ML19344E832
| ML19344E832 | |
| Person / Time | |
|---|---|
| Site: | 07109009 |
| Issue date: | 09/03/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19344E828 | List: |
| References | |
| NUDOCS 8009110759 | |
| Download: ML19344E832 (8) | |
Text
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Form NRC418 U.S. NUCt. EAR REGULATORY CoMMISSloN U2 73 3nc,,3, CERTIFICATE OF COMPT. LANCE 7
For Radioactive Materials Pacmages 1.lal g icate Numeer 1.{b) R n No.
1, fi n No.
1,[d) P No. 1.(e) Total Ng. Pages
- 2. PREAM8LE 2.lal This certificate is issued to satisfy Sections 173.093a.173.394.173.*:95, and 173.396 of the oeoertment of Transoortstion Hazardous Mater als Requaatsons (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-104 and 146-19-100 of the Ceoartment of Transoortation oangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging end contents desenbed in item 5 below, meets the safety standaros set forth in Suboort C of Titte to. Cade of Federal Regulatens. Part 71. **Packageng of Radioactive Materiais for Transoort and Trartsportation of Radioactive Matenal Under Certaitt Conditions.*
2.fc)
This certificate does not ectieve the consmanor from comosiance witn any roouirernent of the requiatens of tee U.S. oeoarernent of Transoortation or otner acosicacio regulatory.agen:aes. incaucing the government of any country enrougn or into wnicri the pacxage wdl be transoorted.
- 3. This certificate is issuaa on the cases of a safety anaevsis reoort of the package design or anosication-3.lal Prepared by (Name and address):
3.Ibi Tide and identification of reoort or anotication:
General Electric Company General Electric Company application dated P.O. Box 780 March 12, 1973, as supplemented.
Wilmington, NC 28401 3.fci oocket No. 71-9009
- 4. CCNolTIONS This certificate is conditenal uoon tee fulfilling of the roouirements of Sueoart o of '10 CF81 J1. as aoolicacle, and the concitions soecified in item 5 below.
- 5. coscriotion of Packaging and Autnorizac Contents. Moces Nurnoer. Fissaie C: ass, other Concitions. and
References:
(a) Packaging (1) Model No.:
FL 10-1 (2) Description Two, 16 gage 55 gallon drums welded end to end, approximately 68 inches long and 22-1/2 inches in diameter.
The outer drum closure shall be accomplished by at least a 12 gage bolt-locking ring with drop-forged lugs, one of which is threaded to receive at least 5/8-inch diameter bolt and lock nut.
The pressure vessel support mechanism consists of wood supports, steel inner sleeve and nut ring to receive the containment vessel, and fire resistant phenolic foam, formed in place to an average finished density of at least 8 pounds per cubic foot for the main body and 10 pounds per cubic foot for the cap.
Gas relief holes shall be provided in the outer steel drum.
The containment vessel is a 304L stainless steel 5.-inch Schedule 40 pipe, approximately 53-1/2 inches long, with a 304L stainless steel 1/2-inch thick welded bottom plate and a 304L stainless steel 300 pound slipon flange and blind flange which is fastened by eight, 3/4-inch steel bolts.
The flange closure is gasketed by two flourcelastomer 0-rings with a pressure tap between the two 0-rings grooves.
During shipment, the 0 ring groove pressure tap is sealed with a pipe plug with threads wrapped in teflon tape.
A 1/4-inch stainless steel valve is screwed into the hiind 80001076p.~-.-.-.-
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1
Pag 3 2 - Certificate No. 9009 - Revision No. 9 - Docket No. 71-9009 5.
(a) (2) Description (continued) flange of the containment vessel.
The valve is sealed by a pipe cap (threads wrapped with teflon tape) and is protected by a 2-1/2-inch high section 5-inch Schedule 40 pipe welded to the top of the flange.
The packaging has a maximum gross weight of 515 lbs.
(3) Drawings The Model No. FL 10-1 package is described by International Nuclear Company (INCO) Drawing No. 050-479-0, Rev. C, and the containment vessel described by INCO Drawing No. 050-480-0, Rev. C.
The containment vessel seal is described by INCO Drawing No. OED-169-8, Rev. 2.
