ML20134K182
| ML20134K182 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1996 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-0383, NUREG-0383-V02-R19, NUREG-383, NUREG-383-V2-R19, NUDOCS 9611180288 | |
| Download: ML20134K182 (599) | |
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~ i NUREG-0383 i ! Volume 2 ; - Revision 19 ! i l f [ Directory of j i l Certificates 1of Compliance for LRadioactive Materials Packages i F l Certificates of Compliance ,
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i -U.S. Nuclear Regulatory Commission ) l F Office of Nuclear Material Safety and Safeguards > i i i l 4 i j 'l
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9611180288 961031 . PDR NUREG 0383 R PDR }L
AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street 'NW., Lower Level, Washington.-DC l20555-0001 2. The Superintendent of Documents, U.S. Govemment Printing Office, P. O. Box 37082, Washington, DC' 20402-9328 .
- 3. The National Technical Information Service, Springfield VA 22161-0002
. Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.
Referenced documents available for inspection and copying for a fee from the NRC Public ' Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins.- circulars, information notices, inspection and investigation notices; licensee event reportst vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence. The following documents in the NUREG series are availaole ici purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reporv, grantes reports, and NRC booklets and bro. - chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions,'and Nuclear Regulatory Commission issuances. Docements available from the National Technical Information Service include NUREG-series reports and technical reporte prepared by other Federal agencies and reports prepared by the . Atomic Energy Commis>1on, forerunner agency to the Nuclear Regulatory Commission.'- Documents available from public and special technical libraries include all open literature . Items, such as books, joumal articles, and transactions. Feders/ Register notices. Federal and State legislation, and congressional reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-forence proceedings are available for purchase from the organization sponsoring the publica-tion cited. Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mall Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001. Copies of industry codes and standards used in a substantive manner in the NRC regulatory - process are mainthined at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadway, New York, NY 10018-3308.
NUREG-0383 Volume 2 Revision 19 Directory of Certificates of Compliance for Radioactive Materials Packages Certificates of Compliance t Manuscript Completed: October 1996 Date Published: October 1996 3 i }f Spent Fuel Project Office l Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission [ Washington, DC 20555-0001 W.p~s.,,)
FOREWORD The purpose of this directory is to make available a convenient source of information on packagings approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 for approved Quality Assurance programs. The reports include a listing of all users of each package design and approved Quality Assurance programs prior to the publication date of the directory. Comments to make future revisions of this directory more useful are invited and should be directed to the Spent Fuel Project Office, U.S. Nuclear Regulatory Commission. l l 1 iii l
U.S. NUCLEAR REGULATORY COMMISSION INDEX OF CERTIFICATES BY MODEL NUMBER ! 10/01/1996 l MODEL # CERTIFICATE # l MODEL # CERTIFICATE # I A-0109 6280 l CNS 1-13C II 9152 ! ABB-2001 9274 l CNS.1-13G 9216 AI 500 SU 9006 l CNS 10-160B 9204 j l ANF-250 9217 l CNS 14-170 III 9249 i t AP-101 9071 l CNS 14-195-H 9094 l ATR 9099 l CNS 21-300 9096 A1W-3 CB/TS DC 9789 l CNS 3-55 5805 .
.A1W-3 HD/SB SDC 9790 l CNS 4-85 6244 f
?
.A1W-3 PUSC. 9787 l CNS 6-75 9108
! i B-3 6058 l CNS 6-80-2 9111 l l 6 BCL-2 9068 l CNS 6-80-2A 9111 BCL-3 9067 l CNS 8-120A 6601 l BCL-4 5950 l CNS 8-120B 9168 BETTIS WASTE 6142 l CNSI 14-215H A 9176 f f BMI-1 5957 l .DHTF 9203 l BS-33-180 6722 l D1G CB-TS 9792 f BU-7 9019 l D2G POWER UNIT 6441 l BUSS'R-1 9511 l E-MEH-00-00004 9011 BW-2901 9251 l FL 10-1 9009 C-l' 9036 l FPD-100 9057 Ca8 9128 l FSV-1 6346 CGN 25/35 RCDP 9794 l FSV-3 6347 CI-20WC-2 9098 l GE-100 5926 CI-20WC-2A 9098 l GE-21PF-1 4909 i GE-500 9049 CNS 1-13C 9081 l l V
l U.S. NUCLEAR REGULATORY COMMISSION IFEX OF CERTIFICATES BY MODEL NUMBER 10/01/1996 , MODEL # CERTIFICATE # l MODEL # CERTIFICATE # ! GE-8500 6697 l M-140 9793 { i HFBR'UNIR CONT 9853 l M-160 9781 HN-100 SERIES 3 9151 l MCC-3 9239 HN-190-1 9086 l MCC-4 9239 , HN-190-2 9224 l MCC-5 9239 ! HN-194S 9089 l MO-1 9069 l IF-300 9001 l MODEL B 6206 INNER HFIR UN 5797 l MODEL 1 S-6213 9186 IR-100 9157 l MODEL 2 S-6213 9186 ; IR-50 9156 l MW-3000 9030 ) t LCG-25A 4888 l N-55 9070 LCG-25B 4888 l NAC-LWT 9225 l LCG-25C' 4888 l NAC-STC 9235 f i LL-60-150 6568 l NAC-1 9183 LN 10-135A 9177 l NATICK IRRADI 5362 i t LN 14-170 1 9151 l NCI-21PF-1 9234 IR 14-170H 9159 l NFS-URANYL NIT. 5059 LN 14-170L 9159 l NLI-1/2 9010 ; LN 14-170M 9159 l NLI-10/24 9023 j LN 14-195H 9176 l NNFD SX22 9250 LN 14-195L 9176 l NNFD-10 635*/ LN 6-80H 9179 l NONE SPECIFIED 6406 l LN 6-80L 9179 l NPI-20WC-6 9102 ' LN 7-100 9178 l NPI-20WC-6 MKII 9215 j M-130 6003 l NRBK-41 9221 l r l vi l l
l 4 U.S. NUCLEAR REGULATORY COMMISSION INDEX OF CERTIFICATES BY MODEL NUMBER l 10/01/1996 MODEL # CERTIFICATE # l MODEL # CERTIFICATE # l l NUPAC 10/140 9177 l RCC-1 5450 NUPAC 14/190H 9159 l RCC-3 5450 NUPAC 14/190L 9159 l RCC-4 5450 NUPAC 14/190M 9159 l SENTINEL-100F 5862 i NUPAC 14/210H 9176 l SENTINEL-25A 4888 NUPAC 14/210L 9176 l SENTINEL-25B 4888 l \ NUPAC 14D-2.0 9079 l SENTINEL-25C 4888 NUPAC 50-1.5L 9145 l SENTINEL-25C3 4888 NUPAC 50-2.5L 9145 l SENTINEL-25D 4888 NUPAC 50-3.0L 9145 l SENTINEL-25E 4888 NUPAC 50-4.0L 9145 l SENTINEL-25F 4888 l NUPAC 6/100H 9179 l SENTINEL-8 9030 NUPAC 6/100L 9179 l SNAP-21 5830 i NUPAC 7/100 9178 l SP-1 9248 i OP-100 9185 l SP-2 9248 ORNL TRU CALIF 5740 l SPEC 2-T 9056 OUTER HFIR UN 5797 l SPEC-150 9263 j PADUCAH TIGER 6553 l ST 9246 j PAS-1 9184 l S2C REC. COMPT. 9788 PAT-1 0361 l S3G CBDCA 9786 PAT-2 9150 l S3W REC. COMPT. 9788 i PWR-2 CORE BAR. 9791 l S4W REC. COMPT. 9788 l l RA-2 4986 l S5W POWER UNIT 5580 RA-3 4986 l S5W REC. COMPT. 9788 RCC 5450 l S5W REFUEL.SRCE 5757 f vii
)
i U.S. NUCLEAR REGULATORY COMMISSION : INDEX OF CERTIFICATES BY MODEL NUMBER 10/01/1996 MODEL # CERTIFICATE # l MODEL # CERTIFICATE # ; i I T-2 5607 .l 10-142A 9073' ! T-3 9132 l 100 9127 ! TN-BRP 9202 l 100A 9127 i TN-FSV 9253 l 110G-A 9247 l t TN-RAM 9233 l 125-B 9200 ' l TN-REG 9206 l 14-215 9222 i TN-8 9015 l 1500 5939 TN-8L 9015 l 181361 5796 ; TN-9 9016 l 181375 5796 l TRIGA-I 9034 l 2.7 NEW FUEL 5894 l TRIGA-II 9037 l 20 9126 TROJAN PRESSUR. 9260 l 20A 9126 TROJAN STEAM 9259 l 200 9127 i i TRUPACT-II 9218 l 200A 9127 I UC-609 9932 l 2000 9228 UNC-2600 5086 l 235R001 6386 UNC-2901 6294 l 3-82B 6574 j URIPS-8A 6786 l 3206B 9167 ; URIPS-8B 6786 l 3218 9167 ! UX-30 9196 l 3227B 9167 WAPD-40 5874 l 4.5 TON CF 6642 l l YNPS RPV 9262 l 40G-A 9254 l 6 YNPS STEAM GEN. 9256 l 420 9245 1 l 10-135B 9210 l 50 9126 l 10-142 9208 l 50A 9126 1 4 viii l l
. - . . . . - - . - . - _ - . - . ~ - - - . . . . - - . - - . - . _ - . - - . - --
1 U.S. NUCLEAR REGULATORY COMMISSION INDEX OF CERTIFICATES BY MODEL NUMBER 10/01/1996 i MODEL # CERTIFICATE # l MODEL #. CERTIFICATE # 6581 680BE 9035 51032-1 l 9252 680E 9035 51032-2 l 9139 l 684 9028 589 5979 684A 9028 5979 l 5984 684AE 9028 5984 l 6400 684B 9028 6400 l 9032 l 684BE 9028 650 l 9269 l 684E 9028 650L , 9033 702 6613 660 l 9033 l 715 9039 660A i 9033 l 741 9027 l 660AE 1 9033 l 741A 9017 660B 9033 l 741AE 9027 660BE 9033 l 741B 9027 l 660E 6717 741BE 9027 6717-B l 9029 741E 9027 676 l 9029 770 9148 676A l 9029 771 9107 676AE l 9029 814A 5149 676B l t 9029 820 9137 676BE l 9029 850 9147 676E l l 9035 855 9165 680 l i 864 9166 ! 680A 9035 l 9035 865 9187 680AE l 920 9143 680B 9035 l l h ix
U.S. NUCLEAR REGULATORY COMMISSION INDEX OF CERTIFICATES BY MODEL NUMBER _0/01/1996 MODEL # CERTIFICATE # l MODEL # CERTIFICATE # I 927Al 6078 l 927C1 6078 l 934 9243 l 1 , I ; 1 i : i I I . I I I l, I ) I I i i I I I I i l i i I
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gr_---=-----------------------------------------7 I U.S. NUCLEAR REGULATORY COMMISSION I MAC F08tM 918 I CERTIFICATE OF COMPLIANCE I I cm If i I e cra n FOR RADIOACTIVE MATERIALS PACKAGES I C PACKAGE IDENYiFicAliON NUMBER c PAGE NUMBER e TOTAL NUMBER PAGES
. . cenrincAre NUusta o nev4ON NUMBER 4 l 6 USA /0361/B(U)F-85 1 0361 ,
I Patausts l
- a. Tnis certificate is issued to certify that the padagmg and Contents desenbed in item 5 below, meets the applicable safet y standards set forth in Title 10. Cod I
of rederai neguistions. Part 71. " Packaging and Transportshon of Radsoactive Matenal? l l I b. This certificate does not reheve the consignor from comphance with any requiremer)t of the reguistions of the U.S Department of Transportation or other I I apphcabie reguistory agencies. mciuding ine goverr ment of any country tnrough or into wnsen ine pacaage wife be transpo,,eo. p I I I l * '"'*siE'@,^18 '*5ff, " '"' *^8 ' ^ 5^" ^"*"S,"',Ts',NV,"ot0 Jc^fy'#Me"OO'C#4t c,1,0N I I NUREG-0361; Safety Analysis Report for the l I U.S. Nuclear Regulatory l Commission Plutonium Air Transportable Package Model il, l Washington, DC ?0555 .No. PAT-1, as supplemented. l I I 1 I
. oocus, Nuussa 71-0361 I
I 4 CONDmONS I This certificate is condational upon fulfilhng tbo re' quirements of 10 CFR Part 71, as apphcable, and the coridations specified below. l l 5 .y a l I I I (a) Packagingr< >f I I : . ' I I (1) Model",No.: PAT-l':+ I I .. ; , (2) Description ( 3 l l *f
+4 f/ I p
l l A stainless" steel'contailiment vessel (designated TB-1) surrounded by a i l k stainless ' steel and redwood overpack (designated AQ-1). The contents I I steel product can (designated PC-1) I ! I are ' sealed inside,the" containment a4. within a' vessel stainless ld r I i 14 -;3,.g; TheAN-1ovehp'achis rigbtfcircular cylinder, .approximately 42-1/2 l inchesxlong by 24-1/2 dnches outside diameteri.3The walls of the overpack ii I i consist oflrapproximately 8 inches of> grain oriented redwood encased I I within double stainless steel drums. The ends of the drums are doubly closed. A copper heat conducting elementland an aluminum load l ' l distributer are eni:ased within the redwood, g l i 9 % , A p 'jA The TB-I containment vissel'is approximately 8-1/2 inches outside g i i -l I length by 6-3/4 inches outside diameter. The minimum wall thickness I I of the vessel is approximately 1/2 inch. The interior cavity of the vessel is a right circular cylinder, 4-1/4 inches diameter, with l l hemispherical ends. The vessel is closed by 12, 1/2-inch diameter p l l bolts and doubly sealed with a copper gasket and knife edges and an a l l I l I elastomer 0-ring. I , I I J I l ! I I l I I I l l l l l I i I I I l l 1 l 2 _________-_____ ----_--_--- - -------- ---- ------------ i
*C""** U.S. NUCLEAR REGULATORY COtetelSSION
- cONDmONS (conunued) l ,
Page 2 - Certificate No. 0361 - Revision No. 6 - Docket No. 71-0361 I I i l
- 5. (a) Packaging (continued) l (2) Description (continued) l1I The weight of thr, package is approximately 500 pounds. The weight of I the TB-1 containnent vessel, when loaded with 4.4 pounds of contents y is approximately 41.7 pounds. g l I 1 (3) Drawings and Specifications j The Model No. PAT-1 packagin is fabricated in accordance with the drawings and specifi t s pgtio 9.0 of the Safety Analysis l ,
y Report, NUREG-03610a le(6nted-l ue B of Drawing Nos. 1004, p 1009, 1013, 1 6y1017, 1018, 1019, I q 22. (b) Contents D O l (1) Type an r of material 77 l Plutoqqn oxideg s daughter pr n any si id form. The i pluto Tm oxide e ixpd with t . oxide an( its daughter I prod c ,inany/s orm A / ' 4 ! 1 l A e O I - (2) Maxiu(mquan t 'of ts&pT%(i conten s F 4_'andadditiglpermissible
/
l 1 t f (f) (i) Maximu
^\E atohl r t c a 1
>2' ve mat e d >
,pida maximum 16 grams I i
l i o ateriam . rG > p p or poly 1rinylchloride bagging i I ma t al .4 ; l,dc Qp _ y1 "ed of thV., contents may not ex' o? l 1 25 ttsh (g (ii) Maxi 0 grams toth rNdioactive ma O1, plus: maximum one a gram of r, maximum 200 grams of 1 canning material (in I l t addition th PC-1 product can raw ng No. 1024), maximum 64 I I I grams of alumi fgj 10hadpy (in addition to the top r i f spacer, Drawing o.5 015 mRimum 175 grams of glass and maximum i i I l 35 grams polyethylene or polyvinylchloride bagging material. The i ( maximum decay heat load of the contents may not exceed 25 watts. I (c) Transport Index for Criticality Control y' I g ( Minimum transport index to be shown on p [ label for nuclear criticality control: 0.4 I p I
- 6. The PC-1 product can (Drawing No.1024) and the top spacer (Drawing No.1015) I (l
[ I need not be used when the contents include 20 curies or less of plutonium. l } ' [ 7. Prior to first use, each packaging shall meet the acceptance tests and standards I i h specified in Subsection 8.1 and Section 9.0 of the Safety Analysis Report. I , I 8 . Prior to each shipment, the package shall meet the tests and criteria specified in Subsection 8.2 of the Safety Analysis Report. l I g 2
_____,l u.s. NUCt. EAR REGULATORY COMW$$lON g" "" Cowomows (continv ,, I Page 3 - Certificate No. 0361 - Revision No. 6 - Docket No. 71-0361 l I I I l l l R 1 9. The package sbs11 be prepared for shipment and operated in accordance with the i 1 procedures specified in Section 7.0 of the Safety Analysis Report, j l
- 10. The systems and components of each packaging shall meet the periodic tests and l lg criteria specified in Subsection 8.3.of the Safety Analysis Report. p 1
I
- 11. Repair and maintenance of the packaging shall be in accordance with Sections 8.0 I and 9.0 of the Safety Analysis Report.
l
- 12. The packaging shall be designed, procured, fabricated, accepted, operated, l l maintained, and repaired in accordance with a quality assurance plan approved by y g
g the Nuclear Regulatory Commissic rQigp e. with the carrier, the per shall ensure observance j i
- 13. Through special arrange (,l controls for each shipm 1%f plutonium by air: '8 of the following oper a (a) Thepackage(spaustbestowedaboardaircraftont in deck in the aft-most g g
location that Ts possible for cargo of its size anf t. No other type jy ( f
'f N cargomaybe",yowedfafhofthepackage(s). i I
(b) The package )mustha~ u 1 cra$ed n 1 -downtOhemaindeckof ding package j the aircraft'. The tiet- y ekmu'st p)ble of p f restraint q[ gainst theif6) ngjneriaJopstactingse ward, ately relative g g rd gg;S 1.5g; to the deck 'of then aircr :\Ufhfiifd, kr p v -
/ /, I Downward,tC 5g. D OtQV N
- y/ I li (f) thPig l azardou'ff- sterieblabels may not be 8
'l (c) Cargo which bears- 5 h v :i 1
,crj{tg i' pac i(s): N I transportedg)oardian' 1 CO l i
f Explosi
,4 h ,
1 le Gas CQ g I Explosiv amma iqui N N [. 8 i Explosive // - hmmable Sol
'l Spontaneous 1fhtsbustible Flammable Ga l Dangerous When Wet 0xidize i g
gl Organic Peroxide k orgi i I i This restriction does not apply to hazardous material cargo labeled solely as: ,i , l Radioactive I Poison l l t'oison Gas p g Radioactive 11 I i Radioactive III Irritant Magnetized Materials Etiologic Agent l l l 14. The package authorized by this certificate is hereby approved for use under the [ p l q general license provisions of 10 CFR 971.12. I I Il I 15. The package authorized by this certificate is hereby approved for transportation I ll of plutonium by air. g 16. Expiration date: September 30, 1998. I N 3 K
NAC FORM steA U.S. NUCLEAR REGULATORY cot 0MittlON te-em CONDITIONS (continued) Page 4 - Certificate No. 0361 - Revision No. 6 - Docket No. 71-0361 l ' l I i I l REFERENCES I I I I l Safety Analysis Report for the Plutonium Air Transportable Package Model Number PAT-1, I i NUREG-0361, June 1978
' l Sandia Laboratories application dated February 20, 1980.
l Supplements dated: July 27, 1990 and July 20, 1993. l l l l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l e I I
\J cfxB R h@iam D.
- f. \," Will Spent Fuel P rs, Director t Office 1 i
l gh l Office of Nuc1 agaterial Safety l , and Safeguards l
, i ! Date: 3 2. l l Clkw Ty% /
k ? %_M ' o i i l
< vi A..l ?
o ; i y a%% p E
! <D
.i%d . v '@yg ;
l 5' , o S l Y *
- 1k # I I I
I I I I I I I I a I i I
- I I
I I I i I 4 _-_____________________________________________________l
______-- -------- -----__ --- -------- ---------------I U.S. NUCLEAR REGULATORY COMMISSION penc Fostas sis I t
; == CERTIFICATE OF COMPLIANCE I so crn n FOR RADIOACYlVE MATERIALS PACKAOES a nev seoN NUMBEn c PACKAGE lOEN1W4 CATION NUu ER e PAGE NUMBER e TOTAt NUMBER PAGES NuueEn i e ccmwE8 10 USA /4888/B( ) 1 4 l pauusts I
- a. This certificate is issued to certify f*iat the packaging and contents descr6 bed in item 5 below, meets the applicabb safety standards set forth in Title 10 Code l of Federal Reguistions. Part 71. " Pack oging and Transportation of Radioactive Matenal." l I
- b. This certificato does not releeve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or other apphcaba reguistory agencies, inciuding the gov.mment of any country through or into wnien ine p.ckage wiii de transported.
I I I I y a TNre ge m g g is ;ss guoN r.* asis or a sarerv ANatysis negt,or,v,Ngggegsygogn erytgo ,N i Teledyne Energy Systems applications I Department of the Air Force Technical Operations Division /CC dated April 26, 1985 and August 19, 1986* l as supplemented. 6000 Patrol Road g McClellan AFB, CA 95652-1709 g
- c. oocxtr Nuu ca 71-4888 1
- 4. CONDivlON5 This cettsf6cate is conditional upon fulfilhr g the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
I s. I I I I (a) Packaging l l (1) Model No.: Sentinel-25A, LCG-25A; Sentinel-258, LCG-25B; l Sentinel-25C, LCG-25C; Sentinel-25C3, -250, -25E, and -25F I I (2) Description I l l The packages are thermoelectric generators. The major, components include the main housing, tungstan shield; housing flange, and electrical connectors. l The approximate dimensions 'and' weights for the various Model Nos. are as - I follows: i l I l Model Noa Dimensions (inches) Weiaht (1bs.) F Sentinel-25A, LCG-25A 25 OD x 25 3000 l Sentinel-258, LCG-25B 25 OD'x 25 3300 l Sentinel-250, LCG-25C 24 OD x 32 2000 l I Sentinel-25C3 24 OD x 32 1300 l Sentinel-25D 25 OD x 27 3300 Sentinel-25E 25 OD x 34 4200 l Sentinel-25F 24 OD x 32 1400 y l i I I I I I l l l l l l l l I I 5 y
us. wmAn nemi ny commission g," ** cowomons(continu a, l I Page 2 - Certificate No. 4888 - Revision No.10 - Docket No. 71-4888 I f I + 1 1 (a) Packaging (Continued) l 4 I l l (3) Drawings I- i I I . l The packagings are constructed in accordance with the following Drawing Nos: I l l Model No. Drawina Nos. I i , 1 All Models Isotopes, Inc. Drawing Nos.: I I 001-20000, Rev. E l. l I 001-20001, Rev. F I l 001-20002, Ref. F I i ,001-20003, Sht. 1, Rev. B l
' p- r 5
'001-80003 - l ,
i I . , i I Se ".inel-25A, LCG-25A Martin Company Drawing Nos.: I I : I N0013100, Rev.' A I l .. N0013108, Rev. D I i 001-40000, Rev. A' !,I i . I I
' s Isotopes, Inc. Drawing Nos.:
' " l I
001-10000, Rev. B l 001-70024, Rev. C l , I i i 001-70025, Sht. 1, Rev. D I i 001-70033, Shts. 1 & 2~ Rev. A ' i 001-70036 l , i
;) ;001'80005 .
i , i N' Sentinel-258, LCG-258 ; ! Martin Company' Drawing Nos.: I l
- N0013200, Rev. C I i '001-40012- l I i I
I Isotopes,'Inc. Drawing Nos.: 1l 3 i i 001-70024, Rev. C I l l 001-70025, Sht. 1, Rev. D I l
; 001-70033, Shts. 1 & 2, Rev. A i 1 001-70036 l 001-80005 .l ,
g I II Sentinel-250, LCG-25C Martin Company Drawing Nos.: l Il i 001-40004, Rev. A I j i 001-70010 I i i 001-70012, Rev. B ,l i 001-80004 I i, i l Isotopes, Inc. Drawing Nos.: l L g 001010000, Sht. 1 Rev. D, & Sht. 3 ll ' i 001-70009, Rev. D l Sentinel-25C3 Isotopes, Inc. Drawing Nos.: l [ 001C10000 Shts. 1 & 2, Rev. D l 001-70009, Rev. D ll i' 001-70057, Rev. D il I 001-70060, Rev. C 001-40019, Rev. B j l g _____________________________ 6 ________________ i
l l __ vs.nucwnomon cmassoon ll R** conomous tcontinued) , l Page 3 - Certificate No. 4888 - Revision No. 10 - Docket No. 71-4888 l 1 1 I 3 1
- Sentinel-250' Martin Company Drawing No.
l , 001-80004 l 1 l I Isotopes, Inc. Drawing Nos.: p 1 i 001010000 Shts. 1 & 2, Rev. C 1 i 1 001-70036 I + i 3 001-70033 Shts. 1 & 2, Rev. A I l 001-70025 Sht. 1, Rev. D l i 001-70024, Rev. C g ! l 001-40015, Rev. C g l I ! 001-40006, Rev. B I I , l 1 I I Sentinel-25E <; O Isotopes, Inc. Drawing Nos.: 3~ O +#001E10000, Shts. 1 & 2, Rev. E, & Sht. 3 ll l i ' 001-70039;.Rev. C i ! I 001-70025, Sht. 1, Rev. D & Sht. 2 l l i 1 001-70024, Rev: C3 I 1 001-40017, Shts.-11& 2, Rev. D I , l 001-40006, Rev. B .'
