ML19345F329
| ML19345F329 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 11/28/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19345F328 | List: |
| References | |
| NUDOCS 8102170226 | |
| Download: ML19345F329 (7) | |
Text
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Fcem U C-618 U.S. NUCLE AR REGULATORY COvMISSloN
" 2 73' CERTIFICATE OF COMPLIANCC g,. p y For Radioactive Materials Packeach 1.ta l Cc idicate Number 1.lb) Revision No.
1.(c) Panage identification No.
1.(d ) Pages No. 1.(e) Tota: No. Pages 6698 13 USA /6698/B( )F 1
7
- 2. P R E 4'.* B L E 2.f a s TNs ce idicate is issued te latisf y Sections 173.333a.173 394.173.395, and 173.396 of the oepartroent of Transportation Hazardous
'.'aterials Reculatecas 449 CF R 170-189 and 14 CF R 103) and Sections 146-19-10a and 146-19-100 of the occartment of Transportation can;erous Cargoes Regulations (46 CF R 146-149). as amended.
tb)
~he cacanging and contents described ir item s below. meets the safety standards set fortn in Suboart C of Title 10. Coce of Fecerai Rega:at.ons. Part 71. "Pacnaging of Racsoactive Materials for Transport and Transportation of Rad.cactive Material Under Certain Conditions."
7.(c)
This certificate does not relieve the conssonor fror9 corneliance with any recuaren'*ent of the reguir* ions of the U.S. Decertment of Transoortation or otner acobcable regulatory acencies, including the government of any country through or into which the package Wdl be transoorted.
1 ' s cert >hcate is issuea on the basis of a safety analysis report of the package cesign or apolication-2 tal Prtoarea by #!ame and address):
3 lb)
Titie and.centification of report or acotication:
Nuclear Fuel Services, Inc.
NFS application dated October 6, 1972, P.O. Ecx 124 as supplemented.
Wat Valley, NY 14171 71-6698 3.f c) oocket No.
( C e.acNS This certificate is condition-1 upon the fulfilling of the reouirements of Subpart D cf 10 CF R 71. as acolicable, and the conditions specified in item 5 below.
5.
Cescription of Packaging and Autnerizeo Contents. Mocel Numoer, Fissile Class. Other Conditions, and Ref erences.
(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 inthes long and 13.5 irches 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 inct.es, minimum 5 inches).
The lid is stainless steel frustum of cone 7.5 inches thick.
Tne lid is secured to the cavity flange by six ASTM-A320, Gra.de L43, 1-1/4 inch diameter bolts.
Th e seal is provided by two polytetrafluoroethylene 0-rings.
Four neutron shield tanks, each with surge tank and rupture disc, provide a 4-1/2 inch thick (borated) water-ethylene glycol m xture around the outer 4
shell.
Four trunnions, two located on either side of the upper or lower impact limiter, are provided.
Other cask features include two drain valves ircated in the bottom shield disc, vent valve, head closure gasket leak c7ect valve, rupture disc pressure relief valve system located in the cr/;ty flange, fuel canisters for PWR and BWR shipments, and spacers to i.ccommodate shorter fuel assemblies.
For transport the cask may be enclosed in an expanded metal cage.
8102170 W '
Page 2 - Certificate No. 6698 - Revision No. 13 - 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 ccoling time of each fuel assembly and rod shall'be 12O days; and Irradiated PWR or BWR uranium o,,ide fuel assemblies with the following (i) x maximum active dimensions and maximum compositi,ons prior to-irradiation:
j Fuel Assembly Data PWR BWR Envelope, in 8.60x8.60x150 5.44.t5.44x144 Enrichment, w/o U-235 3.6 3.0 Weight of Uranium, kg 480 197 i
l 9/U atomic ratio 5.51 (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.
f' (iv) Solid nonfissile irradiated hardware and neutroi; source components.
(v) Fuel assembly enriched in the U-235 Tsotope to not more'than_4.1 w/o, l
with active fuel dimensions not to exceed 7.8" x 121" long.