(b) Contents (1) Type and form of material (i) Uranyl nitrate solutions having a concentration of uranium 235 and uranium 233 not exceeding 350 grams per liter and an H/U-235 atomic ratio not less than 80, provided that the U-233 and plutonium content is not more than 1% of the U-235 content; or (ii) Uranyl nitrate solutions having a combined. concentration of uranium 233 and uranium 235 not exceeding 250 grams per liter and an H to fissile material atomic ratio not less than 80 provided (1) the U-233 content is not greater than 20% of the combined U-233 and U-235 content, and (2) the plutonium content is not more than 1% of the combined U-233 or U-235 content; or (iii) Plutonium nitrate solutions having a concentration not exceeding 250 grams fissile plutonium per liter; or (iv)
Uranyl sulfate solution (UO SO ) containing uranium-235; or 2 4 (v) Ory compounds and mixtures of fissile plutonium-uranium-235; or (vi) Mixed U-Pu oxide interspersed with graphite or silicon carbide plus plastic packing material.
(2) Maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor elements; or must be in accordance with Item 9 below; and:
(i) For the contents described in 5(b)(1)(1), (ii), and (iii):
Maximum decay heat load not to exceed 21 watts, and 10.5 liters of solution.
-a F
Page 3 - Certificate No. 9009 - Revision No. 9 - Docket No. 71-9009 5.(b) Contents (continued)
(ii)
For the contents described in 5(b)(1)(iv):
Maximum decay heat load not to exceed 18 watts and 950 grams fissile material.
(iii) For the contents described in 5(b)(1)(v):
Maximum decay heat load not to exceed 30 watts, and 4.5 kilograms fissile material.
(iv) For the contents described in 5(b)(1)(vi):
Maximum decay heat load not to exceed 10 watts and 300 grams fissile material.
(c) Fissile Class I
6.
The solution contents of the package shall be contained with a bottle having one of the following specifications:
(1) Slit vent polyethylene bottle per Drawing No. CAPE-1170-37, (ii) Duo-vent polyethylene bottle per Nuclear Fuel Services, Inc., Specification U-1 and Drawing No. 5B-U-740, or (iii) Stainless steel bottle as shown on General Electric Company Drawing Nos. FRO-140 and FR0-140A.
7.
The polyethylene bottles may be packaged within the metal inner container described by Chester-Jensen Company, Inc., Drawing Nos.1092M-1,1093M-1,1095M-1 and 1096M-1, Issue 1, dated April 26, 1971.
8.
The packaging for the polyethylene bottles shall include a flexibile restraining device (such as recommended in ARH-1819 " Vibration Testing of L-3 and L-10 Shipping Containers") placed between the e m assembly of the polyethylene bottle and the closure flange of the pressure vessel to assure that the polyethylene bottle will vibrate at the same frequency as the pressure vessel during transport.
9.
Dry compounds and mixtures which shall be packaged within sealed metal cans or DOT Specification 2R containers (49 CFR 6178.34); and placed within an inner container constructed and leak tested as specified on General Electric Illustration AFL 1105.
Following the gas leak testing specified on the Illustration, all inner container welds shall be leak tested using a liquid penetrant method in accordance with Article 6,Section V, ASME Code.
Alternatively, the inner container shown in the Illustration may be constructed of 300 series' stainless steel pipe with an outside diameter of 4.500 + 0.031 inches with a wall thickness ranging between 0.095 and 0.140 inch.
- 10. Appropriate steps shall be taken to assure that frcm the time of sealing to the time l
of delivery to the consignee, the pressure in the containment vessel will not exceed l
40 psig.
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o Page 4 - Certificate No. 9009 - Revision No. 9 - Docket No. 71-9009 11.
Prior to each shipment of more than Type A quantities of radioactive material, the space between'the double 0-ring seal shall be tested at 100 psig and leak detection performed by a method capable of detecting a leak greater than 10 3 atm cc/sec at standard temperature and pressure.
No package with a detectable leak shall be delivered to a carrier for transport.
12.
In addition to the requirements of Subpart D of 10 CFR 71, a test shall be performed on each containment vessel and associated 1/4-inch SS valve (without its associated pipe cap) initially and once each year at 300 psig and the leak detection performed by a method capable of detecting a leak greater than 10 8 atm cc/sec at standard temperature and pressure. Any chamber that fails to pass the test shall be withdrawn from service and repaired to meet the test.
