ML20040F909
| ML20040F909 | |
| Person / Time | |
|---|---|
| Site: | 07106003 |
| Issue date: | 09/11/1981 |
| From: | Engel W ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20040F910 | List: |
| References | |
| 20121, NUDOCS 8202100458 | |
| Download: ML20040F909 (6) | |
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2 Department of Energy A
g Washington, D.C. 20585 September 11, g] 8%*ucts D:
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20555 M-130 IRRADI ATED FUEL SHIPPING CONTAINER - REVISION TO THE CERTIFICT OF N*9 m07ey Ogkircqq COMPLIANCE TO AUTHORIZE SHIPMENT OF LWBR IRRADIATED SEED MODULES IN S E
M-130 IRRADIATED FUEL SHIPPING CONTAINER; REQUEST FOR g
N Naval Reactors requests Nuclear Regulatory Commission concurrence and a 4,4 C
to the M-130 irradiated fuel shipping container Certificate of Compliance to authorize shipment of LWBR irradiated seed modules in a modified M-130 container.
The M-130 container is currently authorized to ship various types of Naval Reactors irradiated fuel cells by Nuclear Regulatory Commission Certificate of Compliance USA /6003/BF. The enclosed analysis demonstrates that shipment of LWBR irradiated seed modules in a modified M-130 container will have safety margins under normal and accident conditions which comply with Code of Federal Regulations (10CFR71) requirements.
In support of the request for a revision to the M-130 Certificate of Compliance, Naval Reactors notes the following:
a.
The modifications made to the M-130 for LWBR irradiated seed module shipment include the removal of internal equipment not needed for this shipment (heat exchanger and backup cylinder), the elimination of various penetrations in the standard M-130 container (piping, etc.), the addition of 0-ring and gasket seals, the addition of an internal support structure, and the addition of an external energy absorber. These modifications have improved the structural integrity and containment ability of the M-130 container, b.
The maximum weight of a modified M-130 loaded with six irradiated LWBR seed modules is 214,500 pounds. This weight is less than the maximum weight currently certified for the M-130 container and contents. This confirms that structural integrity and containment of the modified M-130 container will be maintained under all specified conditions of transport when shipping LWBR irradiated seed modules as demonstrated for heavier certified contents.
c.
Compliance with specified radiation levels for all conditions of transport is controlled by holding the irradiated seed modules for a sufficient period of time prior to shipment to permit radioactivity to decay to an acceptable
- value, d.
The thermal margins for shipment of LWBR irradiated seed modules in a modified M-130 are also controlled by irradiated seed module hold times and have been determined in a manner similar to the methods used for currently certified contents.
1L 2D1 8202100458 810911 PDR ADOCK 071*****
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NRC e.
The maximum calculated reactivity of LWBR irradiated seed modules, which 23302 fuel, in a modified M-130 subjected to a hypothetical contain Th02 and U accident is equivalent to Keffective = 0.949. This reactivity value is in compliance with the requirements of the Code of Federal Regulations (10CFR71).
f.
Containment of fission products is provided by the modifications to the M-130 container (elimination of penetrations in the standard M-130 container, addition of 0-ring and gasket seals) which preclude venting during both normal and accident conditions.
Naval Reactors considers that shipment of LWBR irradiated seed modules in a modified M-130 irradiated fuel container complies with Code of Federal Regulations (10CFR71) requirements and a Safety Analysis Report for Packaging (SARP) has been prepared and is enclosed (Enclosure (1)) to support this conclusion. A separate SARP will be forwarded for LWBR irradiated blanket module shipment in an M-130 container.
Nuclear Regulatory Commission concurrence and a revision to Certificate of Compliance USA /6003/BF per Enclosure (2) is requested by September 30, 1982.
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W. P.
ngel Naval Reactors Enclosure (1): LWBR Seed Safety Analysis Report for Packaging Enclosure (2): Proposed Revision to Certificate of Compliance USA /6003/BF Copy to:
Dr. D. M. Ross, Operational and Environmental Safety, DOE (w/o Enclosures) l l
Manager, PNR0 (2) (w/o Enclosures) l General Manager, Bettis (w/o Enclosures)
Manager, LWBR Project, Bettis (w/o Enclosures) l Manager, LWBR Safety Engineering, Bettis (w/o Enclosures)
- 0. R. Rieley, Bettis (w/o Enclosures)
+ +,
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Form 'NRC418 U e. NUCLEAR REGULATORY COMMISSION 10 ChR 71 CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.(e) Certifiate Number 1.(b) Revision No.