, ,l, ],
Sentinel-25F s Isotopes,Inc. Drawing Nos.: g i 001F10000, Shts.1 & 2', Rev. H* I , 1 001-70070, Rev. C i l I I I - 001-70060, Rev. C E
- '001-70009, Rev. D i I , .
.~ , _001-40025, Rev. A l l m. ,
*As modified by Figure 1 of I N I I a Jthe April 26, 1985,- application.
l y' (b) Contents y I ' I s l (1) Type and form of material ' l l , I I (1) Strontium 90 titanate doubly encapsulated in a Haste 11oy or Uniloy fuel capsule which meet the-requirements of special form l l radioactive material; or - i I I I I I I (ii)'Model No. Sentinel-25F may have, strontium fluoride doubly i I encapsulated in Haste 11oy or Uniloy fuel capsule, with a Haste 11oy I C-276 liner which meets the requirements of special form l radioactive material. , l I I 1 i l l (2) The maximum quantity of material per package I I 1 I 125,000 curies I I
- 6. A barrier (permitting the free circulation cf air) must be provided with l 1 l sufficient separation distance to ensure that the requirement of 971.43(g) will be p l i I 1 met. ll li I
I
- I I
l 7 l __ _______ ________________________________I
--------------a-----------------------------------r
*c == m^ ***" * '*""' " "* ""**'"
m cowomows (continu.a> Page 4 - Certificate No. 4888 - Revision No. 10 - Docket No. 71-4888 l(l B I 7 Eye-bolts shall be removed or covered during transportation to prevent their use as tie-down devices of packages. l b i
- 8. il l In addition to the requirements of Subpart G u '10 CFR Part 71, each package shall u l be operated, prepared for shipment and maintained in accordance with the following i Operating Procedures and Maintenance Programs:
l ! ; Model No. Doeratina Procedures Maintenance Proaram ! I Sentinel-25A, LCG-25A Appendix E of TES-3206, Appendix F of TES-3206, I l as revised as revised i R l Sentinel-258, LCG-25B Appendix E of;TES 3209, Appendix F of TES-3209, astrevised *'" as revised l
.1 a(} - ,-
i l Sentinel-250, LCG-25C i Appendix E of TES-3210, , Appendix F of TES-3210, I as revised 'as. revised i Sentinel-25C3 Appendix E of TES-3211, App'endix F of TES-3211, l as revised as reirised [ 1 i l' Sentinel-25D Appendix E of TES-3212,~ _ Appendik F of TES-3212, I as revised as revised 1 N Sentinel-25E Appendix E of TES-3213,. i Appendix F of TES-3213, as revised ,as revised l i i . I Sentinel-25F ! t, Chapter VI!! of TES-3202, , Chapter-IX of TES-3202, I
! as revised 5 as revised j i 9. The packages authorized by this certificate are hereby approved for use under the l general license provisions of 10 CFR 971.12. l p
I l ;
- 10. Expiration date: December 31, 1996. N
,j N REFERENCES l
l Teledyne Energy Systems applications dated April 26, 1985; and August 19, 1986. I 1 l l Teledyne supplements dated: November 3, 1986; September 17 and December 2, 1991. l lt Department of the Air Force supplement dated: November 12, 1993.
}
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION g Tow /d 5 $n Cass R. Chappell, Se tion Leader ! Cask Certification Section p Storage and Transport Systems Branch il Division of Industrial and i Medical Nuclear Safety, NMSS l e Date: ! g N_ 8
----------- -_____--- __-___._______- ____,_,_ --_ _-4,
3 l \ u.s. NUCLEAR REGULATORY COMMISSION I l I mac rones eis CERTIFICATE OF COMl PLIANCE I < l I w I l a Ca n FOR RADIOACTIVE MATERIALS PACKAGES D REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER O PAGE NUMBER ~e . TOT AL NUMBER PAGijn 4 . CERTwiCATE NUMBER 6, 4909 14 USA /4909/AF 1 3 l l l ! i 2 PREAMBLE l 1
- a. This certificate is issued to certify inat the packaging and contents described in item 5 below, meets the applicable safat y standards set forth in Title 10 Code I l of Federal Regulations, Part 71, *Packagmg and Transportation of Radioactive Matenal" i
I l b This certificate does not reiieve tne consignor from compiiance with any requiremoryt of the reguistions of tne u s. Department of Transportation or other apphcable reguistory agencies. 6ncluding the government of any country through or into which the package will be transported. l l 1 I l I I I
- s. TNis CERTIFICATE IS l& SUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION l a ISSUED TO (Areme amt Amass / b. YlTLE AND IDENTIFICATION OF REPORT OR APPLICATION I General Electric Company General Electric Company application dated l P.O. Box 780 January 26, 1994. i l g Wilmington, NC 28401 i
1
- h1. g#1 g
71-4909 I I I w 'c. DOCxET NUMBER
- d. CONDITIONS g (i This certificate is conditional upon fulfillmg e requirements of 10 CFR Part 71 as apphcable, and the coretions specified below.
I I s. A '
- N 's I I
I I @) , l I 1 (a) Packaging Qf scb-Jf -. I
-e ' -(4
. < -// '
I I Model No.A:' GE-21PF-l' O\p l l l (1) 1 l Q s - % \ ,) '
, , l
-- ( f '>
r- p i (2) Description m a
- I l
I t- ,f, ' g +.J _ z 7,f n i I l Overpack(for 30-inch diametere enr,iched uranium hex'afluoHde (UF 6 ) cylinders. I l I The overpack is'af right circular, cylinder' constructed ofatwo stainless steel l shells. The annulkhvolume:between ithe shells is filled with wood blocks and l i fire-resist' ant phenolic; fp'am' ap;iroxiniately. 6 ; inches thick. The foam is in l ecification SP-9,,Rev. 1, and(Supplement K/TL-729. A I l I accordance'With stepped and'gasketedUSAEC hor Sp,izontal joint, permits the top half of the overpac i I I be removed from;the base. Thelpackage " halves" afe. secured with fourteen, I 3/4-inch boltfnut'fwasher assemblie's. The overpack'is approximately 43-5/8 l inches OD by 95-I/2 inches long. Maximum grosslweight of the package is i l 8,600 pounds. i i I y h fe h[ ,pb I i I (3) Drawings I I The packaging is constructed in accordance with General Electric Company l l Drawing ho. 769E237 - Sheet Nos. I and 2, Rev. 4. In addition, the length of i l i l l the 8" x 2.5" tie-down support channel may be from 43 to 55 inches long and I I vent holes in the exterior shell may be sealed with plastic plugs. I I I I i I I ! l I I l l l I l l I i l l I ) l I l I I I I I I I I I I i l I l 9 i I
e um ma U.S. NUCLEAR REGULATORY CO80880SSION cm CowomONS (continued) l, Page 2 - Certificate No. 4909 - Revision No. 14 - Docket No. 71-4909 l l l l (b) Contents I I (1) Type and form of material l Uranium hexafluoride enriched in the U-235 isotope. ! 1 (2) Maximum quantity of material per package I I (i) Model No. 30A cylinder: 4,950 pounds UF6 enriched to not more than b I w/o in the U-235 isotope. l s,U,F enriched to not more than 5 6 l (ii) Model No.U-235 w/o in the 30B cylindeg: isotppe. Q,0Q{3p2U i (c) Transport Index for C i y Control Minimumtransportj$1pxtobeshownon A g label for nuclear criticality control: 5. 0e# M- r i CQ l
- 6. In addition to t g uirgmg req \ h of ~tSubpart G o fRPart7 I (a) Prior to e b shipmenh ve h M a o mlstbeins ted. These j gaskets ming be replacedf insppctidyso gafydefects every 12 months, g whichever curs f r tt jf g g (b) Eachpackag()gmhet thg% : tt o f asTs a Haintenance Program of I
$ the ddp I a L u r?' fg 4 I (c)
Sections 7.2 The package and n %;-W[f 11 be/ [ "pkr M
,i
'M$ Q - %
bperatehnaccordancewith I the Operatin 4 l cedbres6{3 S ti o applid$ pion. l (d) The loaded cyli must be ship d bthout a va(vhrotector. The valve I protector must be aced in accordance with n p l handling practice when I the cylinder is remo d m the overpack. I, (e) Prior to each shipment, the s nks el components of the packagirg must -! be visually inspected. Packagings in which stainless steel components show I pitting, corrosion, cracking, or pinholes are not authorized for transport. l
- 7. (a) For packagings which are not seal welded, the joints between the inner and l outer shells (ends) and the side (end) panel moldings must be silicone i sealed. The inner and outer overpack gaskets must cover side (end) panel i molding joints (unless seal welded). Except for joints covered by a glued I down gasket, visually inspect all silicone sealed joints and maintain in good I repair prior to each shipment or outside storage (loaded or empty). I I
(b) All body seams and joints for the inner and outer shells (ends) and the side i (end) panel moldings must be continuous welds. Welding must be by a fusion i process in accordance with the American Welding Society Code or American I Society of Mechanical Engineers' Code. [I I i 10
U ##""#C"S" CONDITIONS (continued) l ? l fY,f"#Page 3 - Certificate No. 4909 - Revision No. 14 - Docket No. 71-4909 l l I I I N 8. The 30-inch diameter UF 6 cylinders must be fabricated, inspected, tested and i l N maintaired in accordance with American National Standard N14.1 (1990 version). I Cylinders must be fabricated in accordance with Section VIII, Division I, of the l ASME (American Society of Mechanical Engineers) Boiler and Pressure Vessel Code l g and be ASME Code stamped. ; l l l 9 l l 1
- 9. At least once every five years, each packaging must be inspected to verify the I l
presence and condition of the insulation. The inspection shall consist of I l inserting a probe through each vent hole in both the lid and base to confirm the g presence and rigidity of the insulation. For packagings which require drying, the l l inspection must be performed after drying. y
- 10. Shackles are for lifting Ig kl s u g/ e used for tying down the package during transpor j i 11.Thepackageauthorizdbythiscertificateisherebyapgedforuseunderthe ly py generallicensepro(isionsof10CFR571.12.
- 12. Expiration date: CMovemNr-30,1999. A hh ,qf[/ Q fd/
E 8 h:3
~
h; q f 6 ) REFERENCES 31/ c 3 84 Q 1l (M General Electric Company applicatidq%datedQaduary/26,J1994., ?> g r g r- a - ,
~
Supplement dated October k6 4' $ NI I' e l I k af F0'R
;hik('[d .#CJ E hS.NUCL'Ek'REGULATORYCOMMISSION-R jC hl N
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'll WilliamD.TravershDirector m
R l g
/ j Spent Fuel Project Office j
! A sf w.0ffjce of,Nudlear Material Safety ,
"d; 4 and Safeguards i R:
Date: Mi9 0 1 l N I - 1 ! q, .i l Il Ri i l Il l Ul l Nl 8 i E I , g N ' 3 4 8 I 8 I ! bl
\
N l N I I I 1 I 11 8--------------_--------------------_---,--_-,,---------,I
_----- ----------------------------------------------- 5 mac ronu sie u.S. NUCLEAR REGULATORY COMMISSION I ( is am CERTIFICATE OF COMPLIANCE N l w crR " FOR RADIOACTIVE MATERIALS PACKAGES t I f a CERiirecATE NUMBER b REVISION NUMBER C PACKAGE IDENTWICA1 ION NUMBER 'e PAGE NUMBER 'o TOTAL NUMBER PAGE3 I 4986 33 USA /4986/AF 1 a N l 2 PREAMBLE I i a This certificate is issued to certify that the packagmg and contents descnbed m item 5 below, meets the apphcable safety standards set forth m Title 10. Code l i of Federal Regulations. Part 11. " Packaging and Transportation of Radioactive Material" l l b Tnis certificate aoes not renove the consignor from comphance with any requirement of the regulations of the u s oepartment of Transportation or einer l lR apphcable regulatory agencies, mcluding the government of any country through or into which the package will be transported jI I I il' i l I N
- rNis,gRririca,rysygy
, rsE sasis O, A sArErv ANAtysis,REgr o,, r,sE P,AcxA,ogs4G , 04A,PP 1
i General Electric Company General Electric Company application dated ' l' l P.O. Box 780 March 17, 1992, as supplemented. l 1 Wilmington, NC 28402 lI I I I l l . oOcnErNuueEa I I ruou C. CONDirlONS I inis cettificate is conditional upon futfiinng ine requirements of 10 crR Part 71. as appocabie. and the corwistions specified beiow. l lll l s. I I
;A I l
1 l (a) Packaging Ld , j i e~ I l (1) Model Nos..: RA-2 and RA-3). ' I l M ),
I i
I (2) Description ' I
' " ' l I
i A fuel a's"sembly and fuel rod shipping container. Packagings are right ; I i rectangular boxesiconsistinglof. an outer container of wooden construction and 1 I a metal inner container separated.by cushioning material. I l s, y3 L , I I The metal inner container is '1-1/2 1 inches by 18 inchds by 179 inches long and I is positioned within a Model,No. RA-3 wooden outer-container approximately 30 l l g i inches by 31 inches by 207 inche's long. Cushioning is provided between the 1 l inner and outer cbntainers by phenolic impregnated honeycomb and ethafoam, or i i I equivalent. Closure js accomplished by bolts," latches, or equivalent. A I pressure relief (breather) valve istprovided on the inner container, and is I l set for 0.5 psi differential. ;The~ total' weight of the packaging and contents i is 2,800 pounds. l y i (3) Drawings I
, I I
I I i The packagings are constructeil in accordance with the following General I l Electric Company Drawing Nos.: l ll l 769E229, Revision 7, Model RA-3 Outer Container I r 769E231, Revision 5, Model RA-3 Inner Container i 1 I 769E232, Revision 5, Model RA-2 Inner Container i I I l (4) Product Container l l 5 i Five-inch, Schedule 40, stainless steel pipe fitted with screw type or flange i i closure. Container shall be vented in the event it contains materials which l I decompose at less than 1475*F. i l I I I I I I I I 12 I l, I
! --------- & AA----------A------- ---------------------,
"nc resus essa co ,,,7,o ,,7,,,y ,y,,,
u.s. NuctaAn neoutArony costuission
),
l Page 2 - Certificate No. 4986 - Revision No. 33 - Docket No. 71-4986 1 . I I i 5.(b) Contents l l I (1) Type and form of material i I I (i) Unirradiated U0, fuel rods with a maximum U-235 enrichment of 6.5% by weight. Rods are clad with Zircaloy, Incaloy, Inconel or stainless steel l . such that the ratio of clad to fuel cross sectional area is at least l l 0.26, and have a maximum fuel pellet outside diameter of 0.508 inch. I Each rod must have a maximum length of 174 inches. The clad rods must be I bundled (contained) in the product container described in 5(a)(4). [ (ii) Unirradiated U0, fuel assemblies. Each fuel assembly is made up of l i either 60 or 62 rods 8 J( Cgqua e array with maximum fuel cross- g sectional area of (5 nt ie N aximum fuel length of 150 I . l inches. The ' -235 enrichment ercent by weight, and the I maximum ave e richment is 5.0 percent ight. The maximum pellet I diameter, mum clad thickness, water rod p fications, and poison l ' rod spec ions are in accordance with Sect .1, Appendix 8-H, of l . the supp e s dated June 27 and Novembe 1 (iii) Unirr ed U L assemblies. Eact er assembh is made up of 74 1 , l full anY partia ' juare arre hith maximum fuel l' i t rods % 4 9 j l cross # sectional alt f 25 T ar6 i c{ .gn,d a maxi fuel length of 150 l l l inch The maxtpu - 35 nrichme ) R 0 percen y weight, and the y l he maximum pellet avera e eny) sa V4i6 l maxi . t?by eight p . i diam , mi Dm c ick. nessa .h,od/ 9'cifi ions, and poison l l l l rodspfgifi s5 o c a h l ,w f wn 6 Appendix 8-I, of I l ! I the suppleme pfate% d 8th,e , ) r a ov"emberEf,1995.- I (iv)UnirrahedV ' squar I asse is made up of 92 l l i full and rtii cross-se f al area 0 h rp(6 4f 25/ lipraMn and ray with maximum fuel mum fuel length of 150 I ll l l inches. ximum U-235 32hmentis5.5 cent by weight, and the I ! l I maximum aver nrichment is 5.0 percent eight. The maximum pellet l l l diameter, mini clad thickness, wate trod pecifications, and poison , ! rodspecificationsa$i gacc dagp $ Section 6.1, Appendix 8-J, of i
! the supplements dated JuifE 2 nd m vember 1, 1995. -
l ) I ! I (2) Maximum quantity of material per package ) f Total quantity of radioactive material within a package may not exceed a Type l I j i A quantity. I
- I I
I l l (i) For the contents described in 5(b)(1)(i): 11 l l Two (2) fuel bundles. ll
' (A bundle is defined as an arrangement of rods which are either contained ) I within a product container or strapped together.) I
' (ii) For the contents described in 5(b)(1)(ii), 5(b)(1)(iii), and 5(b)(1)(iv): [ ll
' 's Two (2) fuel assemblies. I 1
l l 13 l l 1
--------------A------------A--------------------- *** conomous ccontmven usmm m comsm Page 3 - Certificate No. 4986 - Revision No. 33 - Docket No. 71-4986 l ll l
1 5.(c) Transport Index for Criticality Control i I Minimum transport index to be shown on I label for nuclear criticality control: 0.4 l
- 6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, !
polyethylene sheath which may not extend beyond the ends of the fuel assembly. .I The ends of the sheath may not be folded or taped in any manner that would I l prevent the flow of liquids into or out of the sheathed fuel assembly. [
- 7. For contents described in 5(b)(1)(ii), 5(b)(1)(iii), and 5(b)(1)(iv), polyethylene holders with a maximum effective thickness of 0.151 inches (0.3835 cm) may be l g
placed surrounding the fuel ass u 1ha um of 0.13 grams H 2O hydrogen i equivalentpercubiccentime(erg g Ve t yssembly. The effective holder il thickness is the linear igage of the maximum an y m thickness. j
- 8. For contents descri n 5(b)(1)(ii), 5(b)(1)(iii), and ;b)(1)(iv), polyethylene !
shipping shims may nserted between rods within the f fsssemblies up to a i maximum of 0.10 ra .
, hydrogen equivalent per cubicpentfryeter averaged over !I the assembly. T hi hims may be used wit ' ithout-the polyethylene ll holders. g ( -f i ,j
.- Q +
r
- 9. Forcontentsdebibedi.aM p) i), lie og { product gtainer specified in 's 5(a)(4),excep r U0 fuel < s wit - 5er R ment greater than 3.2%, clad I rods must be b ed ( nd w st t p two or m locations) with a i maximum cross ion a% 2 n wo . h'e tota reaking strength of I the strapping mth be es' w s 1 ( fg ht ouk no,'ds.
t - I y a 3g. I
- 10. For contents des within the bundl ed {n t be 1 h b[{een. $s t m pf g m ' cing befhen adjacent rods l
st be ntained by the i product container ,m rapp al me ~ ic dunnage with a i melting point great / han 1475'F wt i . r@jeb . l
- 11. Maximum average enrich eans the highest enrichmhaveraged over any axial !
zone of the assembly. y !
- 12. In addition to the requirement of bp t f 10 CFR Part 71, each packaging !
must neet the Acceptance Tests and Maintenance Program of Chapter 6 of the a i application, and the package must be prepared for shipment and operated in accordance with the Operating Procedures of Chaptar 6 of the application. ll , g I
- 13. The package authorized by this certificate is hereby approved for use under the I general license provisions of 10 CFR 671.12. I i
- 14. Expiration date: October 31, 1997.
[r I i i I l! l l' I L______m________________ I
u.s. NUCMAR REGUuTORY COFal8860N l 5"" Cowomous (cononu.a; Page 4 - Certificate No. 4986 - Revision No. 33 - Docket No. 71-4986 ; i I REFERENCES General Electric Company application dated March 17, 1992. l Gsneral Electric Company supplements dated: April 16, October 5, and November 18, 1992; March 18, 1993; and June 27, and November 1 and 3, 1995. FOR THE U.S. NUCLEAR REGULATORY COMMISSION 4 h William D. Travers, D Spent Fuel Project Offic%r g h Office of Nuclear Materia e ty and Safeguards g$ (/) 5% l f f Date: 3 M 9 q., O
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I ee- , [% J4I y .n t E l f,g,fi
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w w w w w w n w w w w w w w w w w w w w w w w w w w w w w w sFii~w w w w w E& w w w w w]ici NRC FORM 618 A l nw CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION Ig soca n - l . FOR RADIOACTIVE MATERIALS I%CKAGES % l l a CERTlHCATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBLR d PAGE NUMBER e TOTAL NUMBER PAGES l 5059 12 USA /5059/AF 1 2 g k 4. PREAMHLE k b
- a. This certificate is issued to certify that the pckaging and contents described in item 5 below, meets the appbcable safety standards set forth in Title 10, Ni
$; o of Federa1 Regulations, Part 71, Packaging and Transportanon of Radioactive Material?
r de k I
- b. This certificate does not reheve the conhi;:nor from compliance with any requirement of the regulations of the U.S Depanment of Transportation or cect k N
applicable regulatory (gencies, including the government of any country through or into which the package will be transported. !
$ N
- 3. THIS CERTlHLATE IS ISSUE a ISSUIDTC(Nua,eed Adircui9 ON THE B ASIS OF A SAFETY ANALYSIS REPORT OF THE PACK AGE DESIGN OR APPLICATION p b. TITLE AND IDENTIMCATION OF RFPORT OR APPLICATION: k Nuclear Fuel Services, Inc. n j
i a Nuclear Fuel Services, Inc., application j P. O. Box 337, MS 123 Erwin, TN 37650 dated March 27, 1981, as supplemented. , j l 9 g
- c. DOCm NuuBER 71-5059
{ h 4 CONDITIONS g This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as applicable, and the conditions specified below. ( ,
~~ g B 3.
g R E Packaging l (a) ' B (1) Model No.: NFS Uranyl Nitrate Tank Trailer E B 6 , B Description B (2) N ! d . B B Bulk liquid insulated. cargo tank trailer. The 3,800 gallon tank 4 i
. trailer .is of all: welded. construction of type 304L stainless steel. E l E
- 4 5 Drawing.
(3) E B
'. Q The tank' trailer is' coristructed in accordance with DOT 4 ;
Specification MC-312.
~
B
~ q !
B d W (b) Contents d l B 4 5 (1) Type and, form of material e B
~
4 B Uranyl nitrate in dilute acid solution. The maximum U-235 g ! B enrichment in the uranium must not exceed 5% by weight. The U-235 g j B content of the solution must not exceed 10 grams per liter, y
~
B E
$ The total uranium content must not exceed 357 grams per liter g p The U02 (NO (1.5M). 3 )2-6H 2 O content must not exceed 50 weight i
g B percent. The HNO 3 concentration will be normally 0.4M. The g B freezing temperattre of any of the solutions must be less than g B 32*F. E I W W B E M;; El Ni E! e E D El N 9' E B! W W Nl i 16 E E ! dm m m m m m m m m m m m sscincu0k m m m m m m m m m m m w w m m m mmm m
g! NRC FORM 618Awwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwgl coNomo%s (umimwds U.S. NUCLEAR REGULATORY COMMISSION i gl g gln+9 E Page 2 - Certificate No. 5059 - Revision No. 12 - Docket No. 71-5059 E 9 m h n s a Wl 5. (b) Contents (continued) El 61
$l B
i (2) Maximum quantity of material per package E N 5 Not more than 45,600 pounds net weight of uranyl nitrate acid solution. W - j sl Total quantity of radioactive material within a package may not exceed a W B Type A quantity. (
# 6 9 (c) Transport Index for Criticality Control (
Bj W Bj Minimum transport index to be shown on g label for nuclear criticality eontrol: 100 g l B; 8 E s 6. The solution must be at a temperature of 68*F or above at the time of packaging. g W g <
! 7. Prior to delivery to a carrier for transport, for U-235 enrichments greater than g n 4% by weight, the shipper must ensure that at no point along the proposed shipping g g route that the ambient temperature will be less than 32* F. In the event freezing g g weather is encountered, the administrative procedures and controls as specified in g 3
Nuclear Fuel Services,~Inc., application dated March 27, 1981, must be complied g p with for all U-235 enrichments. g ,
- 8. In addition to the requirements of Subpart G of 10.CFR Part 71: l f
g (a) Each package must be acceptance tested and maintained in accordance with Section 8.0.of the application, as supplemented. l
- W j (b) Each package.shall be operated and prepared for shipment in accordance with the Operating Procedures in Section 7.0 of the application, as N
g
, supplemented t N
- 9. The package authorized by this certificate is hereby approved for use under the 8 g general license provisions of 10 CFR 671.12.