For shipment of the contents of not more than a Type A quantity of radioactive material, this test shall not be required.
13.
The fire resistant phenolic foam shall be in accordance with AEC Materials and Equipment Specification SP-9 or as modified by ORGDP Reports K/TL-729 and K/P-65675.
14.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12(b).
15.
Expiration date: August 31, 1983.
REFERENCES General Electric Company application dated March 12, 1973.
Supplements dated:
April 13,1973; March 21,1974; April 16,1979; and August 27, 1980.
l Westinghouse Electric Corporation supplements dated: October 3, 1979; and March 11, 1980.
Babcock and Wilcox Company supplement dated: May 14, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION 8 %c ~rD Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
SEP 0 31900 e,
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CVf GENER AL h ELECTRIC m,etel~mem PRODUCTS DIVISION mousseeavam esansueAcmnia c,3 i a w a a = =c. - e. os mox :ea, euno.c rcm. A c. anet. mim = =aaa essaamana August 27, 1980 Director Orrico of Nuclear Material Safety & Safeguarda U.
S. reuclw.ar hgulatory Coasr.isalon W ar. l o.J ton, D. C.
20555 A t t en t ia n a Mr. C.
E. L cDonald, Chief
- rranspor tation Certification Branch Dear S124 auference:
Application Amendment T-18 for bintC Certificate nf Coaspliance USV9009/1OF Wi th ref ere;.ce to the subject certificate for the FL 10-1 container sactson 12 of that cert.ificate requires that leak tests shall be E
- 3. o 2 r u r mo.2 c.si c;.a c34 containment yuas c u l t uwu.g.
vessel initially and then once emeh wo rea l t ev w t h.a t for the uranyl nitrate solution (gado11nia-bearing) rur W.ict we use tr.= FL 10-1 to ship this liquid to an offsite for u ra n ium _r ecovery, these v e r.acu-u := u ry.
yearly leak tests should not be g..
Typical 2 2 cronium concentratior. in these solutions is less than n o f c.n44.
per liter oud the U-235 concentration less than 15 grams
+
por l i s. n r.
rise re ra re, w are requesting that the inner containers of the FL 10-L f
- p. d.. v u us ror our wu shipments of uranyl nitrate solutions meeting the ew t=nt c=quirements specified above, be exeunpted fross the
..uau 1 1.4L t=St r+1rosnent of Section 12 of that certif Acate.
A t t a cL e-d f or your r ef erence is a copy of the proposed changes to 2.
.wac t s.;n E and 12 of the ccetificate.
Puracant to 10 C1'M L70.31, a General Electric Company check for 4130
!= attached for processing this exesaption request.
Yosar 1 r e.aspt cous ider.ation of this request wuld be appreciated.
Very truly yours, b
GENERAL ELICTRIC COMPANY 4
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GEk[E AL Q ELECTRIC Diructor O.caMSS
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Augunt 27 1960
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ATTACBMENT
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t Tw rev2= ions ar= proposed. 4a shown on tbs followi Lo Nht' low -:4acantration,6:grtificate of Ccampliance USA /9009/B()F
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ng tuc,yages, of to allow mipament tup to a anaximum of 44 maric5 uranyl nitrate solutions with low-enriched ur aim ment la U-235) pe k., u without r quiring an annual leak test for the imanein FL 10-1 co s t.a in ct.
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O A M = n=w sec t. ion 5 (b) (1) (vii) as foliows:
uranyl ultrate solutions having a concentration of uraninsa sa t.
excuuding 350 grams per litar and not exceeding 44 una terwant in U-23 5. "
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mor.tence to section 12 as follows:
' t'o r shipt.en t of the cent.nts spec 3 fled in 5(b) (1) (vil),
teat.s.41 A rot be required,"
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PROPOW D HEVISit#t ep 2 - Certificate Ho. 9009 - Revision No. g - Docher No. 71-9009
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Description (continued)
Ll (enrads wrapped with teflon tape) and is protected by a 2-1/2-inct. hit. - ;;;.
ser. tion 5-incn scnedule 40 pipe welded to the top of the flange.
The ',,
p.ckaging ha s.t axiamma gross weignt of 515 lbs.
tj; (3)
Drawings yi!
