ML20041A335
| ML20041A335 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 01/25/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20041A331 | List: |
| References | |
| NUDOCS 8202190446 | |
| Download: ML20041A335 (8) | |
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3 Forn NRC418 U.S. NUCLEAR REGULATORY CoMMISSloN
[CFRM CERTIFICATE OF COMPLIANCE 8
For Radioactive Materials Packages 1.fa) C t f ts Number 1.(b) ision No.
1.(c) Pac I
a 1.(d) Pages No. 1.(e) otal No. Pages
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.333a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous
. Materials Regulations (49 CFR 170-189 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, meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations, 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 Transportation 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)
Titte and identification of report or application:
Nuclear Fuel Services, Inc.
f1FS application dated October 6,1972, P.O. Box 124 as supplemented.
West Valley, fly 14171 3.(c)
Docket No.
7].6698
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: NFS-4 (2) Description A steel, lead and water shielded shipping cask.
The cask is a right circular 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 i
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 l
4-1/2 inch thick (borated) water-ethylene glycol mixture around the outer shell.
Four trunnions, two located on either side of the upper or lower l
impact limiter, are provided.
Other cask #eatures include two drain valves locateo in the bottom shield disc, vent valve, head closure gasket leak check valve, rupture disc-pressure relief valve system located in the cavity flange, fuel canisters for PWR and BWR shipments, and spacers to accommodate shorter fuel assemblies.
For transport the cask may be enclosed in an expanded metal cage.
8202190446 820125 PDR ADOCK 07106698 C
PDR.
Page 2 - Certificate No. 6698 - Revision No.15 - Docket No. 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 must be 120 days; and (i)
Irradiated FWR or BWR uranium o,.ide 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.
(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 maximum enrichment 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 fuel rods,
a..
Page 3 - Certificate No. 6698 - Revision No. 15 - Docket No. 71-6698 5.
(b) Contents (continued) additional fuel rods secured in guide tube thimbles, or combinations of both cases above.
Fuel assembly described above must conform to the maximum active dimensions given in item 5(b)(1)(1).
Any fuel assembly shipped without one or both end fittings must 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 must.ot exceed 4.0 w/o with active fuel dimensions not to exceed 5.63" x 5.63" x 83.8" long.
r (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. lA-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 j
5.0 1.5; or (iv) Item 5(b)(1)(iv) above:
As needed, appropriate component spacers must be used in the cask cavity to limit movement of contents during shipment; or
- +, - -
...,..._-n
Page 4 - Certificate No. 6698 - Revision No.15 - Docket No. 71-6698 5.
(b) Contents (continued)
(v) Item 5(b)(1)(v) above:
0 One (1) fuel assembly; or m
(vi) Item 5(b)(1)(vi) above:
vii Fuel rods within the fuel canist'ers described in 5(a)(3). The maximum mass of U-235 plus pluttinium must not exceed 4.0 kg.
A suitable fixture may be used tonsecure the fuel rods within the canister; or (vii) Item 5(b)(1)(vii) above:
tii The maximum compositions of onemPWR fuel assembly including additional rods must conform tolsItem 5(b)(1); or (viii) Item 5(b)(1)(viii) above:
rii Two (2) BWR fuel assemblies.
Prefor to irradiation, the maximum uranium content per assembly must not exceed 122 kg.
i j
(c) Fissile Class III Maximum number of packages per shipment: ges One (1) l 6.
The cask cavity must be dry (no free water) wKen: delivered to a carrier for transport. If the package is loaded or unloadedhunder water or water is introduced into the cavity, residual moisture must be reniaved from the cask cavity by 0
positioning the cask vertical and with both driain lines open.
Air pressure must I
be applied through the open vent line in such emanner to insure no liquid
' r l
remains in the cask cavity and drain lines.
Alternatively, the cavity must be evacuated until pressure falls below 1" of Hg 1(<0.5 psi) at 80*F and remains there for 15 minutes. Valve off the vacuum linCand remove vacuum source.
Cavity must maintain a vacuum of at least 1" of dig for an additional 15 minutes before returning to atmospheric pressure.
ic 7.
Except for fuel with minor cladding deflects s'uch as pin holes and hairline cracks, failed fuel assemblies and fuel rods must be delivered to a carrier for transport within an inert atmosphere (at atmospheric pressure) in the cask cavity. Drying of the cavity must be accomplished by the alternate procedure (vacuum drying) described in Item 6 above. Faired fuel assemblies (pellets) which are oxidized are not authorized.
- tb 8.
The water-ethylene glycol mixture in the neutro'n shield tanks may contain up to 1.0 weight percent boron. This mixture must ndt freeze or precipitate in a temperature range from -40*F to 330 F.
to 9.
The cask contents must be so limited under norniail conditions of transport that l
27 times the neutron dose rate plus 1.4 times the gamma dose rate will not exceed 1,000 millirems per hour at three (3) feet from the external surface of l
the package.
I
4 Page 5 - Certificate No. 6698 - Revision No.15 - Docket No. 71-6698
- 10. The vent and drain valves must be 1/2" FG 466TSW 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.
11.
In addition to the requirements of Subpart D of 10 CFR Part 71, each package prior to first use must 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 must be documented and retained for the life of the cask.