N
- 10. Expiration date: August 31, 1996.
N U I REFERENCES N N l Nuclear Fuel Services, Inc., application dated March 27, 1981. j l 8 N Supplements dated: August 6, 1986, and July 18, 1991. 8 N FOR THE U.S. NUCLEAR REGULATORY COMMISSION N ~ N 1 p g i l b l s n. , f n' ' h- l l B William D. Travers, Director E 8 Spent Fuel Project Office W l D Office of Nuclear Naterial Safety W ; E y and Safeguards N ; d !
>lDate:
B M bb U a i a h e mammmmmmmmmmmvammmmmma mammmmmmmmmmmmmmmmmmmm2
---------.--------------- mA----AA------------------- y NIIC PORet 01s U.S. NUCLEAR REGULATORY COMMISSION l sai CERTIFICATE OF COMPLIANCE I to CFR n FOR RADIOACTIVE MATERIALS PACKAGES I 9 . CERTIFICATE NUMBER D REVIS40N NUMBER C PACKAGE IDENTIFICATION NUMBER e PAGE NUMBER -e TOTAL NUMBER PAdE'ti 5086 10 USA /5086/B(U W 1 9 .I I
PREAMett I
.. Tnis certdicate is issued to certify t. t ine p.ck.geng .nd contents described in stem s below, meets the.pplic.ble s.fety st.nd.rds set fortn in Title 10. Code I or reder.i negui.nons. een ri. e.ca.ging and Tr.nspori t.on or n.dio.ctive u.ieri i-
,1 o in,s cena,c.te does not rei e. ine cons,anor trom compo.nce witn .ny requirement of ine reouianons or in. u.s. oop.nmeni or Tr.nspon.non or otner ji
.ppucme reguatory genc.es. inciuding in. goarnment of .ny country inrougn or enio .nicn ene p ckage wiii ne ir nsported. I I
I 3 THIS CERTIFICATE 18 ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION I . I
. ISSUED TO therns amt Address / b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION- g 1
Babcock and Wilcox Babcock and Wilcox Company application I P.O. Box 785 dated November 29, 1993. I Lynchburg, VA 24505-0785 . n n I l , c QD li r >
., I
- i L. '.. oOCxc7 NuueEa >71-5086 I a CONDITIONS % .,I ' "'
, This certific.te is condelion.1 upon fulfilling tnopequirements of 10 CFa P.rt 71, .s .ppuc.ble, .nd.4ne consktions specified below.
-a i
s.
@* U,e l l
Ce x 'b, I Q ,) l (a) Packagirjg'f (gN y1s Q e l () a rf~ n , b [) [\t? fd 's I (1) Modhi No.: UNC 2600 , I t g . i.
'l i.
- a.s n
l A. De,s cri ption,,, W'y (i \ v e . (2) u .?. I (J) y M. % A ; g g g rj f ' O I j The inneMchfitainehisan tilfgaug~e steel box with inside dimensions of l 2-578" higlifxJ" wid4 M 96" Jong. The-inner container is supported in a i 2291/2" ID byi102el/2"J1ong,114-gauge steel drum by an insertable cage e I
, for'med,by nin'e'21-1/2"' diameter byz3/8" thic)Psteel plates, spaced I approximately 12"4 apart, withia channel fo[med through the center of the plates'byfangle ironsSfTheJouter bontainer ilosure is made with a 14-gauge' drum lid with 12-gauge bolt lockidg ring with drop forged lugs, . lI i one of which is Jhreaded, having a 5/8fdiameter bolt. I
)% , ks I IT k h{ Y i
(3) Drawing j The packaging is constructed in accordance with Thomas Gutman Consultant Drawing No. B-2600-2, Sheets 1 through 6, Rev. 3. ! I I (b) Contents l I (1) Type and form of material I, I Unirradiated, uranium-zirconium, Naval fuel elements. The uranium may i be enriched to any degree in the U-235 isotope. I I (2) Maximum quantity of material per package l Up to 8.9 kilograms of U-235 per package. The ratio of the weight of l U-235 to the weight of U-235 plus zirconium shall not exceed 0.074. I i The net weight of the contents shall not exceed 265 pounds. 1 I I I 18 I
.-------------------------------------------,-----4 l
_. . ~. . _ _ . . . ._ .._
*** conomons tcontinuee) u.s. nucmemm comsson l l Page 2 - Certificate No. 5086 - Revision No. 10 - Docket No. 71-5086 IlI I
I \ 5.(c) Transport Index for Criticality Control l l Minimum transport index to be shown on I , label for nuclear criticality control: 1.4 I I
- 6. In addition to the requirements of Subpart G of 10 CFR Part 71: l 1
(a) The package must be prepared for shipment and operated in accordance g with Chapter 7 of the application. 1 . ll (b) The package must be acceptance tested and maintained in accordance with li Chapter 8 of the application. l i
- 7. The package authorized by thh c Q Ei is hereby approved for use under p ,
the general license i hf of 1 7 12.
- 8. Expiration date: huary31,1999. l D [o l i .
l REFERENCES a h ! Babcock x d Wilc pp ated November , . SupplementsDatbSeptembh 1995. 99 nd Ja uq O I
-fJ% L LEA REGUgRYCOMMISSION e W > Il (f) %.4
/%
1
'" f I
{ [ p ,A C fj s, Dir k r l h I fGe1 ectoff[ty ll
- [ f (y$tif Qf ( ar M A N a1 Safety ji j
l , a Safeguards () 1 Date: 3 at 19L0 -l l
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i I h . i I i I I l
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.I l l l _--------__--_-____--_ -__-__ __-_-_----___-____------,
19 lll l
gWiiDjiFFFiiiwi I g NRC FORM 618 wwwwwwwwwwwwwwwww iirw w w w w w w w w w w U.S. NUCLEAR REGULATORY COMMISSON g io CERTIFICATE OF COMPLIANCE ! h "w " n- FOR RADIOACTIVE MATERIALS PACKAGES k E' g i i a CERTillCATE NUMBER b REVISION NUMBER c PACKAGE IDENTillCATION NUMBER d. PAGE NUMBER e TOTAL NUMBER PAGES P' 5149 9 USA /5149/B( )F 1 2 gl q J PREAMB11 N bl a. This cenificate is issued to cenify that the packaging and contents described in item 5 below, meets the ap;,hcable safety standards set forth in Title 10 N $l Code of Federal Regulanons. Part 71. "Packagmg and Transportation of Radioactive Material." !
- b. Tha certificate does not reheve the consignor from comphance with wy requirement of the regulations of the U.S. Depanment of Transportation or other N
% apphcable regulatory agencies, includmg the government of any country through or into which the package will he transported. Nl 3 THIS CERTlflCATE IS ISSUED ON THE B ASIS OF A SAllTY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION kj a ISSUED TO ther and Addess) b TITLE AND IDENTii'ICATION OF RfMRT OR APPLICATION: 9; a 5' W
! Babcock & Wilcox Company Babcock & Wilcox Company application g p!
p P.O. Box 785 dated September 20, 1979, as supplemented. g g Lynchburg, VA 24505 g g e DOCKETuuMBER 71-5149 g ; g 4. CONDITIONS - g g This cemficate is conditional upon fulfilling the requirements of 10 CTR Part 71, as applicable. and the conditions specified belom g 5 5. E B E g (a) Packaging g B E , (1) Model No.: 814A g j 5 (2) Description 4 g l Steel container as described 'in Babcock & Wilcox Company's I j application dated September 20, 1979. (b) Contents > l (1) Type and form of material' l N Unirradiated fuel cluster 8 R d 8 (2) Maximum quantity of material per. package a e N 5 One fuel cluster containing U-235 with inserted poison fixture as N $ specified in Babcock & Wilcox Company's application dated W ? September 20, 1979. E N (c) Transport Index for Criticality Control N 4 j Minimum ;ransport index to be shown on E label fo. nuclear criticality control: 25.0 W ~ W
- 6. The package authorized by this certificate is hereby approved for use under the g i
general license provisions of 10 CFR 671.12. E j N , i
- 7. Use of packaging fabricated after August 31, 1986, is not authorized. 4 I i 4 5
E u E
, W j W i '
i E i N 20 El - mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmad
l gwwwwwwwwwwwwwwwwwwwwwwwwwwwwww www.wwww ww wwg l g N,RC FORM 618A CONDITIONS ruarmadj U.S. NUCLEAR REGULATORY COMMISSION e n1 p Page 2 - Certificate No. 5149 - Revision No. 9 - Docket No. 71-5149 gl B E! P El i 8. In addition to the requirements of Subpart G of 10 CFR Part 71: El , pl gl : p (a) The package shall be prepared for shipment and operated in accordance with ! l p the Operating Procedures in the application supplement dated May 18, 1990. ( B W g (b) The package shall be maintained in accordance with the Maintenance Program a ! g in the application supplement dated May 18, 1990. g l 9 E l g 9. Expiration date: June 30, 2000. g I
$ 6 REFERENCE l
l Babcock & Wilcox application dated September 20, 1979. l l Supplements dated: May 18, 1990, andApril2h,~1995: B N l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l i h WilliamD.'Tsavirs,Direstor E 8l Spent Fuel Project Office N Office of Nuclear Material. Safety N
! and Safeguards E 9l f- n Bj Date: $ [M1 Q[o '
E B E n! , ._ n
,1 ,
l e - E B E R a
$I E p! E s' s e a p N B E B 8 4 W 9 0 W 8 l W gl e u l m a
. m. E I i B N h El, s n' y a gl E i s e
# N
- %. . . . . . . . . . . . . . . . . 2 1...................... 4
,1-----------------------------m----------------3 ;
b uncroam m U.S. NUCLEAR REGULATORY COMMISSION i eau CERTIFICATE OF COMPLIANCE l-a crR n FOR RADIOACTIVE MATERIALS PACKAGES I l t . cERTwicATE NUMBER h r4EvissON NUMBER c PACKAGE IDENTIFICATION NUMBER . PAGE NUMBER e. TOTAL N'JM.tR PAGES 5362 4 USA /5367/RI i 1 9 [ PREAMBLE b
.. ini.c.ninc.i. i.i u.o io certivy in t in. p.cm.smo no content o crib.a en item s beio . meets in..ppuc.bi. f.iy stano.ra. t fortn in riti.io. coo. [_
of F.o.ral Regulations, P.ft 71, *P.ck.ging .nd Tr.nsportation of R.dio.ctiv. Mat.nai." (
- b. ini. conific.i. oo.. noi r.u... in. con.igno,irom compn.nc. . in .ny r quir.m.ni of in. r.aui.i on. or in. u s. o.g.rimoni or Tr n. port tion or ain r t.
I-
.ppnc.bi. r.aui.iory .a.nc . inciuoina m. go..rnm.ni or any country mrouan or into -nicn ine p caso. iii be iranspon.a.
L [ L
- s. rNis,gRgigges
, igoN THE Basis or A sarErv ANAtvsis, reg,v,o,r,1,,geggaEg,ogo4 gen, tic,4,rg,, [
U.S. Department of Agriculture U.S. Department of Agriculture application f Agricultural Research Service October 17, 1980, as supplemented. [ ' Radiological Safety Staff L 6303 Ivy Lane ' [ Greenbelt, MD 20770 ' I 71-5362
+ c. DOCKET NUMBER f I
. coNDmoN . .
ini. conific.t. i. cod,non.i upon tuiviinng in. r.quir.m.nt of 5o cFR P.rt 7i, .. .ppnc.bl., .nd tn conditions .p.cife.d b.iow.
- s. ,' I (a) Packaging I ,
, L (1) tiodel Noi: 'Natick Irradiator I I
4 l (2) Description , [
'J s r The package is a cylindrical,' steel-encased, lead-filled weldment 29-3/4" 00 by 58" high, enclosed in. a double-walled' impact' and fire shield (overpack) f .
57" by 45" by 90"..high mountedfonia pallet 57" by 45"; The stepped cavity is f l 9.56" ID by 8-1/4.", 12" ID by;27-1/2" and 20" ID by 11-5/8". The source { !' holder (drawer assembly);is 9.48":0D'by 46.625" with'9-1/2" shielding on i bottom and 12-1/8" on top. A' lea (shielded cask insert assembly 20" OD by b 9.52" ID by 12.12" is installed!at the top of the. cask and the entire
^
assembly is held in place with a 1"; thickisteel lid secured with twelve,1" [ bolts. A cask.~ drain line is sealed with'a pipe plug. A 39" OD laminated f plywood plug fills the space between the top of the cask and the overpack. [ Plywood will be positioned around the circumference of the irradiator for I i support. The cask weighs 16,000 lbs. L L (3) Drawings L i t [ The packaging is constructed in accordance with Lockheed Nuclear Products [ , Drawing Nos. 442-2093, Rev. O, 442-2094, Rev. O, 442-2096, Rev. 0; 442-2098, l ! Rev. 0; 442-3002, Rev. 0; and U.S. Army Natick Research and Development L i Laboratories Drawing No. FE-81-16, Rev. O. I i' I ( I ! l l I f C ( l 6 Y {- I t 22
----------------------------------------------yy------i, l
1 j
u.s Nucuan acoutATony couuission
"""'" cowomous (continued, l t I
Page 2 - Certificate No. 5362 - Revision No. 4 - Docket No. 71-5362 l l , I I
- 5. (b) Contents l I
(1) Type and form of material e I Cesium-137 sources meeting requirements for special form radioactive I material. l (2) Maximum quantity of material per package l l I 250,000 Ci. I
- 6. 'In addition to the requirem t hubpakG-p CFR Part 71, each package shall be maintained, operated dpr red for shipm ccordance with the operating .l procedures and mainten 4 rogram in supplement tid ay 21, 1992.
, 7. The package authori bythiscertificateisherebyaphvedforuseunderthe i l general license p@sions of 10 CFR 571.12. ,,$
- 8. Expiration date anuar,y ., 2000.
/* ,7,g /l l
y f, y- 6@) - ~1 ! L REFERENC S- 5 O I - j Y to: ap he ( .Zw1L)0cto[be]r on dated.
]
17',f l980 I N
.S. %
Department of p ricult g,$ 199 Supplements dated: htobe , b 1'9 k. h [ h C LJ ..
^-
(NLATORY COMMISSION I M P*JELie F0 E :D l y 6 Q/ W' 4'u$0CLEARv'
,1 ,
I I 4h y M h. S Ca s R.gChaQell,SectionLeader l I I I I CpifcationSection ! ,' *S rage and Transport Systems Branch l Division of Industrial and ;j i. l FEB 141995 l I Date l I i i I i i I I I I I I I I I I I I i r I I h I N I I i i 23 , 1
p_____________________________________________ _ _________ l s
*> U.S. NUCLEAR REGULATORY COSAGAISSION I s*ocran enc rosim sie CERTIFICATE OF COMPLIANCE I I
p i . CERTariCATE NUMBER FOR RADIOACTIVE MATERIALS PACKAGES ti REVISION NUMBER c PACILAGE IDENTIFICATION NUMBER d PAGE NUMBER ~e . TOT AL NUMBER PAGi5 I 6 5450 33 USA /5450/AF ' 1 7 I I t enE4ustE l' I
- a. This certificate is issued to certsfy inat the packaging and contents desenbod in item 5 below, meets the applicable safety standards set fortn in Title 10, Code l of Federal Regulations. Part 71, Packaging and Transportation of Radioactive Material? l l l
- b. Tnis cerieficate does not rei .< tne consignor from compiiance with any requiremer3: of tne reguistions of the u.s. Department of Transportation or other ja I
appi cabie reguistory agencies. inciuding ine government of any country tnrouan or into wn cn the package wise be transported I i 1 I I l a 1wisgn,ri,rgca,rys ssg rsE sasis or a sarErv amatysis,negn,1 or r,sge,4ga,oEggagon
, apge,4gou I
I I Westinghouse Electric Corporation Westinghouse Electric Corporation i I P.O. Box 355 I I Pittsburgh, PA 15230 application dated December 20, 1985, I r3 as_) supplemented. I I - t - 1 f t \xE,
'C P.(ooc I T '.uUueEa" ' - 4 I
s 4MM I i I I I 4 cowomous m v 4. This certificate is conditional upon fulfillingghe)equ6r6ments of 10 CFR Part 71, as applicable, and the conditions specified below. l I 5-Q - Q l l (a) Packaging 'O ,
- -p/ l i DJ G.2.N Zr ^ i i
I (1) Model Nds,: RCC, RCCt1 RCC 3 I us ) RandRCC-4[- a ; - (') r l I DescriptIn l C (2) I I I L p (5, y(.e[ w( f
, j g Steel f'ue] element cradle Tssemblysconsiktingofastrongbackand l l adjustable fuefle']ement <clampjn I I
I steel outer contMner;by sheapm(olints'.hssembly, Neutron;absorbir plates shockare mounted to a 14-g 1 required (for the' ennte I l lbs. , RCC ;l)and RCCJ3%ntsMs' 7:200;1b'sSand spe'ci RCC-4 fie'd. Gross'lbs. is 81400 weight;for the RCC is 6,3 s p' < .s , l l l (3) Drawings [j [s Dj/ (,.s ! Thepackagings[/a9 constructed in,O l I accordance Wjth the followin) I I Westinghouse Electric Corporation Drawipg No't.: I l l For the RCC packaging: yT fI 4n Jr % rRCCL002, Sheets 1 through 3, Rev. 2. l i For the RCC-1 packaging: i RCCL102, Sheets 1 through 3, Rev. 2. l l For the RCC-3 packaging: RCCL302, Sheets 1 through 3, Rev. 2. I I For the RCC-4 packaging: RCCL402, Sheet 1, Rev. 3; Sheets 2 I l through 3, Rev. 2. l l l (4) Fuel rod container reinforced 13-gauge steel box constructed in accordance l i i { I with Westinghouse Electric Corporation Drawing No. C5650D55, Rev. 7. I I I I (5) Dimensions and placement of neutron absorber plates in accordance with I unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated i 2/14/89. l 1 i l
- l. l l l l l l l l l l l l l l I l I
i 24 l
l CONDITIONS (continued) fPage2-CertificateNo.5450-RevisionN 71-5450 g i i I 5.(b) Contents l I (1) Type and form of material I , (i) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel I elements. Two neutron absorber plates consisting of 0.19" thick, I ' full length stainless steel containing 1.3% minimum boron or 0.19" I l thick 0FHC copper are required between fuel elements of the following lg l I specifications: - g , 14x14 15x15 14x14 15x15 17x17 16x16 14x14 I I Zr Zr SST SST Zr Zr Zr I I IyAq Clad Glad Clad Clad Clad Pellet diameter 0.344- [ 0.308- g (nom),in 0.367 0.384 0. p 0.322 4 0.322 0.3805 1 ! QV367 Rod diameter (nom), in y 0.400-0.422 0.422 0.422 0.422
.360-374 0.374 0.44 1
I I i Maximum fuel length, in N 44 144 120 209 gg., 144 144 l Maximum rods / \ y element D \1 204 180 26 Q 235 176 I I Maximum cross k E section, @- N"l'I'
'g4 O I (nom), in sq 7,
? ~
L [h k # ; .' 8.4 7.8 7.98 l Maximum U-235/ } - element, kg g (d i .- i e 9p ' U .117. y % + 8" i g 1 2 16. (1 "L) 16.6 19.0 g I h p . s ( 'L) ; Maximum U-235 M sl % 4.0 D C Yfp.65 4.0 3.85
)
enrichment, w/o f f 5 ed fuel elements contained I (ii) Uranium dioxh as Zircalcy i clad Twounkrad neutron absorber plates I within the Model RC -4 n i consisting of 0.1 th, hack teel are required between fuel elements of the following spec ications: l i l 17x17 l l'
.Tygg ZL_C_ lad l
Pellet diameter, in 0.308 - 0.322 l Rod diameter, in 0.360 - 0.374 l
; Maximum fuel length, in 168 i 264 1 Maximum rods / element Maximum cross section (nom) in sq 8.4 1 Maximum U-235/ element, kg 19.3 i Maximum U-235 enrichment, w/o 3.55 i i
I I I I l 2s g
r
----------------------a----------------------------,
""" U.S. NUCLEAR REGW.ATORY COthielSS40N t m CONDITIONS (continued)
Page 3 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 I l , I
,5.(b) (1) Type and form of material (continued) l l
l i I (iii) Uranium dioxide as Zircaloy clad unirradiated fuel elements. Two ', 1 I neutron absorber plates consisting of carbon steel, 0.035 inches in n I l thickness, a withg-Gd total of 0.054 a cermet 0 /cm Ggo[or both sides of the plate, arecoating affixe i 2 l required between fuel eiements of the following specifications: , i 14x14 15x15 14x14 15x15 17x17 17x17 16x16 16x16 I n I Zr Zr SST SST Zr Zr Zr Zr I I l Iypa [lg_ C1ad C1ad [ lad _ C1ad C1ad C1ad C1ad l l i Pellet diameter (nom),in 0.344-0.367 0 46 388 g- hp.322 0.308 0.322 0.325 I ' l Rod diameter 0.400 \ b Q !gl I' (nom),in 0.422 0.422 0.422h07422 0.3r/ p 0.360 0.374 0.382 I I l Maximum fuel length, in Q 144 120 120 168 k68 144 150 (E 18 I i Maximum rods / 'M i I i element ( dyB0 D Q 4 4 180 204 6hm 2f/ 235 236 d Maximum cross ll I section b~ '+ C I 7.b (nom), in sq b 7.8 l [ .
;4 8.4 7.8 7.98 h MaximumU-235/q r- 4
^"(J q(7175 l E ,
s element, kg 22.1 50
. 19. 20.7 21.1 h 0t yll44. L (14 ) lyl (f) y"e 2,% ' ) 23 p )
y i l
$g Av Maximum U-235 0 o'4 1
(' # ) (IERSL % lI
;l l
enrichment, w/o O g '
!,O.g I^ J 7 4C3) 5.0 5.0 i
[ (BMI{
) a '
Ilpa . ) Q I I h+* *+ i Pellet diameter R am er l (nom),in 0.422 i Maximum fuel I length, in 141.8 I ; Rods / element 208 I ' Maximum cross I section, (nom), l in sq 8.5 g Maximum U-235/ I element, kg 17.8 i Maximum U-235 I enrichment, w/o 3.95 l I t I ! l ! i I a i 1 26
---------___________________________________________,l t I
. - _ ._ - .- - ~ - _. _ _ _
______________________________________________________,l conomows (continvec u.s.nucteAn neouurony commission , "m"C'*""*
- I i
Page 4 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 I I l l
, 5.(b) (1) Continued l l i Uranium dioxide as Zircaloy clad unirradiated fuel elements l l ! (iv) containing a minimum of 48 IFBA rods and 25 Instrument / Guide tubes I I I
' I per specification and loading pattern described in Westinghouse I Two neutron absorber plates l drawing SKA-89044, Sheet 1, Rev. 2. consisting of carbon steel, 0.035 inches in thickness, with 4 mils of j g s Gd230 (0.02 gm-Gd 23 0 /cm ) affixed to each side of the plate are y p I required between fuel elements of the following specifications: l llI 17 x 17 I Zr Clad I Iypa l 0.308 (n ll I Rod er
, in n 0.360 lII N
I um fuel V l l ength, in 7 +$4 168 l )' gxiintim - s/ g a I kax ect on n C" Ma h O j
- elegent **' , p 22.5 (144"L) l b Mininidst Z ~
e
/"
, 48 I q
(f)MiniridgA$sse + bw // 108 I I trB leng , ' 'fn Fila 4'
% I I i; , ~
C ], ximum,Q Z3) M q g) l g enrichpentigw/ , Q 4.85 uel elements. Two l Uranium de as Zirc unirradi ; (v) r plates consisting of ca stpel0.035inchesin I i ! I neutron a I I thickness, 4 irils of Gd 0 03 /cm ) affixed to each sideoftheplate)re r q /(0.02qm-G$ fu 1 elements of the following l l l specification: -
.g a !
