ML19340C664
| ML19340C664 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 12/02/1980 |
| From: | Mcdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19340C663 | List: |
| References | |
| NUDOCS 8012170178 | |
| Download: ML19340C664 (7) | |
Text
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- . :0 413 U.S. NUCLE AR AEoVLAToRY COMMISSICN h
CERTIFICATE OF COMPLIANCE For Aaoioactive Yaterials Packages 1.t a l 0,,..e;cate Numoer 1.:b) Aevision No.
1.t c) Pacuage loentification No -
1.fd ) Pages No. 1.te) Total No. Pages 6693 14 USA /6698/B( )F 1
7
- 2. 8::A'.t S L E 2.!a s Ths cc tmcate is sswoo to satisfy Sections 173.092a.173.094,173.395, ano 173.396 of the Ceoartment of Transoortation Mazardous o quiations (49 CF A 170-189 ano 14 CF A 103) and Sections 146-19-10a ano 146-19-100 of the Ceoartment of Vat eris ts e
Trsntoortation Oange ous Cargoes Regulations (46 CF A 146-149). as amenoso.
"' e 34Cha?inQ and Contents oescrioed in item $ beiOw. meets the safety stancaros set forth an $wooart C of Title 10. Coce of 21:3 8scerai :Waticns. Part 71, "Pacuaging of Racioactive Vateriais for Transport ano Transoortation of Aaoicacttwe Material Unoer Cetain Ocncitions."
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~5s certifict <. :es not reiieve the ccesignor from ccmchance with any recuirement of the requiations of the U.S. Oeoartment of Transoortatsch r oton a poncante regulatory agencaes..ncluomg the government of any country througn or mto wnsen the package asil be transooreo.
- 2. 'is ce-fifiere s isssec on tne basis at a saferv anarvsis reoort of tee package oesign or aco6 cation-0..a s 3-(
3.ib n Titte end.icentification of report or acclication:
%.c'. ea r Fue'.enarea ov, Name ale adoress):
f4FS application catea Octooer 6,1972,
- ern ces,
nc.
F.O. E0x 12a as supplemented.
West Valley. NY 14171 71-6698 3.tc) occuet No.
CON tTICNS 4
This cartshcate is conoitional woon the fulfillie.g of the recuirements of Suboart o of to CF A 71. as as.F=~'s, and the concitions specified in sem 5 seiow.
- 5. Oesc r:tien et.3acuaang ano Autnorireo Contents. Mocol Numoer, Fissile Class. other Concitions. and References.
(a) ?ackaging (i) Model No.:
NFS-4 (2) Description A steel, leaa c.nd 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 snell 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 ASTn-A320, Grade La3,1-1/4 inch diameter colts.
The seal is provided by two polytetrafluoroethylene 0-rings.
Four neutron shield tanks, each wi'.h surge tank and rupture disc, provide a.
4-1/2 inch thick (bo. rated) water-ethylene glycol mixture around the outer snell.
Fcur trunniens, two located on either side of the upper or lower
' ;ict ' Nter, are provided.
Other cask features include two drain valves
- ::itec in tne bottom snield Cisc. vent valve. nead closure gasket leak
- ,ec e calve, rupture cisc pressure relief.'alve system located in the
- s.'ty C ar'ge, #uel canistees for F.iR and BWR shipments, and spacers to 3::r ;ccate horter fuel assemblies.
For transport the cask may be enclosec 3-e c an.ad T.etal cage.
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i Page 2 - Certificate No. 6698 - Revision No. la - DocAet No. 71-6698 5.
(a) Packaging (continued) 4 (3) Drawings The NFS-4 shipping cask is constructed in accordance with Nuclear Fuel Services, Inc., Orawing No. E 10080, Sheets I 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 J
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 (i)
Irraciated PWR or SWR uranium oxide fuel assemblies with the following maximum active dimensions anc maximum compositions pr'ar to irradiation:
Fuel Assembly Data PWR BWR Envelope, in 8.60x8.60x150 5.44x5.44x144 Enrichment, w/o U-235 3.6 3.0 i
Weight of Uranium, kg 480 197 i
H/U atomic ratio 5.51 i-(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, l
l (v) Fuel assemoly enriched in the U-235 isotope to not more than 4.1 w/0, with active fuel dimensions not to exceed 7.8" x 121" long.
i l
(vi) typroduct and special nucletr naterial in the form of irradiated l
canium and plutonium oxide fuel rods.