- 12. At periodic intervals not to exceed (3) years, the thermal performance of the cask 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, must be withdrawn from service until corrective action can be completed.
- 13. The rupture discs for the neutron shield tanks must be type "B" or "DV" (BS&B Safety Systems, Inc.) or equivalent.
14.
In lieu of the requirements of 10 CFR 571.54(h), the licensee must 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 shipment 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 Shield Tank Rupture Disc Annually Replace Impact Limiters Annually Test for leakage
- There must be no visual (pressure gauge) indications of pressure drop for the component under test during a 10-minute test period. Othenvise, corrective action must be taken and the test repeated until such time as the component meets the specified test.
(Test to pressures equal to orgreaterthanthoseindicated.)
Page 6 - Certificate No. 6698 - Revision No.15 - Docket No. 71-6698 15.
(a) The containment vessel (cavity) dimension of each cask will be measured prior to the first shipment of irradiated fuel after December 12, 1979, and at intervals not exceeding twelve (12) months thereafter. Should a cask be removed from l
service, the cavity will be remeasured prior to the next shipment of irradiated fuel if the previous cavity measurements were made more than twelve (12) months l
prior to the shipment.
(b) Cavity measurements will be accomplished using six (6) calibrated guages mounted on a six (6) armed fixture movable over the length of the cavity. The gauges are mounted and oriented such that " radial" measurements may be made at 30,
90,150, 210, 270, and 330 from a 0 point, which is the center of the center valve port. The measurements may then be converted to diameters at azimuthal locations of 30 -210, 90 -270, and 150 -330. Axial locations for cavity measurements to be recorded will be nominal 4! and 12! inches from the top of the cavity and at nominal 6-inch intervals thereafter over the length of the cavity except that the axial interval between the two measurements at the bottom of the cavity shall be approximately 3 inches apart. This will result in
" radial" measurements at 29 axial locations for a total of 174 values.
Three consecutive measurements will be considered a cavity measurement set. The measuring equipment will be removed from the cavity and disassembled between each measurement operation to assure as well as possible that measuring equipment and set up variance are incorporated in the results.
The true cavity dimensions will be considered the average values from one or two consecutive cavity measurement sets. All measurement that are made of the cask cavity must be included when determing a cavity measurement set (i.e., no measurement may be excluded from thesample).
(c) The cask will be considered as meeting dimensional requirements when the difference between the maximum diameter at any location in the vessel and the minimum diameter at any location in the vessel is no greater than 0.270 inches and the straightness of the inner surface along the axis at azimuthal locations of 30",
90, 150, 210 270, and 330 is within the tolerance specified in Drawing No.
E10080 Sheet 1, Rev.19. The neaning of the straightness tolerance shall be as described in ANSI Y14.5,1973, "Dimensioning and Tolerancing."
(d) Any cask which does not meet the criteria stated in paragraph (c) above must be withdrawn from service.
(e)
The cavity measurements and data reduction to arrive at true dimensions will be carried out under an NRC approved Quality Assurance Program (10 CFR 571.51).
- 16. Shipment of an " empty" cask (containing only residual internal radioactive contamination) need not meet the rec.uirements of Items 12 and 15 above.
Page 7 - Certificate No. 6698 - Revision No.15 - Docket flo. 71-6698
- 17. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 18. Expiration date:
December 31, 1982.
REFERENCES Nuclear Fuel Services, Inc. application dated October 6,1972.
Supplements dated: November 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, 1975; September 13, 1976; October 20, 1977; May 25, July 18, and September 25, 1978; June 8, July 26, and October 31,.1979; and March 3, July 3, 1980 and December 1, 1980.
FOR THE U.S. NUCLEAR REGULATORY C0: MISSION Charles E. MacDonald, Chief Transportation Cartification Branch Division of Fuel Cycle and Material Safety JAN 2 51932 Date:
i e
.,,,,n
O U.S. Nuclear Regulatory Comission Transportation Certification Branch Approval Record Model No. NFS-4 Docket No. 71-6698 By application dated October 27, 1980,' Nuclear Assurance Corporation requested renewal of Certification of Compliance No. 6698 for the Model No. NFS-4 packaging.
Since December 12, 1979 three casks which meet the design approved by the Comission have been authorized with certain restrictions placed on their use.
Certificate of Compliance No. 6698 has been under timely renewal in accordance with 10 CFR 52.109 since December 31, 1980.
Certificate of Compliance No. 6698 has been renewed until December 31, 1982.
This will provide tine to resolve the issues raised in our letter of December 29, 1981 and for a consolidation application to be submitted at least 30 days prior to the expiration date of the Certificate.
Issues include resolution of the effect of deviations for casks not constructed to the design approved by the Comission. These casks are not authorized for use.
Conditions to the certificate have been modified or added to take into account recent operating experience. These include a condition to assure that the cask is properly drained and prepared for shipment in the dry state.
In addition, vacuum drying and inert atmosphere is required for shipment of failed fuel, shipment of oxidized fuel is not authorized. The use of a pipe plug in the drain line has been deleted. These conditions are to assure that 1
the package has been properly drained and that possible oxidation of fuel during shipment is minimized. Also, the cavity inspection frequency has been extended from 6 months to one ycar since no adverse changes to the cavity have been detected for the packages in use.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JAN 2 5199~9 Date:
.