I 17 x 17 l
- i Zr Clad l l
l Iypa 1 l l f Pellet diameter l l l (nom),in 0.308 g l Rod diameter (nom), in 0.360 I , i 168 II i Maximum fuel length, in I 264 I Maximum rods / element I Maximum cross section (nom), in sq 8.4 l g Maximum U-235/ element, kg 22.5 (144"L) ; g Maximum U-235 enrichment, w/o 4.85 i l l g y l 4 i I a I l 27 l
CONDITlONS (continued) Page 5 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 I 5 I g'
,5.(b) (1) Continued I R I q g (vi) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel rods N of the following specifications: i I
N N I SST Zr Zr Zr Zr Zr I l lypg C1ad fla.d C1ad [ lad [la.d sliLd l 4 l Pellet diameter 0.344- 0.308- l i (nom), in 0.384 0.367 0.322 g l 0.322 0.3805 0.325 I Rod diameter, 0.400- 0.360-lj' in I 0.422 0.422 0.374 0.374 0.44 0.382 g Fuel length (max), l i in 0' i i 4 ) 68 144 144 150 i I U-735 enrichment (max), w/o hQ R bb[]Q T g l N Note (1) y 4.0 4.0 3.65p .0 3.85 --- 1 I l g Note (2) Note (3) 4.2 4.2 4.3 3 --- 4.2 j g) W 3.55m --- --- l !, i Notes: (s ' A 'l I L (1)Twdwutronabic laf[cShs'sq 'if 0.19-1 thick, full I I le rh stainleis' c46taiding 1 I th t 0FHC opper ge4' tired-b I (minimum) on or 0.19-inch ghe od bo E OY '.t r 'c )+ - J f ,f,' l l ( (2) Twqgutrdit sor eg pf ll thinness, mT c f c p g nimum' (carbon el,2 035 inch in 0 l Ni pla r gm 0 /cm ) affixed to I eachgdeo t re r l be the boxes. 1 (3)Twondonab$ lateIoksis s f 0.1 ch thick carbon steel a equired !se s. y tgrod (vii) Un rradiated, uran h dio ide, zircaloy cl fu elements, with annular l pellets at the top and og ends ofj,he tive fuel length. Two neutron g absorber plates consisting o Wca7Rin F mel, 0.035 inches in thickness, with l q a cerme . i 23 coating affixed to each side providing a total of 0.054 g-R I Gd 23 0 /cm} Gd for both 0sides of the plate, are required between fuel elements. I i I The fuel assemblies shall be held in place by at least 7 clamping frame i arms. Specifications for the fuel elements are as follows: j Iygg 14x14 14x14 CE-1 l I Pellet diameter (nom), in 0.3444 0.3765 I , I I Annular pellet inner diameter (nom), in 0.172 0.183 I ) l Rod diameter (nom), in 0.4000 0.4400 q Maximum active fuel length (nom), in 144 136.25 l a Solid pellet stack length, in 132 122.65 y g l Annular pellet stack length at the top and bottom ends of the active fuel length, in I 6 6.8 i Rods / element 179 176 I l Maximum cross section, (nom), in sq . 7.8 8.110 ' Maximum U-235/ element, kg l lI Maximum U-235 enrichment, w/o 18.1 5.0 18.6 4.8 l i
.I 28
-- - - = . - -_ - - -_ - _- - . - - - . .
P u.s. Noctsan neoutATony consesissioN me " " cowomows (continued, on I Page 6 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 l l l 4
- l
, 5. (b) (2) Maximum quantity of material per package l l I 1
i (i) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), i I 5(b)(1)(iii), 5(b)(1)(iv), and 5(b)(1)(vii): g I i r Two fuel elements l l l (ii) For the contents described in 5(b)(1)(v): l ' l 1 ' u ls One fuel element I I l (iii) For the contents described in 5(b)(1)(vi): Twoinner,copbrsf t b g ot more than 80 kilograms ,l ! l g l U-235 gb I (c) Transport Inde Criticality Control Minimumtrankrtindextobeshownon riticality control:
-,3
/
$04 8 y label for glea i I more than an i 6. Fuel rods must losely% edsin the fuel c . ' ainer o I 4 loaded rod containers I i equivalent met to-metal I l' mustbefittedpthaminim(q%eTatf57/P u (hr , equal ated blocks f which the noncombustible P>rtion pf the ke @u lby phich y are secured l l b 'an e ' valent metal-to-ained on' t g l 4 '
l r mustassureth(g-therods) metal square la ce h~ art W ~Si .. '.J o ', p I ngjtire % y, l ;; l , ee ed in wi unsealed, I I 7. Each fuel assembi shea $ i m S zs ys' t ' polyethyleneshebmus which intjLk ends o6rJhe fuel assembly. l l The ends of the sluhrth must> no xbe Wt 'in any gapner that would y prevent the flow of quids int >o he thed fg t assembly. Alternatively, the fuk 4embly may be enclosed in ongated plastic bag or i ( l I I sheath along its full lefigth. At the bottom en of fuel assembly, the bag willbecutofforfoldedbacpoa;sureth ten folding entire cross section of the l l ,1 is used, the portion of lower end of the assembly is urobshc$. i l ; i g the sheath that is folded back will be cinched with tape near its end to hold it i i i i in place, and the length will be such that when the assembly is loaded in the I i l- packaging, the folded sheath will be clamped in place in at least two grid I l I locations. The top end of the bag may be gathered together and taped closed. , j However, the top end then will be slit on all four sides. The slits will run l l perpendicular to the axis of the assembly and will extend the inner distance y g between the top nozzle pads and spring clamps (approximately 60% of the length of l i each side). The slits will be made in a plane near that formed by the top of the [ pads and clamps. l Use of packaging fabricated after February 28, 1986, is not authorized. l h8. I El The gross weight must not exceed 6,300 pounds for the RCC packaging, 7,200 pounds i p 9. for the RCC-1 and RCC-3 packagings, and 8,400 pounds for the RCC-4 packaging. l i l 1 29 l l
l l anc coms =
- cONDmONS (continued) 8' " **'"
l Page 7 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 1 1 i i I l , 10. In addition to the requirements of Subpart G of 10 CFR Part 71: I l i (a) The package must be maintained in accordance with the maintenance I i i i procedures submitted with Westinghouse supplements dated June 20, September I 16, and September 19, 1991. i I 1 I l (b) The package must be prepared for shipment and operated in accordance with l the operating procedures submitted with Westinghouse supplements dated June ; 20, September 16, and September 19, 1991. g
- 11. i I The package authorized by this certificate is hereby approved for use under the lf i
I general license provisions of 10 CFR $71.12. I
.REGg R
f 12. Expiration date: September 40, l h REFERENCES ip Westinghouse Electric Cor tion application dated December l 985. j Supplements dated: Ap l 28;'Jul 1, 21, 1986; January (f$ruad14, April 18, ., i October 5, and Novemb , 1969 ch 5, April 17,, i i 19, and September 24, 1; Fe , September 16, September i l r. 1,Mgh21,gh z , ' 27, 199 ( ) I i DepartmentofEnergyl~plementda & Mar ,[158} 1
\
}q, m v I g h0R ,g MA COMMISSION l
oM %ptWJhfim0,Try NimVi&g,tpr l i D s, Dirq > // 'a Spent 'FubD P Off@e\bFNuclear Mat al t Offi
@q Safety y
i I i 7 and~ Safeguards p Date: 3 M 4b y M i I l l l I
^
I I I I I ! I I s I I I I I I i l i I i
7_ l _ rones _ _sie___ __ ________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _u.s. NUCLEAR REGULA l senc I I *=> CERTIFICATE OF COMPLIANCE I so cra n FOR RADIOACTIVE MATERIALS PACKAGES I I ti REVISION NUMBER c PACKAGE 4 DENT 4FiCATION NUMBEA . PAGE NUMBER 's. TOTAL NUMBER PAGCE i a cENTIFICATE NUMBER l 5580 6 USA /5580/B( )F 1 2 l l PRE *ustE l . Tni. e.rtnic.i. c u.o to c.nity m.iin. p.ck.ging .no cont.nt.o cnt.o in ii.m s e.iUw. m t. in. ppiec.oi. t.ty stano.ro. iiorin in Titi. io. coo. llI g i of r.o.rai n.gui.tions. Part Ti. e.ckaging ano Tran.portation of n.oioactiv. u.i.n i.- I b. ini. c ri.e. cat. oo.. not reheve ine consignor from comph nce with any requir.m.nt of in. reguistions of ine u.s. o.partm nt of Tren portation or orner I N I appucsoi. regui iory .g.ncies, inciuoing the government of any country inrougn or enio wnien in. peck g. wiii b. transport.o. I I l I I T OF THE G SG O P CA S TygTl,FgC,AyS;SSg THE BASIS OF A SAFETY ANALYSIS REP I I I I U.S Department of Energy Safety Analysis Report for S5W Power Unit Division of Naval Reactors shipping container dated August 9, 1968, l l Washington, DC 20585 ,a,s . amended. i I 1
- S n h c(J f I t C 3 ?oOcxET NUusER G1-5580 l I 4 cONomONS s tj %Q , l Thi. c ttificate i. conditional upon ,fulfilhngges.quirements of 10 CFR Peri 71, . apphcabl., and th. corLAltion. .p.cifi.d b. low.
I 1 s. Q Q t* l I l Cg ' / I (a) Packaging ; . 4 I I I (1) ModelNo[&S5WPowerUnit K-%e r
/ y[
() l I 1 a s ; i J ry}s l f (2) Descript g~ on
%y Q tj/ c.;-
yf i i r > I i The 55W Power Oqttcshi M ' *,ingocontaip r i I I to,sh p and store ewn,y(PUSC) naval' reactor isLalcontitner power units. The PUSC and support I I assembly' is compriped designed, ess'e'n tis Jy ofdthW s1 jor assemblies: (1) the outer ' ame, (2) I the innerkffame,' ahf 3)4he,'s ppig[ container'. During shipment, the l l shipping containerA bbitsd,t the snher; frame in a>orizontal position. i i i Two trunnions'welde'd tolthe(piddleise.ct,ioh'%f the spipping container support I i t tneans whereby the i I the lower end4f the container / hnd also ~ provide containercanbe'yotatedfromthe'Korizontal(@ p ,g,he,ing) attitude to thei I vertical (loading-tinloading) attitude in the(nper frame. The trunnions l I turn in trunnion base M hich are bolted " the inner frame. The inner frame , and shipping containe/Ereysuppecte by outer frame and pedestal through i l l 80 elastic shock mounts, eahh of wh(fch is secured to both the inner frame I andj i I l 1 outer frame. I I I Approximate dimensions of the three major assemblies of the PUSC are: l l shipping container: 95 inches diameter by 234 inches; Inner Frame: 109 i ! inches width by 52 inches height by 269 inches length; Outer Frame: 121 e i i inches width by 56 inches height by 236 inches length. Maximum weight of the i I I loaded PUSC is approximately 127,900 lbs. I I l (3) Drawings l l l i i l l The packaging is constructed in accordance with Westinghouse Electric I I I Corporation Drawing Nos. 936F963, Rev. 3 and 936F964, Rev. 2. I I I I I I I I I I I I I i I I l l 31 I ( l
nac ronn m ***""****" #** * '
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,l Page 2 - Certificate No. 5580 - Revision No. 6 - Docket No. 71-5580 l
l i 5. (b) Contents i l I I l (1) Type and form of material l l Unirradiated fuel assemblies of the following type, ! I - I i (i) S5W Core 4 power unit with control rods installed and secured in I j place by holddown mechanism. , l l (ii) S3G Core 3 power unit with control rods installed and secured in i place by holddown mechanism. l g i l I I (iii) DMC Power holddown Unit withgn@{rg(,10 mechabilA // stalled and secured in place by I I p I I l (2) Maximum qua of material per package [ l One fuel mbly as described in 5(b)(1)(i), 1)(ii),or i j 5(b)l)( I J I (c) Transport I for' lity Control -f I l t Minimum tr an port indef 4 QAop ^ b l l b sho Q g n 3. label for (lear critic ExpirationDateEDece
't;. Lt co 31
*Q }1[I . j:
ro
+
-?
100 i i i
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I - l% } [ l f l l Q ] # E l
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1 Safety Analysis Report S5W we 'Un ner,WG 1 I August 9, 1968; Addendu WAPD-0P(RJS mber 4,.p-0P(R)SA-820 1987. dated I I g e w Q g l Naval Reactors Supplements db : March 2,1992(G#92-033h ! k F Tg. NUCLEAR REGULATORY COMMISSION l p f Ac= s y ! William D. Travers, Director ' i Spent fuel Project Office ! I l I Office of Nuclear Material Safety I f 7 and Safeguards l , l Date: )i d % i ! I i I I I I . l I I I , I I 32
l g;wwwwwwwwwww2mwwwwwwwwwwwwwwwwwwwwwwwwwwwwww www i g NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION g m CERTIFICA~'E OF COMPLIANCE .
" " " R FOR RADIOACTIVE MATERIALS PACKAGES I a CLRTillCATE NUMBER b. REVISION NUMBLR c. PACKAGE IDENTil1 CATION NUMBER d. PAGE NUMBER e. TOTAL NUMrsER PAGES f 5607
- 2. PRE AMBLE 9 USA /5607/B( )F 1 3 W k
- a. His certificate is issued to certify that the packaging and contents descnbed in Item 5 below. meets the apphcable safety standards set forth in Title 10, N
Code of Federal Regulations, Part 71," Packaging and Transportation of Radioactne Material " k sl
- b. His certificate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other N
applicable regulatory agencies, includmg the government of any country throg.h or into which the package will be transpirted. 4 j re I 5
- d i THIS CLRTil1CATE IS ISSULD ON THE B ASIS OF A SAIT.TY AN ALYSIS REPORT OF 111E PACK AGE DESIGN OR APPLICATION
- o. ISSUED TO (Nume and Addern) b. TIT 11 AND IDEfiTIFICATION OF Rt PORT OR APPLICATION: k B E
! # U.S. Department of Energy T-2 Shipping Package, Safety Analysis ( j B Washington, DC 20585 Report, Draft: April 1980, E i B as supplemented. g B W l B
- c. DOCKET NUMBER 71-5607 g 4 CONDITIONS g h
This certificate is conditional upon fulfilling the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. g 9
$ i (
l 4 9 ! Packaging g 9 (a) B d p (1) Model No.: T-2 g 9 5 g (2) Description g M d a Packaging for irradiated reactor fuel and components consisting of a lead g E encased in steel cask, removable containment vessel insert and shipping g g case. g i al y ! j! The cask is a double-walled steel circular cylinder with thickened g l l shielding in the. center portion. The central cavity is 6.065 inches in y l gl a diameter by 100 inches long. The lead shielding is 8.0 inches thick g i j along a 45-inch center section reduced to 4.2 inches at each 36-inch end section. The containment vessel is positioned within the cask. Cask y g closure is accomplished by a gasketed and bolted steel plug. The cask is l , y a enclosed in the shipping case which is 36 inches in diameter by 133 g
- inches long welded to a 4-foot by 6-foot steel pallet. The maximum weight of the packaging is 18,400 pounds. l (3) Drawings l h
H N 8 (i) The shipping case is constructed in accordance with DuPont Drawing E 5 Nos.: W716539, Rev. 0; 180191, Rev. 1; 180192, Rev. 0; 180193, Rev. E
- 5) 1; 180194, Rev. 0; 180197, Rev. 0; W716538, Rev. 0; 180195, Rev. 0; 5 180196, Rev. 0; and 180089, Rev. O. W W
E 5 (ii) The cask is constructed in accordance with General Electric Drawing 8
- Nos.: 919D755, Rev. 0; 135C5202, Rev.0; 153F966, Rev. 0; and N'
i s 106D3721, Rev. 0; or it is constructed in accordance with DuPont
*j Drawing Nos.: W239534, Rev. 2*; 147214, Rev.15; 147215, Rev. 2*; W s)i and 147216, Rev. 1. U N
R I d' B
! I 01 1
&l *l As provided in the April 12, 1983, supplement l
f
- b irm . m m m m m m m m mm.m.1m m m m m1m m m1.u.u.1m m ma 33 m 1 mmmmmmmmmm 1
i
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g (NRC CONumoNs(n=rm c4; 3-96)FORM 618A U.S. NUCLEAR REGULATORY COMMISSION g i i p Page 2 - Certificate No. 5607 - Revision No. 9 - Docket No. 71-5607 E; h bl (l Ei n 5.(a) (3) Drawings (Continued) B 4l di 9 (iii) The ANL insert is constructed in accordance with Argonne National E g Laboratory Drawing Nos.: WO147-0227-DD, Rev 7; W0147-0228-DD, Rev. E g 6; WO147-0229-DC, Rev. 6; WO147-0231-DD, Rev. 3; WO147-0234-DC, 3 Rev. 4; and WO147-0312-DE, Rev. 2. (l' E s E g (iv) The TREAT Vessel insert is constructed in accordance with g< g Westinghouse Hanford Company Drawing Nos.: H-3-39082, Sheets 1 ' y through 4 and 6, Rev. O, and Sheet 5, Rev. 1; H-3-36134, Sheet 1, ( g g Rev. 3 and Sheet 2, Rev. 2; and H-3-36823, Sheet 1, Rev. I and g g Sheets 2 through 4, Rev. O. g b g (b) Contents Nl g (1) Type and form of material l l (i) Irradiated clad fuel in the form of solid . metal, oxides, nitrides,
, and carbides of uranium, plutonium, or mixed uranium-plutonium l g ,
N contained within the ANL insert or TREAT Vessel insert. The clad i fuel: may contain small quantities of Na or NaK. The minimum 9 cooling time must be no less than 150 days. l 8 8 (ii) Irradiated clad-fuel pins ~of uranium dioxide enriched to up to 3.0 N i
# w/o in U-235 contained within the ANL insert orl TREAT vessel U b
insert. Avera I per kilogram. geThe exposure of _fuel clad fuel maynotcontain to exceed small18quantities megawattofdays Na or
# Nl NaK. The minimum cooling time must.be no less'than 90 days. E' N
4 B N (iii) Irradiated re' actor components' held within the container shown in Nl Drawing No. WO147-0234-DC, Rev. 4. E B 4 < B (2) Maximum quantity of material per package. E B E B Internal decay heat not to exceed 208 watts, an'd: E I B E B (i) For the material described in 5(b)(1)(i), fissile material not to a B exceed 1.71 kg. 6 B E D (ii) For the material described in 5(b)(1)(ii), fissile material (U-235) N N pot to exceed 300 grams. N B E D (c) Transport Injex for Criticality Control 4 B E B For the contents described in 5(b)(1)(i) W D and 5(b)(1)(ii), and limited in 5(b)(2)(i) W D and 5(b)(2)(ii): E D p E < Minimum transport index to be shown on E B label for nuclear criticality control: 0.4 E B i Ell B Ej Ei B E! n; E l 34 I bammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmad
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> d' p, Page 3 - Certificate No. 5607 - Revision No. 9 - Docket No. 71-5607 (!
I d' Bj E W i N ! n 6. The contents must be shipped dry. When loaded underwater, the package must be E p dried using Consumer Power Company's procedure, "T-2 Cask Liner Assembly Drying g l l 3, Procedure," Proc. No. EE&T-Cl2, Rev. 1, 11/12/81. g E s ! 3 7. The ANL Insert and TREAT Vessel insert must be leak tested prior to first use g g and annually thereafter in accordance with the procedures specified in Argonne g National Laboratories Document No. WOl95-0054-ES-00. g, l 3 l W W l a 8. Prior to each shipment, the package must be leak tested in accordance with g l j procedures specified in Appendix A to HFEF/N OMM 6202, Rev. 2, March 17, 1981. g W W l g 9. In addition to the requirements of Subpart G of 10 CFR Part 71 and the other g i
, conditions of this certificate: g l (a) The package shall be operated and prepared.for shipment in accordance with the Operating Procedures in Chapter 7 of the application, as lg l
9 supplemented; and g (b) The package must be maintained in accordance with the Maintenance Program of Chapter 8 of the application, as supplemented. l g l ,
- 10. The package authorized by this certificate is hereby approved for use under the U
5 general license provisions of 10 CFR 671.12. l U I l f 11. Expiration date: May 31, 1998. a W 9 REFERENCES
-l W 6 N
5 DuPont Safety Analysis Report, Draft April'1980. N 9 < E 5 Department of Energy supplements dated: February'll, April 8 and 20, 1982; April 12, i 5 1983; February 26, 1992; and February 3, 1993. d FOR THE U.S. NUCLEAR REGULATORY COMMISSICN 4 B N i s r # d/ b (" William D. Travers, Director E E Bl Spent Fuel Project Office d i
$l B
Office of Nuclear Material Safety G B , and Safeguards W f N B l B- Date: $ A.f n E d B I p E a l m ! N B ' W s R 9 El B N i W s' G W W 9 U
$ 35
@risi m a m m a m a m a m m m m m m m m m m m m m m m m m m m m m m m m
f_W_W_w w w w w w w w w w w w w w in7 ser Tar Tar ser Tar Ter Tar Tar Tar lar Tar Tar Tar Tar Tar Tar ist Tsr 137 ur ur Tar Tar Ta E" w cnin CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL.S PACKAGES $ y L a CLRTinCATE NUMBLN b. Ri VISION NUMBI R c PACKAGF IDlJ4T1HCATION NL MH1 R Ri d PAGE NL'MHLR e. TOTAL NUMHl.R PAGLS l g 5740 5 USA /5740/B( ) 1 3 gl
- 2. PHEA MBLE k
- a. This ceruficate is issued to certify that the packaging and contents descnbed in item $ belon, meets the appiscable WJ.y sianJards set forth in Title 10.
Code of Federal Regulanons. Part 71 " Packaging and Transportation of Radioactive Malenal" kl
${ k l
- b. This ccmficate does not relieve the consignor from compliance with any requirernent of the regulations of the U.S. Department of Transportauon or other N applicable regulatory agencies. includmg the government of any country through or into which the package wtil be transported.
