ML19320A616
| ML19320A616 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 06/19/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19320A612 | List: |
| References | |
| NUDOCS 8007020428 | |
| Download: ML19320A616 (6) | |
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Fum NRC418 U.S. NUCLE AR REGULATORY CCMMIS$1CN u2 31 CERTIFICATE OF COMPLIANCE
,g c q 7, For Radioactive Materials Pacmages 1.lal Certificate Number 1.(b) Revision No.
1.(c) Pacsage identification No.
1.(d) Pages No. 1.(e) Total No, Pages 6698 10 USA /6698/B( )F 1
6
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.3934,173.394,173.39s. and 173.396 of the Oeoartment of Transoortation Hazarcous Materials Regulations 149 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Cangerous Caraoes Regulatens (46 CFR 146-149), as amended.
2.(b)
The neckaging and conterits described in item s below, meets the safety standaros set forth in Suboart C of Title 10 Cooe of Federal Regulations, Part 71, ** Packaging of Radioactive Materials for Transport and Transoortation of Radioactive Matenal Unoer Certain Conditions."
2.(c)
This certificate does not relieve the consignor from comoliance with any roouirement of the regulations of the U.S. Ceoartment of Transportation or other acclicable regulatory agencies, including the government of any country through or into which the package wdl be transported.
- 3. This certificate is issued on the basis of a safety analysis reoort of the package design or aoosication-3.(al Prepared by (Name and address):
3.(b)
Title and identi'ication of report or soolication:
Nuclear Fuel Services, Inc.
NFS application dated October-6,1972, P.O. Box 124 as supplemented.
West Valley, NY 14171 3.fcl Docket No. 71*bb90
- 4. CCNDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CF R 71, as applicable, and the conditions specified in iiem s beiow.
- 5. Description of Packaging and Authorized Contents, Model Number, Fisssie Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: NFS-4 (2) Description A steel, lead and water shielded shiDping cask. The cask is a right circul' r a
cylinder with upper and lower steel encased balsa impact limiters. The overall dimensions are 214 inches in length and 50 inches in diameter. The gross weight of the cask is approximately 50,000 pounds. The inner cavity is 178 inches long and 13.5 inches in diameter. The thickness of the inner shell is 5/16 inch and 1-1/4 inches for the outer shell. The two stainless steel shells are welded to a 2-inch thick stainless steel shield disc at the bottom. The annulus between the inner and outer shells is filled with lead (max. lead thickness 6-5/8 inches, minimum 5 inches).
The lid is stainless steel frustum of cone 7.5 inches thick. The lid is secured to the cavity flange by six ASTM-A320, Grade L43,1-1/4 inch diameter bolts. The seal is provided by two polytetrafluoroethylene 0-rings. Four neutron shield tanks, each with surge tank and rupture disc, provide a 4-l/2 inch thick (borated) water-ethylene glycol mixture around the outer shell. Four trunnions, two located on either side of the upper or lower impact limiter, are provided.
Other cask features include two drain valves located in the bottom shield disc, vent valve, head closure gasket leak check valve, ruptare disc-pressure relief valve system located in the cavity flange, fuel canisters for PWR and BWR shipments, and spacers to accomioda*e shcrter fuel assemblies.
For transport the cask may be enclosed in an excanded metal cage.
8007020 @
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Page 2 - Certificate No. 6698 - Revision No.10 - Docket fio. 71-6698 5.
(a) Packaging (continued)
(3) Drawings The NFS-4 shipping cask is constructed in accordance with Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, Rev.19. The fuel assemblies are positioned within the fuel canisters shown in Figure 2.1.3 of the application dated October 6,1972.
Spacers may be used to accommodate shorter fuel assemblies within the fuel canisters.
(b) Contents (1) Type and form of material The minimum cooling time of each fuel assembly and rod shall be 120 days; and (1)
Irradiated PWR or BWR uranium oxide fuel assemblies with the following maximum active dimensions and maximum compositions prior to irradiation:
Fuel Assembly Data PWR BWR Envelope, in 8.60x8.60x150 5.44x5.44x144 Enrichment, w/o U-235 3.6 3.0 Weight of Uranium, kg 480 197 5.51 H/U atomic ratio (ii) Fuel assembly enriched in the U-235 isotope to not more than 2.5 w/o, with active fuel dimensions not to exceed 4.2" x 4.2" x 110" long.
(iii) Byproduct and special nuclear material in the form of irradiated uranium oxide fuel rods.
l (iv) Solid nonfissile irradiated hardware and neutron source components.
(v) Fuel assembly enriched in the U-235 isotope to not more than 4.1 w/o, with active fuel dimensions not to exceed 7.8" x 121" long.
(vi) Byproduct and special nuclear material in the form of irradiated uranium and plutonium oxide fuel rods. Prior to irradiation, the l
maximum enrichnent in U-235 plus plutonium not to exceed 4.0 w/o.
(vii) Reconstituted PWR uranium oxide fuel assemblies with: -
less than the original number of fue
- rods,
I. o Page 3 - Certificate No. 6698 - Revision No.10 - Docket to. 71-6698 5.
(b) Contents (continued) additional fuel rods secured in guide tube thimbles, or combinations of both cases above.
Fuel assembly described above shall conform to the maximum active dimensions given in item 5(b)(1)(i).
Any fuel assembly shipped without one or both end fittings shall be equipped with an assembly carrier as shown in Battelle Drawing No. 00-001-676 or equivalent.
(viii) Irradiated BWR uranium oxide fuel assemblies.
Prior to irradiation, the maximum enrichment in the U-235 isotope shall not exceed 4.0 w/o with active fuel dimensions not to exceed 5.63" x 5.63" x 83.8" long.
(2) Maximum quantity of material per package.