(vi) _ Byproduct and special nuclear material in the form of-irradiated
~
l uranium and plutonium oxide fuel rods.
Prior to irradiation, the i
maximum enrichment in.U-235 plus plutonium not-to exceed 4.0 w/o.
l-
.(vii) Reconstituted PWR uranium oxide fuel assemblies with:
less than the original number of fuel rods, l
6
Page 3 - Certificate No. 6698 - Revision No. 13 - 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 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)(i) above:
One (l') 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)
(ko 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
--...a
Page 4 - Certificate No. 6698 - Revision No. 13 - Docket No. 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 assen. y 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 c6vity).
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 gamma dose rate will not exceed 1,000 l
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 l
between the cask cavity and the ball passage in a closed position.
Alternatively, j
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.
F
Dece 5 - Certificate No. 6698 - Revision No. 13 - Docket No. 71-6698 11.
At periodic intervals not to exceed (3) years, the thermal performance of the c ok 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 fr?N 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 671.54(h), the licensee shall perform periodic r,aintenance 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 Comoonent Period Test / Action Eall 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 shall De no visual (pressure gauge) indications of pressure drop for the component under test during a 10-minute test period.
Othe rwi s e,
corrective action shall be taken and the test repeated until such tire as the component meets the specified test.
(Test to pressures equal to or greater than those indicated.)
1 1
J Fa;e 5 - Certificate No. 6698 - Revision No. 13 - Occket No. 71-6698 4
5 14.
(a) ine containment vessel (cavity) dimension of each cask will be measured prior to the first shipment of irradiated fuel after December 12, 1979, 4
a,d at intervals not exceeding six (6) months thereafter.
Should a cask be removed from service, the cavity will be remeasured prior to the next shiprent of irradiated fuel if the previous cavity measurements were made more than six months prior to the shipment.
(b)
Cavity neasurements will be accomplished using six (6) calibrated guages i
mounted on a six (6) armed fixture movable over the length of the cavity.
I The gauges are mounted and oriented such that " radial" measurements may be 1
rade 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 cav.ty 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.
This will result in " radial" reasu crents at 29 axial locations for a total of 174 values.
Tr.ree consecutive measurements will be' considered a cavity measurement set.
The measuring equipment will be removed from the cavity and disassembled between each mea-"rement operation to assure as well as l
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 measure-rent that are made of the cask cavity must be included when determing a I
cavity neasurement set (i.e., no measurement may be excluded from the sample).
(c) The cask will be considered as meeting dimensional requirements when the difference between the maximum diameter at any location in the vessel and tne minimum diameter at any location in the vessel is no greater than i
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 meaning of the straightness tolerance shall be as described in ANSI Y14.5, 1973, "Cinensioning and Tolerancing."
(d)
Any cask which does not meet the criteria stated in paragraph (c). above shall be withdrawn from service.
l.
(e) The cavity neasurements and data reduction to arrive at true dimensions will be car,ied out under an NRC approved Quality Assurance Program (10 CFR 971.51).
I 15.
Ship ent of an " empty" cask (containing only residual internal radoactive contamination) need not meet the requirements of Items 11 and 14 above.
i
- 16. Tre ackage authorized by this certificate is hereby approved for use under the l
ge eral license provisions of 10 CFR 571.12(b).
I
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E :' a-icn cate:
Cecember 31, 1980.
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Ra;e 7 - Certificate No. 6698 - Revision No. 13 - Docket No. 71-6698 REFERENCES Nc: lear Fuel Services, Inc. application cated October 6, 1972.
Su:plerents dated:
November 9, 1972; January 10 and 22, February 1 and 28, March 1, 14, ar.c 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 Ce:e er 24, 1975; September 13, 1976; October 20, 1977; May 25, July 18, and Se:te cer 25, 1978; June 8, July 26, and October 31, 1979; and March 3, and July 3, 19E0.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION LG d
1 r-CharlesE.MIcDonald, Chief
[ ' Transportation Certification Branch Division of Fuel Cycle and Material Safety
'0V 2 8 30 Da'e I
i 1
.