$j R)I s
5l 1 Tms etRTinCATE IS ISSULD ON THE Hb TITLE
. IssULDTorwme.asAss,co, AsisANDIDENTIMCATION OF A S AllTY AN ALYSIS REPORT OF THE PACK AGE DLS OF REPORT OR APPLICATION. k'l l h; U.S. Department of Energy Safety Analysis Report for Packaging (SARP) of !
gl Washington, DC 20585 the Oak Ridge National Laboratory TRU Californium 5 y Shipping Container, August 7,1981, Rev. of 2l d 8 Report No. ORNL-5409/R1, as supplemented. !l
% c. DOCKET NUMBER 71-5740 5 g
h a CONDITIONS g
$ This certificate is conditional upon fulfilling the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. g $ 5.
g
* (a) Packaging E 9
E 5 (1) Model No.: ORNL TRU Californium Shipping Container E b E (2) Description i 5 E 5 A 304L stainless steel encased concrete shipping cask. The outer shell n 51 consists of two, 1/2-inch thick, 66-inch diameter hemispherical heads joined ( B by a 6-inch cylindrical section. The cylindrical cavity has a ( s 1-inch thick stainless steel wall and is 3 inches in diameter x 6 inches long. (
${j Shielding consists of 30 inches of Blackburn Limonite concrete having a (
s< density of approximately 175 lb/ft3. Upper and lower level n i ball valves located at the end of concrete filled plugs define, isolate, and g B seal the cavity. Both of these plugs have 0-ring seals, are bolted in place gr i and are protected with a gasketed cover plate. Fusible plugs are located in g g the cover plates and the shell. g B 4 s' The top ball valve and plug may be replaced by other plugs for multiple source a b e shipments. Sources are contained in special form inner containers. j s W The cask is mounted onto a 1-inch thick steel base plate by eight steel 2-1/2 i g inch NPS Schedule 40 pipe struts. The cask is transported on a special i p trailer. The package gross weight is 23,500 pounds. i 5 B 5 n! e ~ s,i 5 n l B El l nlj 8 si 5l n a l L hi l B, l j e! E 1 W p! g 1 36 l! i h a 2airm KIirisfr rTara a m 2s_ wniUst m a m 2st m a m m 2ss m 2ss 2snigsUsp: 1 m a m 2:1 m m a m a m a m 2s, a m
l w w w w w w w W w w TEbh[5bhr W y w w w w w w It[Ur w w w w w w w w w y W y w w w w w w w w w g NRC FORM 618A CONDmoNs (omimads U.S. NUCLEAR REGULATORY COMMISSION g d a i 8' E j Page 2 - Certificate No. 5740 - Revision No. 5 - Docket No. 71-5740 e i N 1s n! E 8' 5. (a)(3) Drawing g i s
! The package and special trailer are constructed in accordance with Dak Ridge National Laboratory (ORNL) Drawing Nos.:
E E
? > 5 M-11230-EN-001-D Rev. 4 E
9 M-ll230-EN-002-D Rev. 0 5 M-ll230-EN-003-D Rev. 0 W N M-11230-EN-004-D Rev. 2 W 5 M-11230-EN-005-D Rev. 0 W B M-ll230-EN-006-D Rev. 0 E 9 M-11230-EN-007-D Rev. 0 ( s M-ll230-EN-008-D Rev. 1 E s M-ll230-EN-012-E Rev. 4 E 9 M-11230-EN-014-E Rev. 3 E i M-11230-EN-017-D Rev. 3' (
$ M-ll230-EN-018-E Rev. 0- _
E l s (Appendix A, August 7,1981 revision of ORNL-5409/R1, as supplemented.) W ) i i i q i s (b) Contents n G l gl (1) Type and form of material g s W i l y The contents consist of isotopes of" Americium (Am),; Curium (Cm), g l y Berkelium (Bk), Californium (Cf), Einsteinium (Es),-and Fermium (Fm) as a i y a solid (metal, oxide, oxysulfate, or dry salt), contained in capsule (s) g that meet the requirements of special ' form radioactive material. g (2) Maximum quantity of material 'per package - f for the contents describe'd.in 5(b)(1): , l Three (3) grams'and the maximum internal heat not to exceed 5 watts. l
- a j 6. The contents described in 5(b)(1) must be~ shipped in beal welded special form inner container as described in section 5.2.1 of the' application.
g g g
- 7. In addition to the requirements of Subpart~G of 10 CFR Part 71: l l
(i) Each packaging must be maintained in accordance with the supplement dated l y May 10, 1991; and g U 8 (11) The package must be prepared for shipment and operated in accordance with the supplement dated May 10, 1991. l l 8 .' A minimum of two lifting ribs shall be used to lift the package. l E l 8 9. The package authorized by this certificate is hereby approved for use under 8 general license provisions of 10 CFR 971.12. l
- 10. Expiration date: July 31, 2001. l, s
N , 5 N N E l Bf 37 I N} l Sammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm5 l
wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwI g CONDITIONS famtmwd> U.S. NUCLEAR REGULATORY COMMISSION g (NRC 3-es) FORM 618A Nl Page 3 - Certificate No. 5740 - Revision No. 5 - Docket No. 71-5740 E Sj 9 m B E I B E 2 6 B REFERENCES N B E 9 Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU E B Californium Shipping Container, August 7,1981, revision of Report No. ORNL-5409/RI. N B 4 nj Supplements dated: April 4, 1986; March 26, April 23, and May 10, 1991; June 4, 1992; E B and May 13, 1996. E B E E E B FOR THE U.S. NUCLEAR REGULATORY COMMISSION E B 6 5 William D. Travers, Director ( 5 Spent Fuel Project Office g 3 Office of Nuclear Material Safety g g and Safeguards g 9 Date: I O ' l W;
~
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$ NRC FORM 618 J (m) CERTIFICATE OF COMPLIANCE !i E !
' ' " FOR RADIOACTIVE MATERIAL.S PACKAGES s)j l. s. C1 RillICATE NUMBI R b REVISION NUMBLR c. PACKAGE IDLNTlHCATION NUMBER d PAGE NUMBER e. TOTAL NUMHER PAGE3 gl !
j 2 n ! ! f _E757 6 USA /5757/B( )F 1 k l $g I PRLAMBLL N k a. This certificate is issued to ceitify that the packaging and contents desenbed in item 5 below. meets the applicable safety standards set forth in Title !O. Code of f ederal Regulations. Part 71. " Packaging and Transportation of Radioactive Material." @ j $
- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other N
h applicable regulatory agencies, including the government of any country through or into which the package will be transported. f 6 h 3 3 THl$ CERTlHCATE IS ISSULD ON THE B ASIS OF A SAFETY AN ALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION $ g a ISSUED 10 f Mune and AddicuJ b. TITLE AND1DENTlHCATION OF REPORT OR APPLICATION. W l . U.S. Department of Energy Safety Analysis Report for S5W Refueling ( l , Division of Naval Reactors Source shipping container dated February 14, 1968 E I S' Washington, DC 20585 ( i ' g
- c. DOCKET NUMBLR 71-5757 g ,
9 g l N 4 CONDITIONS This certificate is conditional upon fulfilhng the requirements of 10 CIT ( Part 71, as applicable, and the conditions specified below. g l l $ g I f $ 5 I g l 5 (a) Packaging l s B i B (1) Model No.: S5W Refueling Source g ' g B Description g l 5 (2) g 3 The S5W Refueling Source shipping _ container consists of two structures, g one nested within the other, having an overall envelope of 5 feet, g g pl 5 inches diameter by 9 feet,.5-5/8 inches. length. The outer structure, g l $ the shipping container, is a ring of_ polyethylene 11-1/2 inches thick g i l a with an OD of 5. feet 4 inches and length of approximately 5 feet , 2 inches. The polyethylene is canned in a'1/2-inch thick carbon steel y s shell. The inner structure, the replacement and installation container, a N fits into the cavity of the outer _ structure. This' assembly consists of a l ig 6-1/2 inch'00, 7915/8_ inches long stainless central; tube, which is N 8 l a plugged at bath ends by machined stainless steel forging. Three cavities I i are machined'in the bottom end plug to contain the neutron source 8 j assemblies. A-jacket of lead, 6 inches thick, encircles the central tube and this innermost layer of shielding to attenuate the gamma radiation. E a 8 s A wall of polyethylene, 8-1/2 inches thick, surrounds the lead shield and I j is canned with a 1/2-inch thick carbon steel plate. Gross weight is g approximately 19,000 pounds. jJ (3) Drawings . 4 d The packaging is constructed in accordance with Westinghouse Electric ll Corporation Drawing Nos. 9050318, Rev. C; 905D315, Rev. F; and 9050285, E E h' 8 Rev. A. W B 4 N 6
- g 3 g W g 9
E 5 e s 5 5 E r B g B E ! $ 39 j K1m-~iiirfisTm KIsrisi m m m m m m musrm a m m m m m m m m m m m m m m m m m m m m
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,8 Page 2 - Certificate No. 5757 - Revision No. 6 - Docket No. 71-5757 E p! l '
g 5 W 5.(b) Contents N I E 8' Type and form of material B (1) E 4 8 Radium-Beryllium special form radioactive material neutron source. (1) 4 , R These sources may be either new or irradiated and have surface d l B contamination as a result of previous use. E ! E D (ii) Plutonium 238-Bery111um special form radioactive material neutron d B source. These-sources may be either new or irradiated and have a B surface contamination as a result of previous use. 4 8 4 5 (2) Maximum q'antity of material per package E : p m r ! g D (i) One, two, or three' neutron sources;as described in 5(b)(1)(1) and g b limited to attotal content of not more than 940 curies, with radium g R limited toyot more than 2.5 curies (gms) and total emission rate g , B' of 3.8 'x 10 n/sec. These sources are limited to a combined surface g 9 contamination of not more than an 2A quantity of radioactive g 5 material. ,4 g R s .... -
- l. g ;
p (ii) One,' two, or three neutron sources as" described in 5(b)(1)(ii) and g B limited to a;totalicontent g B pl emission rate of:1.48 x'10(of n/sec.c These notimore sources than are925 curies limited to a and tot g combined surfacescontamination'of not more thanzan2 A quantity of g , E radioactive material. 1 , y , p < 1 c , . 1 _. g g (c) Transport Index for Criticality Controle c < g g Minimumtranspoht.indexLto'beiskownon, g label for nuclear criticality control:1 0.4 lg g v. e ,
- v g g 9. The package authorized by this certificate is 'hereby approved for use under the g g general license provisions of 10 CFR 671.12.
g l 10. Expiration date: December 31, 1997. . f l t g REFERENCES ly Safety Analysis Report for S5W Refueling Source Shipping Container, WAPD-OP(R)S-2473 dated February 14, 1968. E [ l g Supplements: Bettis Atomic Power Laboratory letter WAPD-0P(R)C-474 dated December 22, 1975; and Naval Reactors letter G#92-03738, dated October 15, 1992. 8 , l g FOR THE U.S. NUCLEAR REGULATORY COMMISSION h - l g l y l I i 1111am D. Trav$rs, Director [M U 8 p/ Spent Fuel Project Office 8 g Office of Nuclear Material Safety 8 y g g and Safeguards y / / 8 l 40 W
$mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm# -
l
mac comm eis u.s. NuctsAn neoutATony coesasissioN l l ==> CERTIFICATE OF COMPLIANCE l so CFa n FOR RADIOACTIVE MATERIALS PACKAGES
! 1 a CERTIFICATE NUMBER D REVISION NUMBt.R s PACKAGE IDENTlHCATiON NUMBER d.PAGE NUMBER e. TOTAL NUMsER PAGES 5796 13 USA /5796/B(U) 1 2
- 2. PREAMBLE
- a. This certificate is issued to certify that the packagmg and contents desc.nbod in item $ below, meets the applicable saf ety standards set forth in Title 10, Code of Federal Regulations. Part 71,"Packagmg and Transportation of Radioactwo Materal"
- b. This certificate does not relieve the consignor from Compliance with any requiremer)t of the regulations of the U.S. Department of Transportation or other l f
applicable regulatory agencies, includmg the government of any country through or into which the package will be transported. l [
- 3. THIS CERTIFICATE 18 ISSUED ON THE BASIS OF A SAFETY ANALYSi8 REPORT OF THE PACKAGE DESIGN OR APPLICATION i s. ISSUED 70 theme stur eheast b. TITLE AND IDENTIFICATICW OF REPORT OR APPLICATION.
l Advanced Medical Systems Inc. Advanced Medical Systems, Inc. application l 121 North Eagle Street dated June 26, 1992, as supplemented. Geneva, OH 44041 . o , C i
- c. oOCxEr NUueER 71-5796 i
l e CONDITIONS . ,. l This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below. i
- 5 i sj O
l
- (a) Packaging C (1) Model Nos.: '181375 an'd 181361 '
(3 t (2) Description ~ , ,
- g,
,s Overpacki that provide impact and ~ thermal ~ protection for^ teletherapy head assemblies or source exchange assemblies. the cubical overpacks covered with ; l 16 guage steel panels. Reinforcing; steel straps and angles are welded l > together and' spaced' to limitithe openings between them-to less than 6
- inches. Ski'd. runners are provided to facilitate fork, lift usage. Dimensions of the Model No. 131375 are 43.5"Lix39.75"W x 41"H with a maximum gross ^
weight of 3,750, pounds. Dimensions of the Model nog 181361 are 39"L x l 34.25"W x 44.5*H with a maximum' gross weight of 4,000~ pounds. (3) Drawing / $' (i) The Model No. 181375' packaging is'c6nstructed in accordance with Advanced Medical Systems, Inc. Drawing Nos'. as specified in Section 1.3.1 (p 1-11) of the application. (ii) The Model No. 181361 packaging is constructed in accordance with Advanced Medical Systems, Inc. Drawing Nos. as specified in Section 1.3.2 (p 1-12) of the application. l l i 41 4 __________________________________=w-------_______.
y m m m m_mm m m m m mmm m m m m mm mm m m m m= A m = = = = = = = == = = == " ** =""= " ""*""9 lg CONDITIONS (continued) i Page 2 - Certificate No. 5796 - Revision No.13 - Docket No. 71-5796 'N I I I S. (b) Contents l l (1) Type and form of material q I g (1) Cobalt 60 sealed sources that meet the requirements of special I i i form radioactive material; or I N 8 l l (ii) Cesium 137 in the form of cesium chloride encapsulated in sealed y sources that meet the requirements of special form radioactive l y material. I j l I (2) Maximum quantity of material per package l-l (1) 13,680 curies of cobalt 60 with a radioactive decay heat load not
,' l 3 i toexceed200 - - . *watts;or([{p,,/
g i (ii) 2,200 curiesiof cesium 137 with"sat radioactive decay heat load not I l l i to exceed 17 watts. i # 'As I
, j, I
- 6. In addition to the regiJirements of Subpart G of 10 CFR kaft 71:
l - g l g . :, I i- (a) The packagesjmust'be operated and prepared for shipmenttin accordance with I i i the Operat{ng' Procedures of Chapter 7 of the; application., I wt . I l' (b) Each packaging must meet the Acceptance (Tests'and Maintenance program of g Chapter 8,0f the applicatiori. _.,,; , f: ips , y; l y
, g
! 7. Useofpackaging^ fabricated'a'fterAugust31N1986iisno'aut$rized. i t I I
8.
- 4 .9 l ( <
e' I I I The packages authorized-by, this c, ertifica! r
! >r"te are herebyfapprov?
ed for use under the 1 i general license provisions 1of.10.CFR 571.12. . .a- <,? 3
/
n m z: - , .~ I
,a
- 9. Expiration date: ' July 31, 1997.
g 7' 3j ,W g g i
's. . ~~ a ,,; . I I c, i REFERENCES V I
~
l l Advanced Medical Systems, Inc.< application dated June 26, 1992. g . t . . , , l g i Supplements dated: August 13 and October 15,a1992. l i 1 i i FOR THE U.S. NUCLEAR REGULATORY COMMISSION N I l i M Charles E. MacDonald, Chief a i Transportation Branch I I Division of Safeguards f l Date: MC16 N- and Transportation, NMSS h. g 4 [. i r I i I I f , i ( I f i C l l i l i [ i 42 I i
- = - - .. - - . - - - - . , _ _
l 4 unc ronu sw u.s. NUCLEAR REGULATORY COMMISSION
*au CERTIFICATE OF COMPLIANCE w co n FOR RADIOACTIVE MATERIAL.S PACKAGES t a CERTIFICATE NUMelER ti REVISION NUMBER c. PACKAGE IDENTIFICATaON NUMBER g PAGE NUMBER ~~ e . TOTAL NUMBER PAGES , 5797 11 USA /5797/B(U)F 1 3 . & PREAMBLE I
[ a. Vhis certificate es issued to certify that the packaging and contents described in item $ below, meets the apphcable safety standards set forth in Title 10. Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Matenal?
- b. This certificato does not rehove the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other apphcable regulatory agencies, includmg the governenent of any country through or into which the package will be transported.
- 3. THt W IFCAT SISSUE THE BASIS OF A SAFETY ANALYSib RE T OF THE KAGE E G O A CA U.S. Department of Energy U.S. Department of Energy Washington, DC 20585 application dated May 30, 1991, as supplemented. !
c % fh *, h,nC?!. i0 ( ~7}.$7$7 CKET NUMBER
~
j 4 CONDITONS g () 'Aj , i, .. Thb cottaficate is conditional upon ,fulfiHing equirements of 10 CFR Part 71, as apphcable, and the conshtions specified below. l 5
@ U (a) Packaging Cp ('s k.L i MG (1) Modelho.: Inne HFIR Unirradiated- Fuel, Element Shipping Container, and Q,
- Oute Unirradjate'd fuel Element Shipping Container j- V[I eg (2) Descr,iptiong .,- ( %
T r 1 hy(j('c
/
s+.
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C Paciriging ( k. %unirridiated;f,ipstle radioactive matirial as fuel elements lleactore(HFIR). The containers are right ciredlar for thecylHipisluyI'soto#p! with in auge ji1}s carbort steel-shell. The lid is atta'cKed to thf- nthser With ixteen>3/8-16xlfinch steel bolts. The steelVshell iFfilled withdtacked;-1 pinch hig,h,CDouglas fir plywood rings.YThe plywooda r i s formg h central cavityjwhich is lined with 1-inch thick polyphylene foani . f/p The packagihfor the inner HFIR fuel eT(ment has overall dimensions of 25inchesODbyjpinchesI;igh,,1ght. aJ cavity, and a 660 po $ g g s $ g 7/8-inch diameter by 30-1/4-inch
] The packaging for the outer HFIR fuel element has overall dimensions of 31.5 inches OD x 45.75 inches high, a 17-3/8-inch diameter by 31-1/8-inch deep cavity, and a 1,050 pound gross weight.
(3) Drawings I (i) The packaging for the inner HFIR fuel is constructed in accordance 1
) with Martin Marietta Energy Systems, Inc., Drawing Nos. l M-20978-EL-003E, Rev. C, and M-20978-EL-008E, Rev.B.
]
(ii) The packaging for the outer HFIR fuel is constructed in accordance l with Martin Marietta Energy Systems, Inc., Drawing Nos. l M-20978-EL-002E, Rev. C, and M-20978-EL-008E, Rev.B. [ I l 43
------------------------------------------..-----------n mac roa" U.S. NUCUEAR REGULATORY COMMISSION I
- conomONS (continued)
Page 2 - Certificate No. 5797 - Revision No. 11 - Docket No. 71-5797 I f !
-l gi 5. (b) Contents l ll 1 (1) Type and form of material I I
lg Uranium as U 0*0-mils thick, and:Al cermet, enriched up to 95% in the U-235 in aluminum,3l ' i I I I (i) For the packaging described in 5(a)(3)(1), the contents are described a ; I in ORNL/TM-9220, " Specifications for High Flux Isotope Reactor Fuel I j Elements HFIR-FE-3," and in the following Oak Ridge National I ' l Laboratory Drawing Nor- E-42118, Rev. M; E-42112, Rev. H; D-42113,
, l g Rev. G; E-42114, Rev. H; and E-42117, Rev. H. y N
(ii) For the packagin ri in ORNL/T$dy07 " Specifications b )(ii) the contents are described M h Flux Isotope Reactor Fuel I I Element if4R-FE-3," N d and in the follow hp>0ak Ridge National 8 Labora Drawing Nos: E-42126, Rev. J; 120, Rev. H; D-42121, l l Rev. g -42122, Rev. H; and E-42125, Rev. g (2) Maximum Q t dylo aterial per package ! /- ! . (i) the con scrgd;ia b 1) not m h than 2.63 kg of l q 5. I; is a 4
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(ii) [<oFthe nt nt sc - rj6) ,vIf(ii) not g than 6.88 kg of , dQ%% F235. _
/, i l f)
Transpo(rt Inde( h/Critl61i l W ol k
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b I I (c) 1 tg C D f: Minimum tra label for nu rtI i ? r crTt AQty ,o O. I I
- 6. Thelidliftingat[ ents must b ohedasshowq@MartinMariettaEnergy I ;
Systems, Inc., Drawi . M-20978-EL-009E, Rev. 2 @ prevent inadvertent use of I l the attachments during t*ran ort. l
- 7. In addition to the requiremen s SkarN of 10 CFR Part 71: -
l l i I (a) Each package shall be maintained in accordance with the Maintenance Program I l in Chapter 8 of the application; l , l (b) Each package shall be operated and p:epared for shipment in accordance with l q the Operating Procedures in Chapter 7 of the application; and I I I I (c) The fuel element shall meet the fabrication inspection requirements of I lg ORNL/TM-9220, " Specifications for High Flux Isotope Reactor Fuel Elements HFIR-FE-3." l ' i I I I 8. Use of packaging fabricated after December 31, 1976, is not authorized. I I I d I I I I l l I I !__________________________ __-______________ __ l
_______________-_____________________________________ l U.S. NUCLEAR REGULATORY cot 4MISS ON l
""C""**
** cowomONS (continued) !l l i, .
Page 3 - Certificate No. 5797 - Revision No. 11 - Docket No. 71-5797 I I
- 9. Tte package authorized by this certificate is hereby approved for use under the l general license provisions of 10 CFR 571.12. I
- 10. Expiration date: October 31, 1996. I, i
REFERENCES l I U.S. Department of Energy Application dated May 30, 1991. I l ' Supplement dated: February 26, 1992, and April 2, 1993. l W
] O Q g . UCLEAR REGULATORY COMMISSION
! 4 g William D. Travers, Spent Fuel Proje
' ytor ff#
l lyl Office of Nu eria6 Safety jl l , I- r I.Q 4/ N '(. and Safeg jl Date: 3 d M h Q ;
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==>
iocrR7' CERTIFICATE OF COMPLIANCE I Imeronseis FOR RADIOACTIVE MATERIALS PACKAGES I C PACAAGE #DENTif tCATiON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 1a cER W wuuoER I ei nEYdf ION NUMBER USA /5805/B( ) 1 3 l l
"N,s c' rtif.cate .ssued to cortif y that the packaging and contents d**ct'* bad in ** 5 b
** 'hPP"b''''''"d" " '"I" ' '
- of Fec'eral Hegulations. Part 71. " Packaging and Transportation of Radioactive Matenal.
- b. This certshcata does not reheve the consignor from comphance with any requirement of the regulations of the U.S Department of Transportation or other '
apphcabia reguiatory agencies. including the povernment of any country through or into which the packso* *'8' b* tran*po*d N 3 THfB CERTIFICATE is ISSUED ON THE BASIS OF A SAFETY ANALYSIS RE 7 OF THE CMAGE SO O A CA N s essUw soto e.m-s l i Chem-Nuclear Systems, Inc. Chem-Nuclear Systems, Inc. application 140 Stoneridge Drive dated February 25, 1994. Columbia, SC 29210 fl3 i 71-5805 I
- c. oocKET NUMBER cer to 6s condit#onal upon fulfilhng the requirements of to CFR Part 71, as apphcable, ano the conditions specified below.
s y (a) Packaging f I i (1) Model No.: CNS 3-55 l (2) Description 1 1 i The package is a steel-encased, lead-shielded cask with crushable impact I limiters. The basic cask is a steel cylinder 133-3/4 inches long by 50-1/2 i inches in diameter with maximum cavity dimensions of 36 inches in diameter by l g I 116 inches long reduced.to lil
- inches by the shield ring attached to the lid cover. Shielding is,provided by 6 inches of chemical-lead in the sides and i I
I closure base plate and 5-1/4 inches in the closed end. i I l I i The outside steel encasement is made up of two,1/2-inch plates on the sides ' I and three plates totaling 2-5/8 inches on the end. The containment vessel is [! i I a 1/4-inch thick cylinder with a 1/2-inch end plate. The shells are welded n' I together with the lead shielding poured to fill the annular and end spaces. I , g l i The removable, flanged and recessed base plate weldment consists of 3/8-inch l and 1-1/4-inch outside plates and a 5/8-inch inside plate. The space between l I I the plates is lead-filled. g ' y , W l The base plate is secured to the cask body by means of twelve,1-1/2-inch E-i high strength bolts and nuts and sealed with two silicone 0-rings. I l l [ I The cavity is penetrated by a vent line at the closed er.d and a drain line i through the base plate. The vent line is sealed by a gasketed and shielded y; j plug. The drain line is sealed with a 25 psig relief valve. t- , I t i i i I p ! i I r: E . Y i 46
.........................------------...--------,--f.
. ,......_-....................--..----.....---- _ .-nI
- I CoNDITlONS (continued) l l l .I l l l
Page 2 - Certificate No. 5805 - Revision No. 16 - Docket No. 71-5805 j
.I
, I I
.(a) Packaging (continued) ;g i
g ;I I I lI l l (2) Description (continued) :I I Cask appendages include two, 8-inch lifting trunnions and two, 4-inch ' l removable tilting trunnions on the cask side. jl y l . I Removable impact limiters are provided at the cask ends and at the two, 8- lN I l l ;I inch trunnions. The former consist of a series of 6-inch diameter closed end ~ l l I tubes. Each impact limiter has tubes approximately 6 inches long around the i end periphery. The closure end impact limiter has 12 tubes, six about 6 }g l inches long and six about 2 inches long, around the sides. The closed end g !p i impact limiter has six tubes about 6 inches long around the sides. A !I i gusseted tube acts as the trunnion impact limiter. ;l 1 l The cask is secured horizontally to a skid which is mounted to the transport ) I I vehicle for shipment. An optional sunshade is provided. j l i I The gross weight of the package, excluding the skid and sunshade is ll g l l approximately 70,000 pounds. The skid weighs about 4,200 pounds. i l . i I ;l ! (3) Drawings g l ;I i The packaging is constructed in accordance with Chem-Nuclear Systems, Inc. :l g ;I p Drawing Nos.: MOD 100, Rev. 12; C-111-0-0001, Rev. 0; and C-111-E-0002, l Rev. 1; and ATCOR Drawing Nos.: MOD 139-1, Rev. K; MOD 140, Rev. C; MOD 124, i I Rev. D; 0999-D-07, Rev. G; and 0999-C-08, Rev. G. An optional sunshade is constructed in accordance with Chem-Nuclear Systems, Inc. Drawing No. j l C-110-D-5001, Rev. 1. lg i t l ' I 'I i (b) Contents ) l (1) Type and form of material l l !I l' Depleted Antimony-Beryllium (Sb-Be) neutron sources and irradiated metal ju i ;I i components packaged in secondary containers. :I i (2) Maximum quantity of material per package l I, Package internal decay heat load not to exceed 250 watts. The source strength l i of depleted neutron sources not to exceed 2.3 curies of Antimony-124. $ll il l i I 6. (a) Both the inner cask cavity and the secondary container must be free of water when the package is delivered to a carrier for transport. l I, 1 l Except for close fitting items, shoring must be placed between contents, ja
, (b) l secondary container and cask cavity to minimize secondary impacts due to i
! I l l accident sequence. (c) The maximum gross weight of the contents, secondary container and shoring is j l l limited to 9,220 pounds. I I
l, -m-m-----------m===---'*-^*4' CONotTioNU (contonved) ' l >, ( g Page 3 - Certificate No. 5805 - Revision No. 16 - Docket No. 71-5805 t ! bl r ,
,1 lI y 7. 'l
'." i Prior to each shipment, the silicone 0-ring seals (base plate and vent plug) must lI I be inspected, the seals must be replaced with new seals if inspection shows any :I defects or every six (6) months, whichever occurs first. I
' 8.