N Model ha. ft 10-1 package is described by International hclear
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( -of (INco) Drawing ho. 05D-479-0. Rev. C, and the containment M
,.u=1 described by INCO Drawing Mo. 0$0-480-D. Sev. C.
The cantainees, y
,enen seal is described ny IMCD Drawing No. DCD-169-4. Rev. 2.
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Contents l23
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{l) lype and form of material V
(1) uranyl of crate solutloos Aaving a concentration of uranium 235 us C uranium 233 not exceeding 350 grams per litar and an H/U-235 atos ratio not iess than 80, provided that the U-233 and plutonium con t:
is not are snan 11 of tne U-2M content; or g
(11) uranyl nicrate solutions havitig a combined concentration of <srael m.
233 and uraniw 235 not exceeding 250 grams per liter and an H to fissile ute-tal atcc.ic ratio not less tun 80 provided (1) the U concent is n 2c greater than 20% of tne combined 0-233 and U-235 content, and (2) ene plutontw content is not more than 11 of the comined U-233 or U,-235 content; or
?
(111)
Plutonium nitrate solutions having a concentration not exceeding 250 grams fissile plutonium per liter; or
[.
(w) uranyl sulfate solution (UG 50.,) containing uranium-235; or 2
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Dry compounds and mixtures of fissile plutonium-orantime-235; or (wt) Mixed U-Pu oxide interspersed with graphite or $111can carbide p).T pi n tic paciting meteria).
,.~.. #,
- M i) uranyl nitrate soluti.ms having a concentratton of urantum not L
eeceedtag 350 grams per liter and not oceeding 4% anrichsent in U-235.
- t:
h.
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M24 tous quanti ty of material per package Pluuntum in excess of twty (2f4 curies per package must be in the or mets), cc:41 alloy, or reacter elements 1 or mast be in 4ccordance i t n 9 Le l o~ i a r.d :
(t1 for tne contents described in 5(b)(1)(1), (ii), and (iii):
- w wn decay hea t load not to exceed 21 watts, and 10.5 liters w i m s.
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PROPOSED HEVISION
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~e.-t t f f ene No. 9C09 - Revision tio.
9-Docket No. 71-9009
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5:
11.
Price to vaca snipmeitt of more than Type A quantities of radioactive material. 6 _~ l
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cr e suce tse: een ene double 0-rfag seal shall be tasted at 100 pstg and leak zi:
Jete:t ion perf ormed by a method capable of detecting a leak greater than
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10 2 s ta cc/sec at stsacard temp 4rature and pressure.
No package with a detect
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led sn,1) ne delivered to a carrier for transport.
12.,
In addi tion to the requirements of Subpart D of 10 CFR 71, a test shall be per1 un naca co..t.1w.unc vessel and associated 1/4-inch is walva (without its assocf
.;.;T Mpv up) it.it hally sno r.mce each year at 300 psig and the leak detection perft t,y atnoa cap.cle of datacting a leak greater than lo a ata ec/sec at standas
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i.e.wra ture and pressure.
Any chamtwr that fails to pass the test shall,be wit
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rne serwnce and r_epaired to meet tae test. *For skipent of contenti &ifi.e4
,l in S(L)U )(v h)_, this test shall not be required,*
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- 5..5.::'13.
Tne fire resistant pnenolic foam shall be in accordance with AEC mtarials and i
Equirent specification SP-9 or as madified by ORGDP Reports X/TL-729 and X/P-t
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14.
ine package authorized by this certificate is hereby approved for use undy in generai I(cme provis ions of 10 CFR 471.12(b),
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15.
Exptration cate:
August 31, 1983.
AEFERENCES
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.?..l"..=..ener4) Electric Cwny application dated March 12. 1973.
i Supple wncs dated:
April 13.1973; Nrch 21,1974; and April 16,19?9.
_..m.=
aestin9ncas. Electric Corporation supplements dated:
October 3.1979; and Nrch 11
.. =.
iccock and Wilcox Company supplement dated:
May 14, 1980.
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FOR TIE U.S. MUC1. EAR REGULATORY CODet1SSION 1 :.=
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Charles E. MacDonald. Chief
[J:T Transportation Certification Branch Division of Fuel Cycle and
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Ma tarial iaf ety
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hW PROPOSFD RFVISidM.'
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