1.(c) Package Idsr.tification No.
1.(d) Pages No. 1.(e) Total No. Pages 6003 1
USA /6003/Bf 1F 1
4 t
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Department of Transportetion Hazardous 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), as amended.
2.(b)
The packaging and contents described in item 5 below, rneets the safety standards set forth in Subpart C of Title 10, Code of Federal Rogalations, Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Trensportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or applicatsn:
U.S. Department of Energy Safety Analysis Report for M-13G shipping Division of Naval Reactors container dated December 30,1968, as Washington, D.C.
20545 supplemented.
3.tc) oocket f4o. 71-6003
4. CONDITIONS This certificate is conditional upon the fulfilling of the requirernents of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item S below.
S. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging i
l l
(1) Model No.: M-130 l
l (2) Description The M-130 shipping container is an upright cylinder 84 inches in diameter by 158 inches overall height. The container walls consist of a finned 1 inch thick outer shell (fabricated from either carbon steel, carbon steel with stainless steel clad, or solid stainless steel),10 inches of lead shielding, and a 1 inch thick inner pressure vessel (fabricated from carbon steel clad with stainless steel). The top of the container is covered with a shielded closure head which is bolted to the container and seals the pressure vessel.
An access opening with a bolted shield plug is provided in the closure head for loading and unloading spent fuel.
The pressure vessel has an inside diameter of 55 inches. The central region contains a secondary heat exchanger (not used during shipment) surrounded by a 1/2 inch thick carbon steel backup cylinder 29 inches in diameter. The annulus which remains between the backup cylinder and the pressure vessel provides a space 13 inches wide and 130 inches high for spent fuel. The spent fuel is contained in the annulus by module holders designed for the particular core to be shipped.
l l
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Page 2 - Certificate No. 6003 - Revision No.1 - Docket No. 71-6003 5.
(a) Packaging (cont'd)
(2) Description (cont'd)
The container has external penetrations to the pressure vessel for steam and water relief lines and a fill and drain line (which are capped during shipment) and a pressure sensing line which remains open to a pressure gage during shipment. The container also has penetrations which do not open to the pressure vessel
- for secondary heat exchanger lines (which are capped during shipment) and a temperature sensing line.
For LWBR spent fuel shipments the heat exchanger and associated structures have been removed, external penetrations plugged and and seal welded, and an external shield and energy absorber added during modifications.
The container is supported on its transport vehicle by an "A" frame structure. Gross weight of the loaded container without its support structure is approximately 220,000 pounds.
(3) Drawings The packaging is constructed in accordance with General Electric Drawings Nos. 247E209, Sheet 1, Rev. R; Sheet 2, Rev. K; Sheet 3 Rev. T; Sheet 4, Rev. U; Sheet 5 of 5, Rev. F and 247E228. Rev. F.
For LWBR spent fuel shipments the container has been modified in accordance with Westinghouse Electric Drawing ll76J48, Sheet 1 Rev G, Sheet 2 Rev E and an external energy absorber added in accordance with Westinghouse Electric Drawing 1525E32, Rev A.
(b) Conten ts (1) T3oe and form of material Irriadiated fuel assemblies, activated corrosion products and structural parts containing Transport Groups III materials and up to 40 gallons of residual water contaminated with Transports Groups III or IV materials. The fuel assemblies and structural parts are of the following types:
(i)
S3W/S4W fuel subassemblies of core type 2.'
(ii)
S5W fuel modules of core types 2 or 3.
(iii)
S5W corner fuel modules of core types 2 or 3.
(iv)
D1G fuel modules of core types 1 or 2.
(v)
D1G removable fuel assemblies of core types 1 or 2.
e
e Page 3 - Certificate No. 6003 - Revision No.1 - Docket No. 71-6003 5.
(b) Contents (cont'd)
(vi)
S1C/S2C fuel modules with control rods.