Prior to delivery of the package to a carrier for transport, the package 'j t i least 1 x 10' atm-cm all be leak tested. The sensitivity of the test shall be at containmentc,avitysg/sec(STP). I i shall be leak tested at least once In addition, the packaging containment cavity ,1 J l thetestshallbeatleast1x10",everygwelve(12) months. The sensitivity of ,a atm-cm /sec (STP). l 9. The package shall be prepared for shipment and operated in accordance with the
- y Operating Procedures of Section 7.0 of the application. $
i ;I i .I
- 10. Each packaging must meet the Acceptance Tests and Maintenance Program of .I j Section 8.0 of the application.
l [
- 11. The package authorized by this certificate is hereby approved for use under the g
i general license 31, after December provisions 1983 is of not10 CFR 671.12. Fabrication of additional packagings authorized. fI i ;l
;I l 12. Expiration date: March 31, 1999. , .I l REFERENCES i
l
.I
, Chem-Nuclear Systems, Inc. application dated February 25, 1994.
)
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
.1 ,
344 Cass R. Chappell, Section Leader Cask Certification Section i Storage and Transport Systems Branch Division of Industrial and
))B Medical Nuclear Safety, NMSS jlI APB 0i.1994 Date I lI
!g
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I U.S. NUCLEAR REGULATORY COtHAISSION
-II unc Fonas sis I w CERTIFICATE OF COMPLIANCE I I to co n FOR RADIOACTIVE MATERIALS PACKAGES tp REVI$ ION NUMBLR c PACKAGE iDENTWicATION NUMBER . PAGE NUMBER 'e. TOTAL NUMBER PAG 55 l
f cc.awecATE NUMBLR 2 g 5830 6 USA /5830/B( ) 1 y I .PRcAuBa p a ins. coridicate is i u.a to c mfy inat in. pack amg eno content o. crio.o in ii.m s balow. m..ts in.appiscabi. sat.ty standeros a.ifortn inTitie to. coo l i of r.o.rai Reguistions Part 71." Packaging and Transportation of Radioactiv. M.terial." i i
- b. Tni. comf, cat do.. noi r.i,. in. conmonor trom compiianc. witn any r.auirement of in reguiations of ina u.s. o.partment of Transportation or einer N l l
- I copiscabi. ,.guistory agenc . inciua a tn. government of any country enrouan or into which tn. package wiis be iransported N I N I N
" ' " I I
! ' 's"id',EoTo'^2' *ff ,," '"' *** " ^ *"'" ^*^"."'vTs'f!Ji!El'E^fTifd$ "?,"o'1 s'R" canon 1 !
i I I Department of the Navy Minnesota Mining and Manufacturing Company l I Naval Support Force Antartica application dated June 28, 1968, as supplemented. p l y j FP0 San Francisco, CA 96601 i i
- h h, b, 'e' I 1
i
, T Gocar NuuBcR 71'-5830 I ;
I ( coNomoNs . < . corWistions specified b. low. I This c.ttificat is conditionai upon fulfiliangin.requir.m.nts of 10 CFR Part 71, as applicabl , and tn 1 i s. ca #
,, A I
l I I !f) ' 3
' I
! (a) Packaging i t-% %x 1 ,. -
/ j
/ [ { ( g' I
l l (1) Model No : SNAP-21
- q
;g h "~g b Description ,b&
l l (2) A I (f) ~ Ksh v r e y rh I L A thermoelectri"c generator p6} inches in' diameter by 30 inches long I packaged-in a'fi htsirculart metal rprotective enclosure 52 inches in diameter l I y by 68 inches Berylco'165 housin hig @'g N{fh~'fjang(;*V-8Mol shielding;; thermal insulat I l thermoelectric modules; and the heat source. Totaj ' weight of the package is I i i 1,900 poun'dsh(/ ' Q V'ig ' "t/
&,^N I
I I h I (3) Drawings M l The SNAP-21 is const ctph-indaccdrdan with Minnesota Mining and . l Manufacturing Compny DraQing"No. T-SK-37-4014 and Drawings included in I l 1 3M Report No. MMM. 4691-33. . I I (b) Contents l. l I! I I i (1) Type and form of material I I I I Strontium 90 titanate pellets doubly encapsulated by a thin inner I liner and a 0.2-inch thick Hastelloy C primary containment capsule which meets! l the requirements of special form radioactive material. i i I l I
- i (2) Maximum quantity of material per package 33,000 ci. I
! l I i i 1-l I l I I i I r I I 49 S l .
K **
- conoirsons (contonvec) u.s wcm umins connu a
Page 2 - Certificate No. 5830 - Revision No. 6 - Docket No. 71-5830 I I I I R I I y
,8 6. In addition to the requirements of Subpart G of 10 CFR Part 71: i 1
I l (a) The package must be prepared for shipment, operated and maintained in I q t accordance with Minnesota Mining and Manufacturing Company Report No. MMM 3691- l I 42, " SNAP-21 Program, Phase II, Deep Sea Radioisotope-Fueled Thermoelectric , 3 I Generator Power Supply System, Shipping and Handling Manual." g g l 7. The package authorized by this certificate is hereby approved for use under I ' g the general license provisions of 10 CFR 571.12. I
! 8. Expiration date: NovembepN0h260. b h I j' yQ REFERENCE I +
l Minnesota Mining and nufacturing Company application date une 28, 1968, I i Department of Navygpplement(dated June 8 and Oct eElb, SfD, and y l l September 20,199h q b tg\ [ 1 ; OR hh a:bRREGULA
.S q
,f Y COMMISSION fa g
5-p , V , R u/s 4 (f) 'l Yd'F 1i' N(17adi-{h,'dIrectoW fl g $4% 4$p t t 'r e I oject f(ice % g g- p 40J l t d ;l ear t'erial $afety 1 I p f kN hts ' V) l Date: h l Q(
+
g l o :
!l i Y***M j l I ' 'l ' a N
I I I l i i l' .I ; I I I I I I i I I I I I I I I __________________________ I
_.______________________________________________________,I u.s. NUCUEAR REGULATORY consensSION nneponssie I
== CERTIFICATE OF COMPLIANCE I I
w crA n FOR RADIOACTIVE MATERIALS PACKAGES ~ cPACKAGE R d PAGE BER e TOTAL NUM8E PAGE5 4REVi&lON ER i cERTi g p ER 1 I 2 PnEmoeE I
.. Tn c.rt.fic.i. inu.a io e.rtify in.t th. p.ck.oine .no cont.ni. o crib.o in item s beiow. m.et in..pphcebie tery tano ro...t forin in Titi. io.coes a of r.oer. n.gui.i.on., p.ri ri. e.ca.gina .no Tr.n.po,s i on of n.o,o.ci ve u.t.ri.L-I
- b. Thi certific.t. ooe. not reheve the consignor from comph.nce with .ny requiremoryt of the regul.t.ons of the U S. D.p.rtment of Tr.n. port. tion or otherI
.pphc.bi. reoui.iory .genci . inciuo.no the governm.nt of any country thrount. or into which the pick.ge will be transported. I I
- 3. THIS CERTIFICATE 18 IS, SUED ON THE BASIS OF ANO t TITLE A SAFETY Af4ALYSIS IDENTIFICATION REPORT OF REPORT OR APPLICATION. OF THE PACKAGE DESIGN OR APPLICATION a IsbufD TO Mwrw eas Adrhessi I Department of the Air Force Teledyne Energy Systems application dated g June 26, 1985, as supplemented. ;I HQ ATAC/SEG I 1030 S. Highway A1A I Patrick AFB, FL 32925-3002 3 I i
-, i s C j i si E G72-sB62 e oOCxET NuusER v s a I
.. CONomONS ,v q . I Tha. certific.t. i. condition.1 upon fulfdhng the requirement. of 10 CFR Part ri. .. .pphc ble, .no the coradhison. .pecified b. low
.- .e v.g ,
I n v , e . l J. I Q .. s x [p' (a) Packaging /~ - (t, , , - cg ,.t n*
+
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l
, : u, .y\i? - O (1) ModelNoIf. Sentinel-100F/ (
y , Wy y , ,, l l (2) Description D -A .y<_ y / p p gg,y , . v,
'f l
The package, a thermoelectric, generator, is 45.5: inches;in height with a base i diameter ofd24.5' inches (excludinginounting pads), andiweighs approximately ~ 1 1 2,600 pounds} Thd~ components',inclbdedTungsten biological shield (10.705" X I 13.837" OD)swhich is withinfthe' aluminum (6061) outet protective housing.
~
I Four 6061-T6 pousing pads at the base ofithe aluminum housing provide the " shipping pallet /at_tachment poi'n ti.N ' (3) Drawings ' y , D i 4 s M N I Thepackagingisconst)uctAlishccbMance'withthefollowingIsotopes,Inc. Drawing Nos.: l l 010F10000 Sheets 1-3 (Rev. C), Generator Assembly Sentinel 100F i 010-20000 Sheets 1-2 (Rev. B), Fuel Capsule Assembly 1 1 010-70003 (Rev. A) Shield Body I 010-70004 Shield Plug 001-90064 Sheets 1-2 (Rev. A), Shipping Crate Sentinel RTG l 001-90039 Sheets 1-2 (Rev. J), Sheet 3 (Rev. H), and Sheet 4, Pallet Assembly ; , I I I I I I I I I I I I 51 1 I I
','," f " " " "* U S. NUCLEAR REGULATORY COMMfSSION cONDmONS (contmuod)
Page 2 - Certificate No. 5862 - Revision No. 7 - Docket No. 71-5862 I I I I - 1
- 5. (b) Contents l
(1) Type and form of material l I i Strontium-90 titanate doubly encapsulated in a stainless steel liner and I . Hastelloy or Uniloy HC capsule which meets the requirements of special I I l l form radioactive material. ! l (2) Maximum quantity of material per package l , l i ( 370,000 curies. I I
- 6. Fabrication of additional p jh9s htbau ized.
- 7. In addition to the re RIents of Subpart G of 10 h art 71:
l
/
(a) ThepackagesjlaLTbepreparedforshipmentandopehedinaccordance withtheOperafngProceduresinthesupplementdatedjAugust 30, 1985. jlN CN g / ,Z-(b) The in the sup packag)e@Nment da'tu'$ngust mustbe;maintainedinaccordancejifhtheMaintenanceProgram h g I I j N + R' ~;3
- j 30,;1985 / f7 g () ,
g p
- 8. The package autprized by'this/ce)rtificate i(s ereby approvedn.ror use Iunde u -3 I s
9. general license provis n \%f%) ons;of;10 V CFR':571.12.)f;. l? $ Expiration dat g Sep't 'er 30, 2 ,4' 4 l ni QV,, / 000 Dff57 fTlrl tTw' R :' ^ ? .T .;, p I 4 Hl g gp& s (7PE M inn {ERINE5g 0674 - T f ') % n i I Co g)\ Teledyne Energy g y Systemkapplication b Lj;j;; 26, 1985. s e O dated June.% I I Teledyne supplements dated *; August 30, '1985jMrid Jul 26, {g . . H j Department of the Air Force supplements dated: November $ 1993; and August 15, 1995. I NFORNtiEkS UCLEAR REGULAT?2Y COMMISSION k E l. Ad /m William D. Travers, Director Spent Fuel Project Office i I i y Office of Nuclear Material Safety ! u OCT 0 31995 and Safeguards Date: l 1, : I li 8 i I I i 1
-11 li iI a l
'- - 52 I
____________________________________ J!
pwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww wwww U.S. NUCLEAR REGULATORY COMMISSION g l g f NRC FORM 618 CERTIFICATE OF COMPLIANCE , I amw crn n FOR RAUlOACTIVE MATERIALS PACKAGES N ' h 9 d PAGE NUMBER e.TUTAL NUMBFR PAGES gj e
- b. REVISION NUMBLR c PACKAGE IDENTIFICATION NUMBLR i o CI:RTIFICATE NUMBLR 1 3 g!
/ 5874 7 USA /5874/B( )F 2 PRLAMitLE 4
- m. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standa.ds set forth in Title 10, k
^
M Code of Federal Regulations.Part 71.* Packaging and Transportation of Radmactive Material." N
- b. This certificate does not reheve the conhignor fro,? .:ompliance with any requirenrnt of the regulatons of the U.S. Department of Transportation or other l Nl l $ applicable regulatory agencies, including he govunment of any country through or into which the package will be transptwted.
1 3. THIS CERTIHCATE IS ISSUED ON THE DA515 OF A SAFETY AN ALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION N
$ a iSSuEnTOmo..ns4asmos b. TITLE ANo ioENririCATION OF REPORT OR APPLICATION:
- N I !" Department of Energy Safety Analysis for Radioactive Material N Division of Naval Reactors Shipping Cask No. WAPD-40 dated i Washington, DC 20585 December 1984, as supplemented.
l
- c. DOCKET NUMBER g
p 4. CONDITIONS g g This certificate is conditional upon fulfilling the requirements of 10 CTR Part 71, as applicable, and the conditions specified below. ( 9 5. I 8 (a) Packaging ' q 9 W N (1) Model No.: 'WAPD-40 W B
- N D (2) Description n 9 d D The WAPD-40 shipping container is;a cylindrical, stainless steel clad, N lead shielded, shipping container, used to ship irradiated fuel and non- N fuel test specimens. The container has an outer Type 304 stainless steel a P
shell 1/2-inch thick and an inner Type 304 stainless: steel shell 1/4-inch ( I k g i W thick, with 9.875 inches of;1ead between the shells.--The overall size of i the container, including-an integral skid, tis 23.25 inches in diameter by a B a W 158 inches in length'. Gross weight'(including skid) Jof the container is g g approximately 28,000 pounds. :The heat removal capacity is approximately g p 2000 BTU / hour. The cylindrical; inner cavity is 2 finches in diameter and g p 135 inches in length. Inner containers.are required for all shipments. g p Stainless steel. clad, lead' shielded end plugs bolt into each end. One-half-inch thick plates are bolted over the end plugs to provide a total g p g y end plug flange thickness of 1.0 inch for puncture resistance. Metallic, g g pressure-filled 0-rings between the end plugs and the container seal the g g package. The cask may be wrapped in polyvinyl chloride when shipped in a closed truck. A special holddown cradle is used during truck shipments. g
)
a g This cradle weighs approximately 5,000 pounds. 3 si R g g (3) Drawings E P The WAPD-40 cask is fabricated in accordance with Westinghouse Electric gl g g Drawing Nos. 936F577, Rev. 11, and 936F578, Sheet 1, Rev. 9, and Sheet 2, 4 ' g g Rev. 4. N i Ni Ni l #j g s. ll N l 9 ' Wl E W! s >\ W Il 8f m g 5 53 g 9e rm a m m m m m m m m m m >m m m m m m m m m m m m m m m
gW Ww WWii = w w w w w w iR7w w w w w w w w w w w w w w w w w w w w w w w w w w g NR FORM 618A conditions tummwds U.S. NUCLEAR REGULATORY COMMISSION g l Ei b Page 2 - Certificate No. 5874 - Revision No. 7 - Docket No. 71-5874 -g! WI
# 5.(b) Contents El g!
s (1) Type and form of material E g! Bll s g! Byproduct and special nuclear material contained within inner product i p containers. The contents must be dry and unmoderated (H to X atomic ratio gl i B less than 2). j s' y e (2) Maximum quantity of material per package j C The fissile content of the cask must be limited to a maximum of 350 Ni
- l. equivalent grams of U-235. The number of equivalent grams of U-235 is !!
g g determined by the equation: 1.0 x grams U-235 + 1.4 x grams U-233 + 1.6 x grams plutonium. [ g f (c) Transport Index for Criticality Control f 5 Minimum transport index to be shown on label for nuclear criticality control: 3.2 f E E 6. l Maximum decay heat per package must not exceed 2,000 BTU /hr. El
!5 7. As needed, shoring must be used to limit movement of contents under accident E
E B conditions of transport. E s
@ 8. The lifting trunnions must be covered during transport to preclude their use as
- 5 tie-down devices.
L 5 E E ll
- 9. The contents of the container must be limited so that the maximum measured gamma 9 E B
dose rate (above background) on the side of the cask for normal conditions does E 8 not exceed the'value' defined by C, = (1000-N4 )/F. E W E where C, - the maximum permissible gamma' dose rate on the side of the cask in E a mrem / hour for normal conditions, 5 ql s sl N, = 0.0 mrem / hour for shipments of irradiated structural materials and i ' $;i 37.0 mrem / hour for shipments of irradiated fuel. Bl g 9 s is
=
F factor obtained directly from Table 1 or Table 2 (attached). B 4 For non-fuel whose principal isotope is not included in Table 1, an F factor 9 must be determined based on calculated ratios of the limiting accident radiation i s b levels to the normal condition radiation levels for each of the principal B isotopes. i gl B p E! for U-233 with approximately 30,000 hours of effective full power operation and gl 9 greater that 17,520 hours of decay, the F factors in Table 2 for U-235 are j! a conservative and may be used. gl N g! 5\ The maximum measured neutron level dose rate on the side of the cask must not si M exceed 10.7 mrem / hour for normal conditions. il f il B il
- j i
il EI
\
EI inirm a m Earmrm a m A m a a m 2srianstrar2,r Tis m angrist m a m a m m grist , a m m anus scarm a m
i, gM5iTWrer w w trinigarantar0rrw w w w w w w w w w w w w , w w w w w w , , ac, w ,, w ,, f CONDITIO%s <wnnawd) U.S. NUCLEAR REGUL ATORY COMMISSION g NR FORM 618A L R sl M Page 3 - Certificate No. 5874 - Revision No. 7 - Decket No. 71-5874 il s f g P g ( 9. (continued) I 6' For mixed shipments of fuel and irradiated non-fuel, the more limiting C, value sGl , h j! l must be employed. s' l 9 sl
/ If C is below the maximum measurable level of the gamma instrument, other ;l meth,ods (e.g., thermal luminescent detectors, source strength calculations) must $ be employed to estimate the expected level for comparison with C,. ;j @ m The acceptance tests and maintenance program must be in accordance with Chapter s'j f
g! 10. 8.0 to WAPD-RE0(C)-270, Rev. 3. 'y , [y 11. The packaging must be leak tegted within one year prior to use to a minimum sensitivity of I x 10' std-cm /sec. ;
)
Prior to each shipment, the package m st be leak tested after assembly to a h[
- 12. j minimum sensitivity of 1 x 10'3 std-cm /sec. ,
y k i 13. The WAPD-40 shipping container may be covered with a wrapping of polyvinyl i chloride (PVC) during shipment provided that the internal heat load of the @
!i "
9 shipment does not exceed 2000 BTU /hr and the shipment is made in a closed truck. The applicable requirements of Condition No._9 above must be satisfied prior to @ h q wrapping. m' sj Expiration date: July 31,1997. l
%s-
- 14. !e s,
E 9 REFERENCES a i Safety Analysis ter Radioactive Material Shipping Cask No.' NRBK-40 dated December 1984 5 hj E i sj (WAPD-RE0(C)-210 through Rev. No. 4). E i si ( sj Naval Reactors supplements dated: ' July 3, 1985 (S#85-1328), May 6, 1987 (S#87-2721), , and November 18, 1991 (Sf92-02,620). (l l (i s i @ i 5 s FOR THE U.S. NUCLEAR REGULATORY COMMISSION --
)M -
M Y )) William D. Tra ers, Director i g s'I i Spent Fuel Project Office l M Office of Nuclear Material Safety i M jl and Safeguards El s: El l
, gI
$' gl l
l M Date 4 , e'u 5l l e Pf, Table I sl p Attachments: 1. M 2. Table 2 ill W i M B; 6,l 9; a:
*i 55 9,
fisifinimususnkrisrisrisrmrzaricsDargnsrt a m a m m m m a m m a m m m m m a sum a a a e a m m_nkgi
Attachment to USA /5874/B( )F Rev. 7 Table 1 F Factors' For Use in Formula C, = (1000-N,)/F For Irradiated 3tructural Material Shipments by Principal Isotone Isotone Enerav and Yield Factor (MeV) (y/ decay) Manganese-56 0.47 0.99 174 1.81 0.29 2.11 0.15 Cobalt-60 1.17 1.0 1492 1.33 1.0 Iron 1.095 0.56 1875 1.292 0.44 I
'The F Factor is a constant for each isotope because the energy spectrum of the emitted gamma radiation of each isotope does not change as a function of time.
56
P Att.chment to - USA /5874/8( )F Rev. 7 l i Table 2 F Factors For U:e in Fomula C, = (1000-N,)/F For Irradiated U-235 Fuel Shinsents i Effective Hours Full t Power Hours Decay Operation ZZR 141Q ZlfQ t 432Q jiSQ 3162 17.52Q 43.800 87.600 l 339 339 330 219 200 194 192 208 698 ; 100 338 338 325 219 203 198 198 237 648 l 500 338 337 318 219 206 203 206 268 629
, 1000 a
332 317 283 230 228 229 250 382 606 5000 10,000 317 300 271 242 243 248 278 427 607 15,000 310 294 269 249 253 258 292 445 610 20,000 306 290 268 254 257 265 300 457 612 [ 25,000 302 286 268 256 260 267 305 464 617 30,000 300 285 267 257 263 270 308 466 624 ; 40,000 295 282 266 258 264 271 310 472 637 i 50,000 292 279 265 259 264 272 311 472 651 I
wwwwwwwmwwwwwwwwwwwwwwwwwwwwtwwwwwwwwwwwwwwwww Y
*h CERTIFICATE OF COMPLIANCE h FOR RADIOACTIVE MATERIALS PACKAGES N
't. a FERTIFICATE NUMBER b. REYislON NUMBf R c. PACKAGE IDENT1FICATION NUMBLR d. PAGF NUMBLR e. TOTAL NUMBER PAGES M 0894 6 USA /5894/AF 1 3 g!
