCLEAR REIULATORY COMMISSION g
m CERTIFICATE OF COMPLIANCE m cm ".
FOR RADIOACTIVE MATERIALS PACKAGES I
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1.a CERTIRCATE NUMBER b REVISION NUMBER
- c. PACKAGE IDENTIMCATION NUMBER
- d. PAGE NUMBER e TOTAL NUMBER PAGES l
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9262 1
USA /9262/A 1
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l
- 2. PREAMBli I
- a. This certincate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10, I
N Code of federal Regulations, Pan 71," Packaging and Transportation of Radioactive Material?
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- b. This certificate does not relieve the consignor from comphance weh any requirement of the regulations of the U.S. Department of Transportation or other L
N apphcable regulatory agencies,includmg the government of any country through or into which the package will be transported.
I N
I 3 THIS CERTinCATE IS ISSUED ON DIE B ASIS OF A SAFETY ANALYSIS REPORT OF DIE PACKAGE DESIGN OR APPLICATlON
- a. ISSUED TO(Name and Address)
- b. TITLE AND IDENEFICATION OF REPORT OR APPLICATION:
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Yankee Atomic Electric Company Yankee Atomic Electric Company g
y 580 Main Street application dated March 23, 1995, g
y Bolton, MA 01740-1398 as supplemented.
g B
I 7 -9262 y
c DOCKET NUMBER g
y 4 CONDITIONS l
g This cenificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
l N
i l
l (a)
Packaging l
l (1)
Model No.:
YNPS RPV l
l (2)
Description l
I A reactor pressure vessel contained within a cylindrical steel outer I
8 packaging, which is welded closed and filled with concrete. The reactor I
E vessel is an open, cylindrical, eight-inch thick carbon steel vessel with I
E a hemispherical bottom head.
The outer diameter of the reactor vessel is I
8 approximately 10 feet, 5 inches, and the length of the reactor vessel is 1
N approximately 26 feet,10 inches. - The reactor vessel main coolant I
8 nozzles are closed with shielded plugs. The reactor vessel is surrounded I
l I
with three-inch thick thermal insulation.
The reactor vessel contains an I
i b
inner waste container, and is filled with concrete.
l I
B i
E The outer packaging is composed of a three-inch thick cylindrical shell I
N welded to a four-inch thick bottom plate, and is constructed of A516, Gr.
I B
70 carbon steel.
The four-inch thick top plate is attached to the i
B reactor vessel flange by the existing reactor head studs, and is welded L
B to the packaging outer shell.
Caps are welded over the head studs. The E
B region between the reactor vessel and the outer packaging is filled with E
B concrete. The overall dimensions of the package are approximately 13 l
t b
feet, 2 inches outer diameter, and 28 feet, 3 inches outer length, I
B excluding the head studs and caps which extend beyond the top plate. The L
h maximum weight of the package is 656,000 pounds.
l t
B I
B (3)
Drawings I
b I
The package is constructed and assembled in accordance with the following i
B Yankee Atomic Electric Company Drawings:
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L b
YR-B-90-005, Rev. 3 I
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YR-B-90-006, Rev. 1 I
b YR-B-90-007, Rev. O L
N YR-B-90-008, Rev. 1 l I B
YR-B-90-009, Rev. O L
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NR FORM 118A CONDm0NS rumnaudi U.S. NUCLEAR REGULATORY COMMISSION r
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p Page 2 - Certificate No. 9262 - Revision No. 1 - Docket No. 71-9262 i
l b
i p
5.(b) Contents l-B I
p (1)
Type and Form of Material i
p i
p Irradiated steel reactor pressure vessel, containing radioactive i
p contamination and waste in solidified concrete, meeting the requirements i
p of low specific activity radioactive material.
l p
L 4
p (2)
Maximum Quantity of Material per Package l
1 D
I p
Greater than a Type A quantity of radioactive material contained in an r
p irradiated reactor pressure vessel and associated contamination and i
p solidified waste.
Fissile material may be present provided the fissile i
p material meets the exemption standards of 10 CFR 671.53.
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I p
6.
In addition to the requirements of Subpart G of 10 CFR Part 71:
i p
L y
(a)
The Federal Energy Regulatory Commission must specifically approve the g
y adequacy of the Sherman Dam and spillway bridge for transport of the i
g Model No. YNPS RPV package.
i B
l y
(b)
The Massachusetts Highway Department must specifically approve the g
g adequacy of the roadway, including slope stability and roadway culverts, i
from the Yankee Nuclear Power Station to the rail line, for transport of i
g the Model No. YNPS RPV package.
i l
(c)
The package must be prepared for shipment and must be transported in l
g accordance with Chapters 7 and 8 of the application.
i j
l 7.
This certificate authorizes a one-time shipment of a single package from the l
Yankee Nuclear Power Station to a disposal facility.
g i
N 8.
The package authorized by this certificate must be transported on a motor l
l vehicle and on a railroad car assigned for the sole use of the licensee.
N I
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12.
I l
10.
Expiration date: January 31, 2001.
[
b REFERENCES I
B l
B Yankee Atomic Electric Company application dated March 23, 1995.
L p
I N
Supplements dated: March 31, August 30, and December 15, 1995; November 14, 1996; and I
b January 15, 1997.
I b
I B
FOR THE U.S. NUCLEAR REGULATORY COMMISSION I
D I
i
& T tL; p l
D Cass R. Chappell, Chief I
B Package Certification Section I
D Spent Fuel Project Office I
B Office of Nuclear Material Safety I
B and Safeguards I
B Date 01 I
- m m m m m m m/30/97mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm
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t UNITED STATES y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20006-4001 s*****/
APPROVAL RECORD Model No. YNPS RPV Package Certificate of Compliance No. 9262 Revision No. 1 l
By application dated November 14, 1996, as supplemented January 15, 1997, i
Yankee Atomic Electric Company requested an amendment to Certificate of Compliance No. 9262, for the Model No. YNPS RPV package. The request was to modify the density of the concrete used to fill the reactor pressure vessel and the region between the reactor pressure vessel and the outer packaging.
The modification was primarily due to weight restrictions for the rail transport of the package.
The package design originally specified a low density concrete (25-30 pcf) within the reactor vessel, and a normal density concrete (140-150 pcf) in the region between the reactor vessel and the outer packaging.
The applicant provided a revised drawing of the package that shows the concrete densities that were actually achieved in preparing the reactor vessel package. The concrete density ranged from 25.7 to 74.2 pcf within the reactor vessel, and the average concrete density was 41.3 pcf in the region between the reactor vessel and the outer packaging. The maximum package weight was revised from 363.5 tons to 328 tons.
The applicant provided revised structural analyses, thermal analyses, and radiation analyses to show that the changes in concrete density would not affect the performance of the package.
Since the structural analyses considered the weight of the concrete, but did not take structural credit for the concrete strength, the reduction in the concrete density did not affect the structural performance of the package. The applicant recalculated the package temperatures under the normal condition heat test using the revised l
thermal conductivity of the concrete.
The temperatures were acceptable.
The applicant revised the radiation analyses to consider the reduced shielding effects of the lower concrete density.
In addition, the applicant reported that the radiation measurements on the outside of the package as prepared for transport which were within the limits specified in 10 CFR 971.47.
The package was approved for transport of low specific activity radioactive material under the provisions of 10 CFR Part 71 in effect at the time of the original application. Authorization for continued use of the package is subject to the provisions of 10 CFR 571.52.
The change in concrete densities does not affect the ability of the package to meet the requirements of 10 CFR Part 71.
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date 01/30/97