(vii)
S1C/S2C peripheral fuel modules.
(viii)
S3G-3/3A fuel module with or without control rods. '
(ix)
SAD cell.
(x)
S3G-3/3A irradiated thennocouples and thennocouple cases.
(xi)
LWBR seed fuel modules.
(2) Maximum quantity of material per package (1) 52 fuel assemblies as described in 5(b)(1)(1).
(ii) 12 fuel assemblies as described in 5(b)(1)(ii) or 9 'uel assemblies as described in 5(b)(1)(ii) and 4 fuel assemblies as described in 5(b)(1)(iii),
(iii) 6 fuel assemblies as described in 5(b)(1)(iv) and 4 fuel assemblies as described in 5(b)(1)(v) or 5(b)(1)(vi).
(iv) 9fuelassembliesasdescribedin5(b)(1)(vi)and 8 fuel assemblies as described in 5(b)(1)(vii).
(v) 10 fuel assemblies as described in 5(b)(1)(viii).
(vi) 9 fuel assemblies as described in 5(b)(1)(viii) and one fuel assembly as described in 5(b)(1)(1x).
(vii) 9 fuel assemblies as described in 5(b)(1)(viii) and one structure as described in 5(b)(1)(x).
(viii) 5 or 6 fuel assemblies as described in 5(b)(1)(xi).
The combined heat load within the package shall be less than 33,500 Btu /hr for all shipments with the following exceptions:
(1) Shipment of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii) and limited in 5(b)(2)(iv) shall be made in a stainless steel M-130 container and shall have a heat load not to exceed 18,960 Btu /hr per shipment.
(2) Shipment of contents specified in 5(b)(1)(viii), 5(b)(1)(ix) and5(b)(1)(x)andlimitedin5(b)(2)(v),5(b)(2)(vi)and 5(b)(2)(vii) shall have a heat load not to exceed 28,620 Btu /hr for the shipboard core and 30,000 Btu /hr for the prototype core.
o Page 4 - Certificate No. 6003 - Revision No.1 - Docket No. 71-6003 5.
(b)
Contents (co.:t'd)
(3) Shipment of contents specified in 5(b)(1)(xi) and limited in 5(b)(2)(viii) shall have a heat load not to exceed 27,600 Btu /hr and a residual water quantity not to exceed 7.5 gallons.
(c)
Fissile Class III Maximum number of packages per shipment:
one 6.
For shipments involving che contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) the M-130 package shall be inspected to verify that boron poison plates are in the module holders, 7.
For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix) or 5(b)(1)(x) the thermocouples and thermocouple cases if included or the vacant module holder shall be located in the mid-position of either cage and module holder assembly.
8.
Shipments shall be made in the dry condition.
9.
Expiration date: June 30,1983.
REFERENCES Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, 1968.
Supplements: Naval Reactor letters A#2256 dated February 24,1969 and G#1931 dated March 3,1969; General Electric Company letter 0NP-74520-526 dated April 3, 1972; Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter 0NP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6,1972; General Electric Company letters ONP-74570-635 dated October 25, 1972; ONP-74570-654 dated December 4,1972; ONP-74570-666 dated December 12, 1972; ONP-74570-682 dated January 12,1973; ONP-74570-698 dated January 31, 1973; ONP-74570-687 dated Febrdary 6, 1973; ONP-74390-65 dated March 26, 1973; "LGN-85570-854 dated September 24, 1973; DLGN-85570-901 dated January 10, 1974;
.sval Reactors letter G#4061 dated January 29, 1974; General Electric Company letters DLGN-85570-924 dated February 15,1974; DLGN-85570-923 dated March 6, 1974; DLGN-85570-969 dated May 24, 1974; Naval Reactors letter G#4991 dated November 25, 1975; General Electric Company letters ONP-74340-JTT-73 dated December 17,1975; CGN-85570-ll45 dated September 9,1976; CGN-85570-1146 dated September 10,1976; CGN-85570-ll48 dated September 14, 1976; and Bettis Atomic Power Laboratory letter WAPD-R(K)-1378 dated August 30, 1976, and WAPD-LP(CES)SE-170 dated July 1981.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Date:
Material Safety