ML19330A537
| ML19330A537 | |
| Person / Time | |
|---|---|
| Site: | 07106698 |
| Issue date: | 07/14/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19330A532 | List: |
| References | |
| NUDOCS 8007280543 | |
| Download: ML19330A537 (6) | |
Text
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a 4rm NRC.618 U.s. NUCLE AR. REGULATORY CoMulsSION 1[C R 71 CERTIFICATE OF COMPLIANCE For Radioactive Materials Pacmages 1.(al Co tificate uumoer 1.(b) Revision No.
1.(c) Package icentification No.
1.(d ) Pages No. 1.(e) Total No. Pages Acop 11 UCA/ Caco /p/ TF 1
6
- 2. PR E AMB LE 2.ta)
This ce tificate is issued to satisfy sections 173.393a.173.394.173.09s. and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and sections la6-19-1oa and 146-19-100 of the Deoartment of Transportation Dangerous Cargoes Regulations f 46 C.*R 146-149), as amended.
2.(b)
The pecuaging and contents descrioed in hem s below, rneets the safety standards set forth in Subpart C of Title 10. Code of Froeral Regulations. Part 71. **Panagmg of Radeoactive Materians for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.tc)
This certir.cate does not relieve the consignor from compliance with any recuirement of the regulations of the U.s. Desa tment of Transoortation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. ""his certificate is issued on the basis of a safety analysis report of the package design or applicatior,-
3.(a)
Prepared by (Name and address #
3.(b)
Title and Zentification of reoort or application:
Nuclear Fuel Services, Inc.
NFS application dated October 6, 1972, P.O. Box 124 as supplemented.
West Valley, NY 14171 3.(c)
Docket No. 71-6698 4 CONDITloNs This certificate is conditional upon the fulfilling of the recuirements of suboart D of 10 C8R 71, as soplicaole. and tne conoitions soecified
,in item s below,
- s. Description of Pacanging and Authorized Contents, Mocei Nur9Ce' Fisssie Class, o-her Condations, anc
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 anc 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 4-1/2 inch thick (borated) water ethylene glycol mixture ar'cund the outer shell.
Four trunnions, two located On either side of the upper or lower impact limiter, are provided.
Other cask features include two crain valves located in the bottom s!.ield 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 transDort the cask may be enclosec in an expanded metal cace.
~
80 0 '7 2 805%T
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i Page 2 - Certificate No. 6698 - Revision No. 11 - 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 shall be 120 days; and (i) Irradiated PWR or EWR uranium oxide fuel ass'emblies with the following maximum active dimensions and maximum compositions prict to irradiation:
Fuel Assembly Data PWR BWR Envelope, in 8.60x8.50x150 5.44x5.44x144 Enrichment, w/o U-235 3.6 3.0 i
Weight of Uranium, kg 480 197 H/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 3
I uranium oxide fuel rods.
(iv) Solid nonfissile irradiated hardware and neutron source components.
(v) Fuel assembly erriched 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 enricnment in U-235 plus plutenium not to exceed 4.0 w/o.
-(vii)
Reconstituted PWR uranium oxide fuel assemblies with:
less than the original number of fuel rods,
.,e
-e r
..w
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Page 3 - Certificate No. 6698 - Revision No. 11 - Docket No. 71-6698 5.
(b) Contents (continued) additional fue! rods secured in guide tube thimbles, or combinations of both cases above.
Fuel assembly described above shall conform to the maximum active aimensions given in item 5(b)(1)(i).
7 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, i
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 (1) PWR fuel assemoly, or Two (2) SWR fuel assemblies; or (ii) Item 5(b)(1)(ii) above:
Four (4) fuel assemblies contained within the fuel basket shown in NFS Drawing No. 1A-T-1107, Rev. 0; or (iii) Item 5(b)(l)(iii) above:
Maximum Fissile Maximum Enrichment Mass Limit (w/o U-235)
(ko of U-235) 3 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 ca-k cavity to limit movement of contents during shipment; or
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Page 4 - Certificate No. 6698 - Revision No. 11 - 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:
Fuei 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 l
l (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 j
(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 i
S.
The cask contents shall be so limited under normal conditions of transport that 27 times +,he 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 Ccmpany,Inc.).
The ball of the valve may have a bleed hole to equalize the pressure i
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 re'quirements of Subpart D of 10 CFR Part 71, each package crior 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 lett e dated November 1, 1974.
The results of these tests shall be cocumented and retained for the life of the cask.
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Page 5 - Certificate fio. 6698 - Revision fio. 11 - Docket tio. 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 i
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.
i 13.
In lieu of the requirements of 10 CFR 971.54(h), 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 cay 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 Yalve 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 fieutron Shield Tank Rupture Disc Annually Replace Impact Limiters Annually Test for leakage "There snall ce 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.)
Page 6 - Certificate No. 6698 - Revision No. 11 - Docket No. 71-6698 14, 'At nominal intervals of six (6) months, but no longer than seven (7) months, following the first shipment of irradiated fuel under Revision No. 9 and later revisions, to Certificate of 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 'ocumented in Appendii C to NAC letter dated June 8, d
1979 shall be removed from service.
15.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR S71.12(b).
16.
Expiration date:
December 31, 1980.
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, and July 3, 1970.
FOR THE V.S. NUCLEAR REGULATORY COMMISSION f
Char es E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
JUL 14 E
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