- 2. Pkt .MBLE k ,
- n. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set fonh in Title 10, kl
$ Code of Federa! Regulations, Part 71, " Packaging and Transportation of Radioactive Material." k
- b. This certificate does not relieve the consignor from compliance with any requirement of ti.e regulatons of the U.S. Department of Transportation or other k I N applicable regulatory agencies, including the guvernment of an) country throul;h or into which the package will be transported. N h N 3 THIS CERTIRCATE IS ISSUED ON Ti1E B ASIS OF A SAFETY AN ALYSIS RLPORT OF INE PACKAGE DLSIGN OR APPLICATION a ISSUEDTO(NanwandAddressJ b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION: k ;
9 g U.S Department of Energy Safety Analysis Report for 2.7 New Fuel (g 1 l g g Division of Naval Reactors Washington, DC 20585 Shipping Container dated July 15, 1968, as supplemented. j '
- c. DOCxrT NuuBtR MMM '
g G. CONDITIONS g g This certificate is conditional upon fulfilhng the requirements of 10 CTR Part 71, as applicable, and the conditions specified below. g N 5. ( l (a) Packaging ' l N (1) Model No.: ^2.7 New Fuel 8 B 4 I Descript' ion N (2) N d 8 The Model No. 2.7 New Fuel container wa's designed to ship and store new a N f and unirradiated S5W Core R2 fuel modules. Adapters'are used to permit I additional shipments of-S5W Core R3,: AlW Core R2, and SIC Type I fuel 5 modules. The container-assembly consists of two major components, an N , 8 W inner container which holds the. fuel module'and an outer container which a supports the inner _ container.,lThe steel outer container is approximately 4 9 24.5 inches wide by 24.5 inches?high and 128 inches long. The cross I B section of the outer container is octagonal, the . steel shell thickness is d b 0.1875 inch ASTM A'283 GR.B. .The outer?shell is surrounded by a B ( framework of steel stiffeners and raili. The inner container is e B constructed from Type 304 CRES plats , 0.1875 inch thick and is 7.76 g B inches square and 99 inches long. Bolted closure is provided for each a R container. The-gross weight of the package ranges from approximately q R 1,500 to 2,000 pounds. g 5 6 5 (3) Drawing g E B The packaging is constructed in accordance with Westinghouse Electric g 9 Corporation Drawing No. 924J152, Rev. 16. g & s N k 8; W 5 m B W Bl E D W 4 E 9 E t W E WI E, D 51 El 58 $ !a m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m
p w iinimiminimirC2rurWrW0rrwntnantrWrwr w w w w w w w w w w w iRi< w w w w w w w w w w w w w g CONomtro ramtmudi U.S. NUCLEAR REGULATORY COMMISSION g g NRC FORM 618A 5 i 5 Page 2 - Certificate No. 5894 - Revision No. 6 - Docket No. 71-5894 l s E l I l 5 5.(b) Contents E 1 9 8 9 (1) Type and form of material B W I B Unirradiated fuel assemblies of the following type: E 1 5 W B (i) S5W Core R2 standard module or corner module; W 4 R (ii) S5W Core R3 standard module or corner module; E s W i B B (iii) AlW Core R2 standard cluster or half cluster; W 5 B g (iv) SIC Core Type I . standard cluster; E D 4 l l 9 (v) SIC Core Type-I' fuel subassembly; 4 N s g (vi) SSW Core 2 standard module or corner module; W , i E N - p (vii) AlW Core R2 subassembly, d N 5 Maximum: quantity of material per package g l g (2) 5 I 9 g (i) One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(ii), g j p 5(b)(1)(iii),;5(b)(1)(iv)'or 5(b)(1)(vi). g 4 i F W l 9 1 (ii)' Two fuel assemblies as_ described in 5(b)(1)(v). g W D g (iii) Four fuel assemblies as described in 5(b)(1)(vii). g Transport Index for Criticality Control l l (c) g ly Minimum transport index to be shown'on: label for nuclear criticality control: lg l ly (1) For the contents described in 5(b)(1)(1), 5(b)(1)(ii),5(b)(1)(iv),5(b)(1)(v), lg and 5(b)(1)(vi), and limited in 5(6)(2)(i) g I and 5(b)(2)(ii): 100 g 8 (2) For the contents described in 5(b)(1)(iii) 5.0 lg and limited in 5(b)(2)(i): l U 8 (3) For the contents described in 5(b)(1)(vii) 31.3 and limited in 5(b)(2)(iii): l I 5 8 6. Expiration date: July 31, 1997. l N B N s pl 4 W I s' 8 l b ' U W 59 Pia m m m m m m m m m m m m m m m m m m m m m m m m m m m = = = = = = = = = = = = l
wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww g NRC FORM 618A COMnTioNs faminnued; U.S. NUCLEAR REGULATORY COMMISSION g i (3-98) D Page 3 - Certificate No. 5894 - Revision No. 6 - Docket No. 71-5894 E B E {l
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e ej B EI W{ E B REFERENCES E N E B Safety Analysis Report 2.7 New Fuel Shipping Container, WAPD-0P(R)S-2650 dated E N July 15, 1968. E N
- B Supplements: Bettis Atomic Power Laboratory letters WAPD-0P-(R)S-2800 dated E D September 3, 1968, WAPD-0P(R)C-3425 dated August 14, 1969; and Department of Energy E W letters G#6291 dated July 13, 1979, and G#92-03424 dated March 20, 1992. E R E B E B .
E p =FOR THE.U.S. NUCLEAR REGULATORY COMMISSION E N E N l E 8 7 E g N f William D. Travers, Director i f Spent Fuel- Project Office i p{ g I Office of Nuclear Material Safety j 5 y g { and~ Safeguards g e B <- E B
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$ NRC FORM 618 CERTIFICATE OF COMPLIANCE H "" tm -
E FOR RADIOACTIVE MATERIALS PACKAGES N N I a CERTIFICATE NUMBER b. REVISION NUMBER c PACKAGEIDENTillCATION NUMBER d PAGE NUMBER e TOTALNUMBER PAGES g g
# h 5926 16 USA /5926/Bf )F 1 3 l - 2 PRf. AMBLE k N
- a. This cernficate is issued to certify that the packaging and contents described in item 5 telow, meets the applicable safety standards set fonh in Title 10,
$ Code of Federal Regulahons, Part 71 " Packaging and Transponation of Radioactive Matenal" !
- b. This cenificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Depanment of Transponation or other I
- apphcable regulatory agencies, including the government of any country through or into which the package will be transponed. k U &
- 3. THIS CERTIFICATE IS ISSUED ON THE H ASIS OF A SAFETY AN ALYSIS REPORT OF THE PACK AGE DESIGN OR APPLICATION
- a. !$ SUED TO INanw and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION: k'
! 9 (
' 8 General Electric Company General Electric Company application W l
8 P.O. Box 460, Vallecitos Road dated November 19, 1987, as supplemented. E E Pleasanton, CA 94566 5 9 E p c. DOCKET NUMBER 9 j 71-5926 h 4 CONDITIONS , l l g This certificate is conditional upcm fulfilling the requirements of 10 Cllt Part 71, as applicable,'and the conditions specified below. g g h 5. g- ! i W (a) Packaging a B N W l B. (1) Model No.: GE-100 B W l s (2) Description 4 5 .
, W
, n A steel encased lead shielded shipping cask. TheLcask is double-walled a 9 steel-circular cylinder, 20-1/4-inch diameter by 26-7/8 inch high with g i i a central cavity approximately 7-5/8-inch diameter by 10 inches high. g s Approximately 5-7/8 inches of;1ead surround the central cavity. The g cask is equipped with a, cavity drain'line and lifting device. Closure g l E l 3 is accomplished by a gasketed and bolted steel lead filled plug. For g i p additional shielding lead,. tungsten or uranium itners may be inserted in
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g ) the cask cavity. The maximum weight of the packaging is 4,800 pounds. g s B W
- 3 (3) Drawings. q B 4 l
3 The packaging is constructed in accordance with General Electric Company g 3 Drawing Nos. 129D4727 Rev. 5; 129D4729, Rev. 5; 12904730, Rev. 4; g l 3 and 129D4731, Rev. 1. g E l 9 N N E B s W W 92 8 5l
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wwwww'swwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww g! NRC FORM 618A CONumoNs inmimurd; U.S. NUCLEAR REGULATORY COMMISSION (3-98) 8 Page 2 - Certificate No. 5926 - Revision No.16 - Docket No. 71-5926 6 B k El
- 5. (b) Contents B (1) Type and form of material "l 8
"h (i) Byproduct and irradiated special nuclear material in the form of E B-fuel rods, or plates, fuel assemblies, or meeting the requirements t B of special form radioactive material; or t B
di B B (ii) Solid nonfissile irradiated metal hardware and reactor control 9' rods (blades). E B 6 B (2) Maximum quantity of material per package 9 El p $\ Radioactive decay heat not to exceed 400 watts and 500 grams U-235 ( p equivalent mass fissile material. (U-235 equivalent mass equals U-235 ( p mass plus 1.66' times U-233 mass plus 1.66 times Pu mus). E B i p Plutonium in excess of twenty (20) curies per package must be in the form ( p of metal, metal alloy or reactor elements, q W E! g (c) Transport Index for Criticality Control gj B g di For the contents described.in 5.(b)(1)(i): g N g Minimum transport index to~be shown on- 4 g g label for nuclear criticality control:' .5. 6 gl 9 ~ g 6. Shoring shall bd provided to minimize movement of contents during accident E g g conditions of transport. g l 7.
~
At the time of delivery"of the -loaded ' package' to a carrier for transport, the g package contents shall be dry and.the fissile material unmoderated (H to X atomic l y , ratio less than 2). g
- 8. In addition to the reqdirements of Subpart G of 10 CFR Part 71:
l 8 (a) The package must be maintained in accordance with the maintenance procedures E l submitted with GE application dated January 18, 1993. 8 (b) The package must be prepared for shipment and operated in accordance with E the operating procedures submitted with GE application dated January 18, 1993. 8 9. The package authorized by this certificate is hereby approved for use under the E general license provisions of 10 CFR 971.12. l l 8 10. Expiration date: February 28, 1998. W W B E R E D E B E B E D E 8 62 El kmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm r m mrmra
- _ _ ~_ .
I wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwI l gf NRC FORM 618A CONDITIONS (amimurds U.S. NUCLEAR REGULATORY COMMISSION g a96) D Page 3 - Certificate No. 5926 - Revision No. 16 - Docket No. 71-5926 E B E l' D E E b4 REFERENCES B E , e General Electric Company application dated January 18, 1993. H l l 9 E W Supplements dated: March 3, 1993. W ! W W i ! W W l l $ FOR THE U.S. NUCLEAR REGULATORY COMMISSION N i B W ! ! R - N l 1 D d l M s lp Md l
-William D. Travers Director g l p Spent Fuel Project Office g I
n Office of Nuclear Material Safety g 7 l p ' and Safeguards- g Date: 131 , 19 b g B E B E l ' g
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i st---------------------------------------------------g i Necromm m U.S. NUCLEAR REGULAT8RY COMMISSION I I *=> CERTIFICATE OF COMPLIANCE I I w cra n FOR RADIOACTIVE MATERIALS PACKAGES I
- cERTiRCATE NUMBER b REVISION NUMBER s. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER ~e . TOTAL NUMBER PAGE'S l
I 5939 27 USA /5939/BI )F ' 1 a I I 2 PREAMBLE I I a. Tni cortificate is issued to certify that ine packaging and contents descnoed in stem 5 below. meets tne apphcabie safet y standardi set fortn in Titi 10. code I i of Federal Regulations, Part 71," Packaging and Transportation of Radioactive Matenal." l l b. Tnis certificai. do.s not reheve in. consignor from comphance wiin any requirement os ine reguistions of ine u.s. oeperiment of Transportation or other i I apphcabie ..guistory agencies. inciudir g ine government of any country inrouan or into wnsen the package wiii be transported. I I I I I
- GO CA N TNggTi
, sc,Ays;ssy TsE aasis or A sarErv ANatysis,nEgR,T,0,F 1,HE P l General Electric Company General Electric Company application !
i P.O. Box 460, Vallecitos Road dated November 19, 1992, as supplemented. I I Pleasanton, CA 94566 r 1 I i I g_g..e ooexETg 8NuuBEaR e- p'* 71[5939, I I
- a. coNomoNs sV' vj. I This certshcate is conditional upon fulfilhng{nt)equirements of 10 CFR Part 71, as apphcable, and tne conshtions specified below.
l t o l l (a) Packagin0CQ 49 Y% s36 e-j f A l l l i (1) (2) MogTNo.: 1500, N Des,cription 9 M
- 9) / [f f
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C,) O l I y n d s m. 1 }hi i l l AGeel peipedJeaddhielded si[tpp'ing cask. ThFcask is double-walled I l sfiel circalar cil)]tde q upqokimately,30t1/4-inch' diameter by 481/2 l i inches high lth.a cep tyall jty>approximately@ inch diameter by 25 i I inchpshigh.Thedine r ; erg reduced from 30 174 inches to 17 1/2 I I inchesbyc tethe top" 7 inch s 'of the cask. I I Appro,x,;matel}'sanktraction1Tynchef ofyl'eadTurppund The cask the fentral I l isequppedwithac4yjtry'drafnlinesandliftingdevice. Closure is l I
, accomprip}ed by a gasliHed\)nd boltVd steel lead-filled plug. A l l
protective cketconsistlngofanuprjghtbircularcylinderwithopen I bottom an i pro ruding box section diametrically across the top and I I vertically dow e ide attchegioasquarepallet. Dimensions of I the protective j ck ar p inrately 60 7/8 inches high by 50 inches I l
, wide across the box sect on. The outer cylindrical diameter is 36 1/2 l i inches and the pallet is 59 1/2 inches square. The maximum weight of i I the packaging is approximately 15,500 pounds. I I I I (3) Drawings l I
I l (i) The packaging is constructed in accordance with General Electric l l Company Drawing Nos. 129D4748, Rev. 7; 129D4749, Rev. 5; and I i 129D4750, Rev. 9. i I I I (ii) An optional canister insert is constructed in accordance with the I l following Chem-Nuclear Systems, Incorporated Drawing Nos.: l l
~
C-Il0-D-48019-001, Rev. D; and C-Il0-A-48019-002, Rev. C. ! l I I I I l I l l l 1 I 64 I
'______________-___________________ _________-_________J 1
I
une cones essa U.S. NUCLEAR REGULATORY cOteldlS880N m, coNoirioNS (continued) ' Page 2 - Certificate No. 5939 - Revision No. 27 - Docket No. 71-5939 I 5.(b) Contents l (1) Type and form of material l ! (1) Byproduct material and special nuclear material meeting the i requirements of special form radioactive material and antimony I pins encased in stainless steel, or l (ii) Byproduct material as "SrF, or '37CsC1 capsules meeting Condition l No. 6, below, or i N g (iii) Solid nonfissile irrdi ted metal hardware and reactor control I rods (blad ) dg K - G (iv) Stain steel encapsulated so e 1 Co-60 sources, or I (v) B uct material as '37 ting Condition No. 7, I w. CsC1 capsules $p 3 ex // A I (2) Maxim 6$quaMitgf material per pac l le \ N M.3,120 wat and i Not g exceed a; )\ heat @pra i V (i)(Item 5(b)*(1 i )jabopgd r f 1 I-
^
Q il I s alent mass equals 500 ar ;a1 ~ 3'5 eq ([)U-23 ss pl'us ii t ia ass lut %m in excess of 20 l curiesyper,pickg, a t s i ;I thel~' of %1, metal alloy or
,l l Q)eactor g he g [ '. f g (ii) 5(bhitj) ,1gfr
~
l 45 curies. i (iii) Item 5 (1)pv)above: j 200,000 curies. k k l (iv) Item 5(b)(1)(v) above: I i 157,000 curies. l (c) Maximum Transport Index for Criticality Control l l For contents described in 5(b)(1)(i) I and limited in 5(b)(2)(i): 1 E Minimum transport index to be shown on label for nuclear criticality control: 5.7 l p I R 1 65 l_______________________________________________________ :
_ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.g PORW eteA CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION l l g Page 3 - Certificate No. 5939 - Revision No. 27 - Docket No. 71-5939 l l 1 6. For the contents described in 5(b)(1)(ii): The "SrF capsules must be in l I I gcordancewithVtroDrawingHos.H-2-66759,Rev.0;2 and H-2-66758, Rev. O. The i CsC1capsulesmustbeinaccordancewithVitrgDrawinggs.H-2-66760,Rev.0; I l and H-2-66761, Rev. O. After fabrication, the SrF and CsC1 capsules must be I l g lea,ktestedusingamethodhavingsufficientsensitfvitytodetectaleakrateof l I i 10' atm cc/sec. Any capsule with a detectable leak may not be delivered to a y carrier for transport. l g 137 l 7. For the contents described in 5(b)(1)(v): The CsC1 capsules mus,t be contained g in the canister insert described in item 5(a)(3)(ii), above. The 37Cscl capsules I ' I must be constructed and tested in accordance with Section 1.2.3 of the Chem- l 1 Nuclear Systems, Incorporated suppleme A dated March 1, 1993. The canister y l 1 insert must be operated, testedta accordance with Chapters 7 and g l 8 of the Chem-Nuclear Systemk Nc)b(rporatEdent itimpptakqd dated March 1, 1993. The I shipment period must begoinpfeted within 30 days lng the placement of the I y/g , y I ( canister lid on the caoMer insert. I Q i n 8. In addition to thehuirements of Subpart G of 10 CFR pay J1: ! l (a) The package s @ l $ 8r ared for shipment, , an[1naintained in I g accordancewQhthe"f#i ing Packaae Asse (sassemb sections of the -l application 4 g f -g j i (b) The silico4 rubber lih ts m[tsibe r I ep within t 12-month period ! l preceding gr.h shipment . -o each ~ #t the,sili e rubber lid l l l gaskets mushbe iRsppote - s i i t Q, ' ghnets m be replaced if I l l inspection 26ws a0ggefpcYfsd a r t y rM&Tinevanjat be led with I i appropriate s lantc t!d tgt i a d $ipepptf. l l (c) The packaging p il Bh I k e9 kt 12-montheriodpreceding aubble it shall be performed i l each shipment, by filling the t p cavitytoappgxQ)lelyl d after each tt)irpjuseh g h4-inepth with water, I i i i reducing the cav least 5 minutes, ssure to no more than 2.5 tance is indicated by no and holding for at inuous generation of j 1, bubbles. ll l i l 9. The package authorized by this cer fine hereby approved for use under the i general license provision of 10 CFR 671.12. , l I! g I i 10. Expiration date: December 31, 1997. p I i i I
- n I
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- . . . . . . . . . . _ _ . _ . - . . . . _ _ . - ~ --- ~_-- -- .~. . . - - . .. . . =====--------------------------_____--.__________---- m l
I 7*"" "" Cowomows (continued; u.S. NUCLEAR REGULATORY COMMISSION I l Page 4 - Certificate No. 5939 - Revision No. 27 - Docket No. 71-5939 l l I ! I I I REFERENCES l I I j l General Electric Company application dated November 19, 1992. l 1 I I Chem-Nuclear Systems, Incorporated supplement dated March 1, 1993. g i l l l l l I FOR THE U.S. NUCLEAR REGULATORY COMMISSION l l i - , I l . l D '[, N e er Director l 8
/t1 l gWilliam8. I l l ,
! q rV Spent Fuel Pr e4 Qffice 8 l l s%/ Office of Nucleaf merial Safety l l N7 and Safeguards Q g 47 &.4 I i qd l l Dated: 3 N 341 b .
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i I I, !, I 1 . I P i i l ! I I 67 i l_____________ _ ______________________________________ ? _
pwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwy ) h U 10 CFR 71 CERTIFICATE OF COMPLIANCE N
, FOR RADIOACTIVE MATERIALS PACKAGES N N N
- 1. a. CERTIFICATE NUMBER b. REVislON NUMBER c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER e. TOTAL NUMBER PAGES P 8 K050 7 USA /595D/B( )F 1 3 b 2. PREAMBli N
N a. This certificate is insurJ to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10 U
$ Code of Federal Regulations. Part 71, " Packaging and Transportation of Radioactive Material." !
I
- b. This certificate dues not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other
$ apphcable reguluory agencies, including the government of any country through or into which the package will be transported. N N
- 3. THIS C1sRTIRCATF 15 ISSUED ON THE B ASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION N! 1
- a. ISSUED TO(14mr and AddnssJ b. Ti1LE AND IDENTIFICATION OF REPORT OR APPLICATION: I b d N
8 Battelle Columbus Laboratories Battelle Columbus Laboratories application Nj N 505 King Avenue dated August 21, 1981, as supplemented. 4l Columbus, OH 43201 NI B E D c.D CKETNUMBER 71-5950 5 g 4 UOND1TIONS ,. c .. ?; jg g l g This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71. as applicable,'and the conditions specified below. g
- 55. - ,, a
~'
3 (a) Packaging - N p ,v g 9 (1) Model No.: ;BCL-4 - I B - N , b (2) Descriptkon . i E a 3x ~. .. a B Steel encased lead. shielded ~ shipping ' package. The package is provided q l B with recessed plug-type lid and gasketed, bolted closure, lifting and u P tie-down devices and relief valve, vent line, and drain line a L penetrations. (Containment for the; contents is provided by an inner can a R assembly,orbymaterialintspecial! form. The. packaging has dimensions, q , p weight; and shielding as fol. lows- > g p r . - .n9::, ,, . q p , Exteriorheight,1.iiit"1- 64l8' q p Exterior diameteri in 26.4 g b i ' Cavity height,/inL 42.5 g b ' Cavity diameter,' in!, 16.1 g n ' Lead, shielding, in ' 8.4 g g Loaded weight, lb
~
13,200 (Incl. 270-lb skid) g b 4 q p (3) Drawing , q B 4 e The packaging is constructed in accordance with Battelle Memorial g p Institute Drawing No. BCL4-01, Sheet 1 and 2, Rev. D. g R q , p The inner can assembly is constructed in accordance with Battelle g g Memorial Institute Drawing No. BCL4-49, Rev. C. g N 8 4 h I 8 I B q 8 4 4 E E B! q b . .N R 68 g L.............................................a
s w w w w w ier w w w w w w w ww w w w w w w w w w w w ww ww w w w w w w w w w w w w g g N C FORM 618A CONumoNS nonnawds U.S. NUCLEAR REGULATORY COMMISSON g Bj E' Rj Page 2 - Certificate No. 5950 - Revision No. 7 - Docket No. 71-5950 8 8 Ei 1 D- di L 5 (b) Contents E! b Ej B (1) Type and form of material Ei b d b Byproduct material, source material, and special nuclear material in Nl solid metal or oxide form, which is packaged within the inner can B W D assembly specified in Item 5(a)(3), or which meets the requirements of a B special form radioactive material. W e a p (2) Maximum quantity of material per package N N d R Not to exceed 400 watts decay heat, and a J B W , p (i) Fissile material not to exceed,650 grams U-235 equivalent mass. p
- p. .c *f a p (ii) Fissile material not to exceed 2,000. grams U-235 equivalent mass. q
# N p (c) Transport Index for1 Criticality Control a
- B N p Minimum transport index to be shown on g
- p label for nuclear criticality control
- ..
g
- g n
I D For contents = described in 5(b)(1) , g p l and limited'in 5(b)(2)(1): . O.4 , g i pl . i
- g g For contents. described in 5(b)(1)' l g p and limited in 5(b)(2)(ii):- - ,l w- 100 g
- 6. The U-235 equivalent mass must be:date ined by.the following method:
f l ^ ^ g lg U-235 equivalent mass equals'U-235 mass plus 1.75 times U-233 mass plus 1.6 times Pu mass. > ly
- 7. At the time of delivery of the lokded package to a carrier for transport, the l l package contents must be (1) dry (contents of inner can assembly must not g b
decompose up to a temperature of 750 *F) and the fissile material unmoderated y (H to X atomic ratio less~than 2) and (2) so~ limited that the dose rate will y
,I not exceed 10 millirem per hour at"three (3) feet from the external surface of g ,y the package. g 8
- 8. The maximum gross weight of the cavity contents must not exceed 180 pounds (inner can assembly, radioactive material, etc.).
f g l n n B 8, a di B El B El e El a t p! B 8 e a Bj Ml Ei B I dj b 69 U Rlk n e m m m m m m m m m m m m m m u m m
wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwWWWWwww gll DNRC 96)FORM 618A UN) MONS (u.unno U.S. NUCLEAR REGULATORY COMMISSION gi g s Page 3 - Certificate No. 5950 - Revision No. 7 - Docket No. 71-5950 0 hl 4, p% 9. In addition to the requirements of Subpart G of 10 CFR Part 71: #l El sl (a) Each package must meet all of the acceptance and periodic tests specified !! sj in Section 8.0 of the application. E ! p ti l.
$ The following item in the thermal acceptance tests (8.1.6) is changed as d!