Prior to irradiation, the l
maximum enrichment in U-235 plus plutonium not to exceed 4.0 w/o.
j (vii) Reconstituted PWR uranium oxide fuel assemolii.s with:
l less than the original number of fuel rods, l
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?s;e 3 - Certificate No. 6698 - Revision No. 14 - Docket No. 71-6698 t
i 5.
(b) Contents (continued) additional fuel rods secured guide tube thimoles, 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 SWR 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 dimer.sions 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 (1) PWR fuel assembly, or l
Two (2) BWR fuel assemblies; or-4 l
(ii) Item 5(b)(1)(ii) above:
1 Four (4) fuel assemblies contained within the fuel basket shown in NFS Drawing No. lA-T-1107, Rev. 0; or j
(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(t?(1)(iv) above:
As needed, appropriate component spacers shall be used in the cask cavity to limit movement of contents during shipment; or l _... _,...
Page 4 - Certificate No. 6698 - Revision No. 14 - Docket No. 71-6698 4
5.
(b) Contents (continued) 4 (v) Item 5(b)(1)(v) above:
One (1) fuel assembly; or (vi) Item 5(b)(1)(vi) above:
Fuel rods within toe 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 net 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 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.
Tia
.results of these tests shall be documented and retained for the life of the cack.
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Page 5 - Certificate No 6698 - Revision No. la - Docket No. 71-6698 11.
At periccic intervals not to exceed (3) years, the thermal performance of the cask snall be analyzed to verify that the cask operation has not degrNed below that which is licensec.
Following the initial acceptance tests, the heat source may be that Orovided by the decay heat from the contents of the package provided tnat the heat scurce 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 Syste s, Inc.) or equivalent.
13.
In lieu of the requirements of 10 CFR s71.5a(h), the licensee shall perform periodic maintenance and testing of 0-rings, drain and vent ball valves, relief valves, and recture ciscs of the cask as indicated in tN table given below.
During inactive
- eriods, 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 Ball Valve Each shipment Hydro test to 80 psig*
Ball Valve Annually Replace seats ar.d 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 Nhere snall De no visual (pressure gauge) indications of pressure drop for tne component under test during a 10-minute test period.
Otherwise, corrective action shall be taken and the test repeater until ruch time as the component meets the specified test.
(Test to p. essure 5 equal to or greater than those indicated.)
i Page ! - Certificate No. 6698 - Revision No. 14 - Docket No. 71-6698 14 (a) The containment vessel (cavity) dimension of each cask will be measured orior to the first shipment of irradiated fuel af ter December 12, 1979, and at intervals not exceeding six (6) montns thereaf ter, Should a cask be removed from service, the cavity will be remeasured prior to the next shipment of irradiated fuel if the previous cavity measurements were made
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more than six months prior to the shipment.
(b) Cavity measurements will be accomplished using six (6) calibrated guages 4
mcunted on a six (6) armec 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 44 4
and 12h inches from the top of the cavity and at nominal 6-inch interv;is thereafter over the length of the cavity except that the axial intervil Detween the two measurements at the bottom of the cavity shall be approxi-mately 3 inches apart.
This will result in " racial" 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 measure-ment that are made of the cask cavity must be included when determing a cavity measurement 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 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 meaning 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 shall 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 671.51).
15.
Shipment of an " empty" cask (containing only residual internal radioactive contamination) need not meet the requirements of Items 11 and 14 above.
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1 s;e 7 - Certificate No. 6698 - Revision No. 14 - Docket No. 71-6698
,15.
Tr.e package authorized by this certificate is hereby acproved for use under the l
- e e al license provisions of 10 CFR 971.12(b).
i 17.
Ex:iration date:
December 31, 1980.
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j REFERENCES i
Nuclear Fuel Services, Inc. application dated October 6, 1972.
Sup lements cated:
Novem::er 9,1972; Janusry 10 and 22, February 1 and 28, March 1, 14 a,c 21, May 4, June 4, and July 26, 1973; July 17, 1974; May 4, 1976; and Novemoer 9, 1977.
Nuclear Assuratice Corporation supplements dated:
November 1, 1974; August 13 and.
Decem:e-24, 1975; September 13, 1976; October.20, 1977; May 25, July 18, and Sec e ::er 25, 1978; June 8, July 26, and October 31, 1979; and March 3, July 3, a.c Oscercer 1, 1950.
l FOR THE U.5. NUCLEAR REGULATORY COMMISSION 1
Origi=al Signed by CEA m.Z. MADON!JZ)
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety DC 2 1980 De s
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