Not to exceed a decay heat generation of 2.5 kw; and (i)
Item 5(b)(1) above:
One (1) PWR fuel assembly, or Two (2) BWR fuel assemblies; or (ii) Item 5(b)(1)(ii) above:
Four (4) fuel assemblies contained within the fuel basket shown in NFS Drawing No. l A-T-1107, Rev. 0; or (iii) Item 5(b)(1)(iii) above:
Maximum Fissile Maximum Enrichment Mass Limit (w/o U-235)
(kg of U-235) 3.0 2.0 4.0 1.6 5.0 1.5; or (iv) Item 5(b)(1)(iv) above:
As needed, appropriate component spacers shall be used in the cask cavity to limit movement of contents during shipment; or i
I. s Page4-CertificateNo.6698-RevisionNo.10-Dockethio. 71-6698 5.
(b) Contents (continued)
(v) Item 5(b)(1)(v) above:
One (1) fuel assembly; or (vi) Item 5(b)(1)(vi) above:
Fuel rods within the fuel canisters described in 5(a)(3).
The maximum mass of U-235 plus plutonium shall not exceed 4.0 kg. A suitable fixture may be used to secure the fuel rods within the canister; or (vii) Item 5(b)(1)(vii) above:
The maximum compositions of one PWR fuel assembly including additional rods shall conform to Item 5(b)(1); or (viii) Item 5(b)(1)(viii) above:
Two (2) BWR fuel assemblies.
Prior to irradiation, the maximum uranium content per assembly shall not exceed 122 kg.
(c) Fissile Class III Maximum number of packages per shipment One (1) 6.
The cask shall be shipped dry (no water coolant in cask cavity).
7.
The water-ethylene glycol mixture in the neutron shield tanks may contain up to 1.0 weight percent boron. This mixture shall not freeze or precipitate in a temperature range from -40*F to 330*F.
8.
The cask contents shall be so limited under normal conditions of transport that 27 times the neutron dose rate plus 1.4 times the gansna dose rate will not exceed 1,000 millirems per hour at three (3) feet from the external surface of the package.
9.
The vent and drain valves shall be 1/2" FG466TSW Miser ball valves (Worchester Valve Company,Inc.). The ball of the valve may have a bleed hole to equalize the pressure between the cask cavity and the ball passage in a closed position. Alternatively, the vent and drain lines may be sealed with pipe plugs.
10.
In addition to the requirements of Subpart D of 10 CFR Part 71, each package prior to first use shall meet the acceptance tests and criteria specified on pages A-21 thru A-34 of the Nuclear Fuel Services, Inc. application dated October 6,1972, as amended, March 1,1973 and Nuclear Assurance Corporation letter dated November 1,1974. The results of these tests shall be documented and retained for the life of the cask.
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I.o Page 5 - Certificate No. 6698 - Revision No.10 - Docket No. 71-6698
- 11. At periodic intervals not to exceed (3) years, the thermal performance of the cask shall be analyzed to verify that the cask operation has not degraded below that which is licensed. Following the initial acceptance tests, the heat source may be that provided by the decay heat from the contents of the package provided that the heat source is equal to at least 25% of the design heat load for the package.
Each cask that fails to meet the thermal acceptance criteria given on pages A-21(a) and A-21(b) using the TAP computer program, or equivalent, shall be withdrawn from service until corrective action can be completed.
- 12. The rupture discs for the neutron shield tanks shall be type "B" or "DV" (BS&B Safety Systems, Inc.) or equivalent.
13.
In lieu of the requirements of 10 CFR 571.54(M, the licensee shall perform periodic maintenance and testing of 0-rings, drain and vent ball valves, relief valves, and rupture discs of the cask as indicated in the table given below. During inactive periods, the maintenance and testing frequency may be disregarded provided that the package is brought into full compliance prior to the next use of, the package.
Cask Component Period Test / Action Ball Valve Each thipment Hydro test to 80 psig*
Ball Valve Annually Replace seats and seals 0-rings Each shipment Test to 80 psig*
0-rings Quarterly Test to 167 psig*
0-rings Annually Test to 1006 psig*
Inner Containment Vessel Quarterly Test to 250 psig*
Cavity Relief Valve Annually Test at set point Cavity Rupture Disc Annually Replace Neutron Shi~ld Tank e
Rupture Disc Annually Replace Impact Limiters Annually Test for leakage
- There shall be no visual (pressure gauge) indications of pressure drop for the component under test during a 10-minute test period. Otherwise, corrective action shall be taken and the test repeated until such time as the component meets the specified test.
(Test to pressures equal to or greater than those indicated.)
4 Page 6 - Certificate No. 6698 - Revision No. 10 - Docket tio. 71-6698
- 14. At least every six (6) months, commencing six months following the first shipment of irradiated fuel under Revision No. 9 and later revisions, to Certificate of l
Compliance No. 6698, the licensee shall perform physical measurements of the cask inner shell. Any cask whose inner container dimensions are measured to deviate by more than _+0.015 inch at comparable points from the dimensions documented in Appendix C to NAC letter dated June 8,1979 shall be removed from service.
- 15. The package authorized by this certificate is hereby approved for use under the jeneral license provisions of 10 CFR 571.12(b).
16.
Expiration date: December 31, 1980.
REFERENCES Nuclear Fuel Services, Inc. application dated October 6,1972.
Supplements dated: Novemt'er 9,1972; January 10 and 22, February 1 and 28, March 1,14, and 21, May 4, June 4, and July 26,1973; July 17,1974; May 4,1976; and November 9, 1977.
Nuclear Assurance Corporation supplements dated: November 1,1974; August 13 and December 24, 25,1978; June 8,l 1975; September 13, 1976; October 20,1977; May 25, July 18, and September July 26, and October 31,1979; March 3,1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION h
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
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