Wl i follows: 6 W: The acceptance criteria must be that the maximum measure d !:'
#f (4) W D temperature of any portion of the cask aust not exceed the W D temperatures indicated in Figure 3.3 of this application by more dl p than 25 'F. In this comparison, solar heating and ambient 9 temperature differences between Figure 3.3 and the test data must (ll '
El p, be taken into account. Ej
$ ( l pl (b) Each package shall be' operated and prepared for shipment in accordance Ej p.j with Section.7.0 of the application. Ej 2: El pl 10. The following item in the Test Procedure (8.1.3), Section 8.0 of the Wl pf application is changed as follows: El e e pl g. Remove pressurization line and insert plug.in pressure port according to gl pl the loading procedure. Use Teflon tape or other compatible sealant in
q pl the threads. g g 11. The package authorized by this certificate is hereby approved for use under the g general license provisions of 10 CFR 671.12. g y! B g 12. Expiration date: August 31, 1996. W g ll , 4 REFERENCES g 1 Battelle Columbus Laboratories application dated August 21, 1981. .i g Supplement dated July 26, 1991. h s
'FOR THE U.S.' NUCLEAR REGULATORY COMMISSION s ~
f (l w-h William D. Travers, Director 3l g Spent Fuel Project Office % y Office of Nuclear Material Safety and Safeguards [ g N 9 I Date: 3,# 6 ,
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CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES
" N N
1.a CLRTillCATE NtlMBI,R b. REVISION NUMBER c. PACKAGE (DENTiflCATION NUMBER d. PAGE NUMBE R e.T(ITAL NUMBER PAGES g
- 5957 24 USA /5957/B( )F 1 8 E k
6 2 PkEAMBLE N
- a. This ceruficate is issued to certify that the packaging and contents described in Item $ below, meets the applicable hafety standards set forth in Title 10,
$ Code of Iederal Regulations Pan 71." Packaging and Transportation of Radioactive Material." k N
i b. This ceruficate does not reheve the consignor from compliance with any requirement of the regulauona of the U.S. Department of Trant,portation or other h applicable regulatory agencica, includmg the governmeut of any country through or into which the package will be transported. k j h k 3 THIS Cf'RTIFICATE IS ISStJED ON THE BASIS OF A SAf1TY AN ALYSIS REPORT OF THE PACKAGE DES'ON OR APPLICATION g , g a ISSUID10 rNums and Addent b. TITLE AND IDENTIFICATION OF REPJRT OR APPLICATION. m I W W p Department of Energy Department of Energy application dated g g Washington, D.C. 20585 April 18, 1995, as supplemented. g 9 W E ! i
- c. DoCxET NUMBER 71-5957 l
p g y 4 CONDITIONS g ; 4 g This ceruficate is conditional upon fulfilhng die requirements of 10 CIlt Pan 71, as applicable, and the condiuons specified telow, g ]
$ 5 E I E 1 B
- g. (a) Packaging g 1
- n j (1) Model No.: .BMI-l g (2) Description N
!8 A steel-encased lead shielded shipping cask. The basic cask body is a d
cylinder 33.37 inches in diameter _by 73.37 inches high formed by two
# concentric stainless steel shells whose annular region is filled with 5 lead. The outer 1/2-inch thick'shell'has a O.12-inch thick plate spot 8
~
B welded to it, providing ~a 0.06-inch thick air gap 1 insulator. The inner 8 !
!5 shell is 15.5 inches inside diameter by 54 inches inside length. The d cask lid is a stainless steel weldment having 7.75' inches of lead E B shielding. The cask lid is secured to the cask by twelve steel studs N 8 which are welded to the cask body. The' cask is provided with a drain d B line with needle valve and 31ug, pressure gauge, and a pressure relief d Bj valve. The total cask weigit, including maximum contents of 1,800 lbs, d ;
9; is 23,660 lbs. N B d W (3) Drawings W 5 E W The cask is constructed in accordance with the following Battelle W B Memorial Institute (BMI) Drawing Nos.: 43-6704-0001, Rev. B; and E R 41-4409-0003, Rev. B. E 2 W E B 9 W E i E q E B 1 a ml B E a
,M E E
W 5, E B p! E 71 E Wl
$m m m m m m mrwrrm e rm7mrm7srm m m m m m m m arm a m m m m m m m m m m m m m m m m
2s._rjur z w w w w w w w w w w w w w w w w w W W w w w w w w w w w w w w w w w w w w w w w w w g! NRC FORM 618A CONDITIONS (omrm.<di U.S. NUCLEAR RE!ULATORY COMMISSION gl y m B N El Page 2 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 g 5. (a) Packaging (continued) 5 l (4) Product Containers ! E W The various authorized product containers are cCnstructed in accordance E N with the following Drawing Nos.: E
. m W
B (i) Inner can assembly as shown in BMI Drawing No. 00-000-421, E Rev. C. E W- E B (ii) Basket Assembly as shown in BMI Drawing Nos. BCL-000-500, Rev. A; E B BCL-000-501, Rev. A; and 0048, Rev. A. E 4 R (iii) Fermi Fuel Element copper casting assembly as shown in BMI E R Drawing No. K5928-5-0049D,0Rev.;to May 12, 1966. 4 9 .. 1 E D p (iv) Basket Assembly as shown in BMI Drawing No. 1020, Rev. B (or with E alternate spacer shown in CI Drawing No. 334D2193) or GA Drawing E R No.- 9590001, Rev. A. Failed fuel assemblies must be seal welded W W , in aluminum or stainless steel tubes with wall and end cap E p . thicknesses of at least 0.015 inch. . ~ 4 p- >< E g (v)l . Basket Assembly defined by BMI Drawing No.' BCL-000-500, Rev. A, g g _ as modified by BMI Drawing Nos. 00-000-236,,Rev. C, and g p BCL-000-502,;Rev. B. g N ~ 4 g (vih Basket Assembly!and -storage can defined by'BMI Drawing No. g g i 00-000-391,'Rev; C, and Atomic International Drawing No. AlHL, g g S8DR.0019-01, .Rev. A,'respectively. g b d g (vii)jInnercan' assembly.asshowninUnionCarbideCorporationDrawing E g y No. 101501,~Rev. Al- ' g l (viii) Basket Assembly a shown in University of Missouri Research lg g Reactor (MURR) Drawing No. 2234,' Sheets 1 through 5, Revision 0. l (ix) HFBR assembly bisket and National Laboratory Drawispacer l g ng Nos.: plate as shown BNL 93-001, in Brookhaven Sheets 1, 2. end g g 3, Rev. 2, and BNL 93-002, Sheet 1, Rev. 2. g , N (x) Basket assembly as shown in General Electric Company E l Drawing No. 183C8253, Rev. 1. l (b) Contents 8 l (1) Type and form of material 8 l E (1) Intact irradiated MTR- or BRR-type fuel assemblies containing not I N more than 200 grams U-235 per assembly prior to irradiation. N Uranium may be enriched to a maximum 93.5 w/o in the U-235 8 8 isotope. Active fuel length shall be approximately 25 inches. . l E N E R E 8j 72 E 5mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmad ) I
1 7wwwwwwwwwwwwwwwiFwwwwwwwwwwwwwwwwwwwwwwwwwwwwwg g NR FORM 618A coNomomunnaness U.S. NUCLEAR REEULATORY COMMISSION g B; El l 8j jl 8 f Page 3 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 j
- 5. (b) Contents (Continued) f Nj (1) Type and form of material (Continued) f, W
, fl (ii) Intact irradiated Enrico Fermi Core. A fuel assembly containing Nj
$ not more than 4.77 kgs U-235 prior to irradiation. Uranium may $
5 be enriched to 25.6 w/o in the U-235 isotope. %
$ El 8 (iii) Greater than Type A quantity of radioactive material which may Ej B include uranium enriched in the U-235 isotope, U-233, plutonium, WI
. B as metal, oxides, or compounds which are thermally stable up to Nl B 600*F. Plutonium in excess of twenty (20) curies per package dl B- must be in the form of metal, metal alloy, or reactor elements. Wl l B E lN (iv) Greater than Type A quantity of. byproduct material meeting the W i R requirements of special form radioactive material. W , i lB Wl ! W (v) Greater than Type A quantity of byproduct material in normal form Wl l l 9 as metal, oxides, or compounds which are. thermally stable up to Ej
# 600*F. WI 9 .
. W
- p. (vi) Irradiated Triga Type fuel assemblies described in Section 6.6 of 4 ,
l M the application (pp. 6-23 through 6-27). El 1 h ( i l / (vii) Irradiated S8DR fuel elements 0.56-inch OD by 18.7 inches long by g! 0.010-inch wall thickness of Hastelloy-N. The fuel material is ( ! L p! UZrH fully enriched in U-235. g p E' l g (viii) Intact irradiate CP-5 fuel assemblies containing not more than gl y 176 grams U-235 per assembly prior to irradiation. Uranium may g l l g be enriched to~a maximum 93 w/o in the U-235 isotope. Active g ll g fuel length shall be 28.5 inches. g l p W y (ix) Solid nonfissile irradiated hardware which may contain g i , encapsulated fission monitors. gl EI B g (x) Irradiated uranium oxide waste enriched in the U-235 isotope up gl' g. to a nominal 93 w/o which is thermally stable up to 800*F. g l (xi) Irradiated uranium enriched in the U-235 isotope meeting the l l ' ly requirements r,f special form radioactive material. g I (xii) Intact irradiated MURR fuel assemblies containing not more than 8 775 grams of U-235 per assembly prior to irradiation. Uranium g E may be enriched to a maximum 93.5 w/o in the U-235 isotope. g, Active fuel length shall be 24 inches. g a 81 9 Wl 5 8l NI
. W; m #l B El l- 5 Nl I
D I 73 ( bairm a m m m m m m m m m m m m m m m m m m m m m m m
W W W W W W Tar W W W W W W W is7 TEJ_W TE7 W W W W 157 W W7 W IBUE_7 W TE7.LR7 T37137 W W W W W W W kW B7 W W NT 1BP g! NRC FORM 618A CONDmoNs (amimus) U.S. NUCLEAR REGULATORY COMMISSION f3 96) g i I W N El P Page 4 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 !I Si hs 5. (b) Contents (Continued) j$
,%j (1) Type and form of material (Continued) 8
$[
O! (xiii) Intact irradiated MITR-II fuel assemblies containing not more $ 5 than a nominal 510 grams of U-235 per assembly prior to
- W irradiation. Uranium may be enriched to a maximum 93.5 w/o in N the U-235 isotope. Active fuel length shall be approximately 24 N sj inches. Ni s
El 9 (xiv) Intact irradiated High Flux Beam Reactor (HFBR) fuel assemblies E{ containing not more than a nominal 351 grams of U-235 per d B assembly prior to irradiation. Uranium may be enriched to a E 5 maximum of 93.5 w/o in the U-235 isotope. Active fuel length 9 shall be nominal 24 inches. El 6 6l w B (xv) Intact irradiated MTR-type fuel assemblies containing not more E p than 240 grams U-235 per assembly prior to irradiation. Uranium
&l may be enriched to a maximum 93.5 w/o in the U-235 isotope.
E ( 3 Active fuel length shall be approximately 25 inches. N
$lI s
(xvi) Irradiated MTR-type fuel sections containing not more than 176 ( n g! i grams U-235 per finel section prior to irradiation. Uranium may ( gI be enriched to a maximsm 93.5 w/o in the U-235 isotope. Active q p fuel length per fuel section shall be approximately 11 inches. E i The fuel assembly shall be sectioned only in the non-fuel bearing g 9 regions of the assembly.. g g s 9 d (2) Maximum quantity of material per package j u il Q The minimum cooling time of each fuel assembly and rod is 90 days, maximum decay heat generation per package not to exceed 1.5 kw, and the j ' g y external dose rate not to exceed 10 mrem /hr 3 feet from the external y y surface of the cask and: gt la (i) For the contents described in 5(b)(1)(i): h
; Twenty-four (24) fuel assemblies as contained in product $
j containers specified in 5(a)(4)(ii) or 12 fuel assemblies as g j y contained in product containers specified in 5(a)(4)(v). l (ii) For the contents described in 5(b)(1)(ii): 5 l One (1) fuel assembly as contained in product container specified E in 5(a)(4)(iii). f (iii) for the contents described in 5(b)(1)(iii): f 480 grams U-233 or 480 grams Pu-239 or 800 grams U-235 as g l [ contained in product container specified in 5(a)(4)(i). j , E W E l .Bf ,E Wl ......,.1.. 74
........ ....... ...... ........ g E l
, 7 w w w w w w w w w w w w w w_wys = w w w w w w w w w w w w w w w w w w FFFFirirFiririg g NRC FORM 618A CONDmoNs amum.ed) U.S. NUCLEAR REGULATORY COMMISSION gi E Bj D E Page 5 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957
- 5. (b) Contents (Continued) {
# (2) Maximum quantity of material per package (Continued) !e e
E ' N (iv) For the contents described in 5(b)(1)(iv): E lB R Gamma sources securely confined in the cask cavity to preclude !R ' B secondary impacts during accident conditions of transport. W Thermal heat generation rate is limited to 200 watts. E B E 9 (v) For the contents described in 5(b)(1)(v): E D E B Contained in product' containers specified in 5(a)(4)(i) and E
$ limited to 200 thermal watts. E E
l B D (vi) For.the~ contents described in 5(b)(1)(vi): E B . E s Thirty-eight (38) fuel assemblies as contained in product E p containers specified in 5(a)(4)(iv). Fuel assemblies with an E.' l 3 , linitial enrichment (U-235 in U) of. greater than 70 w/o U-235 are E y , limited to 19 assemblies per product container. Shipments of g g less than"19 assemblies with a U-235 enrichment greater than 70 g g w/o may be combined with assemblies of 70 w/o U-235 or less g p provided: 'x/38 + y/19 s 1, x = no. assy's s 70 w/o U-235, y - g no assy's > 70 w/o U-235. g E h (vii)! For the contents' described in 5(b)(1)'(vii): g y! ' p E gi ~ Twenty-four (24) fuel elements per can and six sealed cans per g g basket as described in~5(a)(4)(vi). Each of the six cans may g g contain up to 818.g U-235 and 158 g hydrogen. The cask is g g limited to 4.908 kg U-235. g (viii) For'the contents described in 5(b)(1)(viii): l l Twelve (12) fuel assemblies'. l (ix) For the contents described i' 5(b)(1)(ix): l l Thermal heat generatit :.w is limited to 200 watts. l ! (x) For the contents described in 5(b)(1)(x): l 8 Twenty-four (24) containers each limited to 352 grams U-235 as l 8 contained in product containers specified in 5(a)(4)(vii). The g 8 decay heat per container is limited to 20 watts. The containers , l N must be leak tested in accordance with Union Carbide Corporation letter dated November 17, 1980. l l!
, El
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, (3-96) g!
Page 6 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 5 [ E( f 5. (b) Contents (Continued) f ' (2) Maximum quantity of material per package (Continued) s e (xi) For the contents described in 5(b)(1)(xi): E f t; j Twenty-four (24) capsules each limited to 100 grams U-235. El, Wj E 9 B (xii) For the contents described in 5(b)(1)(xii): E 6 9 Eight (8) fuel assemblies as contained in the product container E W specified in 5(a)(4)(viii). The maximum burnup is 150 E 5 MWD / Assembly,and. the minimum cooling time of each fuel assembly E B is 150 days. The maximum radiation source term is 400,000 E 9 curies. E p E p (xiii) For the contents described in 5(b)(1)(xiii): E B .. E p Eight (8) fuel assemblies, contained in' the product container E y specified in 5(a)(4)(viii). The maximum decay heat per package E g is 200 watts. E 9 E 3, (xiv) For the contents described in 5(b)(1)(xiv): g
? E , Twenty.(20)fuelassemblieb'containedintwobasketsseparatedby g g a spacer plate as specified in 5(a)(4)(ix). Each shipment must (
contain twenty fuel, assemblies. The maximun burnup is g - g
, approximately 130 MWD / assembly, and the minimum cooling time is g y 470 days.' ,, g
^
s E g (xv) .For the contents described.in 5(b)(1)(xv): g lg Twelve (12) fuel assemblies contained in product container specified in 5(a)(4)(v). g ! l (xvi) For the contents describ'e d in 5(b)(1)(xvi): l Forty (40) fuel sections contained in the product container 9 specified in 5(a)(4)(x). When a shipment contains less than the l g 9 maximum number of fuel sections (40), empty fuel section basket g g spaces must be provided with an aluminum or steel spacer in the g
, form of an open-ended pipe with a minimum outer diameter of 2.5 ,
inches and a minimum wall thickness of 0.125 inches. The spacer ; l must be of sufficient length to replacr the absent fuel sections. . l ' E E , p ' E E ; 9 El i E y g, i E a, e
- l El L.........m===========76==================== J
l 7wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww.ww.wwww.g CONDITIONS (n=na-d) U.S. NUCLEAR REIULATORY COMMISSION g s NRC FORM 618A
, Bj Ei ,
l ln El 's Page 7 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 f I q 5.(c) Transport Index for Criticality Control E! H! lB l N; Minimum transport index to be shown on label ! for nuclear criticality control: i
- 5s Ei t g (1) For the contents described in 5(b)(1)(iii) and g l9 5(b)(1)(xv), and limited in 5(b)(2)(iii) and g ;
5(b)(2)(xv): 0.4 g E 8 For the contents described in 5(b)(1)(i), 5(b)(1)(ii), d (2)
# 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(x), E l
9 5(b)(1)(xi),5(b)(1)(xii),5(b)(1)(xiii), E d i B 5(b)(1)(xiv), and 5(b)(1)(xvi), and limited in
$j1 5(b)(2)(i),5(b)(2)(ii),5(b)(2)(vi),5(b)(2)(vii), H
' 5- 5(b)(2)(viii),5(b)(2)(x),5(b)(2)(xi),5(b)(2)(xii), W l @ 5(b)(2)(xiii), 5(b)(2)(xiv), and 5(b)(2)(xvi): 100 W u r{ N 8 1 6. For item 5(b)(1)(iii), mixtures of fissile material are authorized, provided E 5 the following equation is satisfied: W
$j IM X + 1. + _Z_ s 1, where f i
N l 480. 480 800
' I
!li X - Grams U-233 to be shipped W l
5l 8 P Y = Graas Pu-239 to be shipped
~
Z = Grams U-235 to be shipped W i q W e{ s' 7. Except for the contents described in 5(b)(1)(ii), 5(b)(1)(iv) and E B 5(b)(1)(xii); and limited in 5(b)(2)(ii), 5(b)(2)(iv) and 5(b)(2)(xii), the W B cask must be shipped dry.- E W B . . D 8. If the cask contents of 5(b)(1)(ii), 5(b)(1)(iv) or 5(b)(1)(xii) are shipped d B wet, the licensee must confirm that the pressure' relief valve is operable G
- p. (set pressure - 75 psig). When needed, sufficient antifreeze in the cask 6 l 9 must be used to prevent damage of any component of the package by freezing. E 8
D . . D 9. Loading and unloading o'perations of the contents described in 5(b)(1)(iii) W y' and limited in 5(b)(2)(iii) must preclude contact of water with the contents. g l' B, W p 10. When the contents of 5(b)(1)(vi) are loaded wet, the optional 0.5-inch a y diameter drain hole must be present in the primary basket lower plate to g assure proper draining of the basket. g e E B p 11. The presence and effectiveness of the Boral poison plate in the Basket g p Assemblies as shown in BMI Drawing Nos. BCL-000-500, Rev, A; 0048, Rev. A; g I y and 00-000-236, Rev. C, must be verified by neutron measurements prior to q y first use and records maintained of such verification. Verification of the a g
- p. presence of the Boral must be made in each subsequent use.
I W D p! W W E D I N l
$' G s
u....<..................................._.....s 77 N Bl
y w w w w w w w w w irr w m w w w w w w m w w w w w w w w *
- W w w w w w w w w W w w w w w w' g! NRC FORM 618A (UNDITIONS f umtmwds U.S. NUCLEAR REGULATORY COMMISSION gi g i ow gj Wl El l Page 8 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957 t 12. Contents 5(b)(1)(1) and 5(b)(1)(x) may te mixed provided the sum of the %!I j product containers and fuel assemblies does not exceed 24.
s 13. t Axial movement of fuel assemblies must be limited so that the active fuel El si F region will remain correctly positioned with respect to the poisoned section ,Nl of the basket. Removable spacers may be used in each section of the basket d 9 to limit axial movement of the assemblies. E
)
s E i W 14. Contents must be securely confined in the cask cavity to minimize movement. El' s t B 15. Prior to each use, adequacy of containment vessel must be demonstrated by E
#; performance of the leak test described in Section 7.1.1.1 of the application. E 5 E Bj, 16. Gaskets and seals (cask and fuel. canister) must be replaced at least every 12 E R months or earlier if visible degradation occurs. 9 s E R 17. For contents described in 5(b)(1)(iii) and limited in 5(b)(2)(iii), the mass E 9 of fissile material contained in reactor fuel must be based on the mass prior E pl to irradiation. E W 4
- 18. In addition to the requirements of Subpart G of 10 CFR Part 71:
~
W E B 4 pl (a) The package shall be prepared for shipment and operated in accordance 4 gl with the Operating Procedures of Chapter 7 of the application. E h E
, (b) The packaging must meet the Acceptance Tests and Maintenance Program of (
y Chapter 8 of the application. g h E a 19. The package luthorized by this certificate is hereby approved for use under j the general license provisions of 10_ CFR 71.l?. g g l 20. Expiration date: March 31, 2001. E g N E B - E y REFERENCES g Department of Energy application dated: April 18, 1995. l Department of Energy supplement dated: November 20, 1995. B l " E Bj FOR THE U.S. NUCLEAR REGULATORY COMMISSION l e - E h lW > l William D. Travers, Director Spent fuel Project Office lg g Office of Nuclear Material Safety ,
- p. and Safeguards B
Date: N M Ob E
- j E 4;
g 1 78 N kamammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmadl
l gs- --- ---- ---- ---------- -- --------- I U.S. NUCLEAR REGULATORY COMMISSION I HRC FonM sis I . I == CERTIFICATE OF COMPLIANCE I I so cra n FOR RADIOACTIVE MATERIALS PACKAGES i N ER d PAO NUMBER e. TOTA NUMBER PAGES gv i a CE.mricgguaER e REvisigNuMi>ER c.eACnAsg I I
'REAMBLE I a This certificate is issued to certify that the packaging and contents described in item 5 below, meets the apphcable safety standards set forth in Titta 10. Code .I l of Federal Aegulations. Part 71,
- Packaging and Transportation of Radioactive Matenal."
i i I b. This certificate does not reheve the consignor from comphance with any requiremer)t of the regulations of the U S. Department of Transportahon or other I apphcebio reguistory sooncies. including ine government of any country through or into nien tne package wiis be transported. I I I I I I 3 THl$ CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION I l I a. ISSUED TO IName end Addess/ b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION : 1 l Alpha-Omega Services, Inc. application I I i Alpha-Omega Services, Inc. dated June 1980, as supplemented. I I 9156 Rose Street 1 I Bellflower, CA 90706
.s
,C [A
\' c. DOCKET NUMBER f1:5979
-+s
- 4. CONDITIONS 3 ./ 'N <
j l This cettificate is conditional upon ,fulfilhng the requirements of 10 CFR Part 71, as applicable, and the conihtsons specified below. l i i I I s. ,' V I 1 1 (a) Packaging k,t 4 I I ,
', (1) Model No.: 5979 E i n ., / ,. ] e I
I
~ %~ 'f 3 / 6 ><
(2) Description -
)
i. l 4 $(/ j, ., i h' . C I l I A shipping container for teletherapyf cobalt sources Configuration l I of, the outer; container is , box-like measuring approximately 38" x 50" i x 40". Thebox_isflin~edjwithf4(5".ofplywoodwith~a0.125" outer i steel sshell welded tofa'npe8terio~rangle'frameworkT Transverse I strips,acrossithe bottom; facilitate use of a fork: lift and lifting i I lugstareprovidedat-the'four'toRcornsrs. Thesinner shield vessel is essentially a 24" diaineterb" lead-filled, barrel-shaped l configuration. Three'di.fferent cylindrical plug inserts and bolted i end caps' provide flexibility to accommodateTs'everal sizes and shapes I I i of sources /, Gross weight is approximately'5,000
, s lbs. l .
(3) Drawings hy 4 d[ I, The packaging is constructed in accordance with Alpha-Omega i Services, Inc. Drawing Nos.: 0090, Rev. 0; 0091, Rev. 0; i 0092, Rev. 1; and 0093, Rev. O. I I I I I I I I I I I I I I I I I I I I 79 I l ___-__________-_______- ---- - --------------------- -- l l l
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- rum commons tcontinuem us.mcm mum cmsseon l y
Page 2 - Certificate No. 5979 - Revision No. 9 - Docket No. 71-5979 i l, i
- 5. (b) Contents 1 i
(1) Type and form of material I I j, Cobalt 60 or cesium 137 as sealed sources which meet the l requirements of special form radioactive material. l g i i I I (2) Maximum quantity of material per package i I I 13,000 curies Co-60 or 3,000 curies Cs-137, with decay heat l load not to exceed 200 watts. l i g 6. t I I Lifting eyes attachments. shall (,beJAcoy,eg
. o{gg(i p prevent use as tie-down I ,
jf I
- 7. The shield ves su es shall be equipped thaskets.
! 8. Bolts used tgs cure the shield vessel closure ca Aall be secured g !
against looshing_%by vibration during transpoyt.;p ,,/ l l A
~
l 9. l In additi g o th ements of Subpa jf 10 CFR art 71: I l a) Eac$7ackage mu$ theia'iht i e supgmentdate'd hspectiongogramofthe l N ut2{l990 y l-b) Thehracka t* s-pred ic'r
)_-3/ i ntGp,acco ce with the i Opeyting eq , l ie a p elft d tes,%ugug20,1990. l
- 10. The packa uth l under the neral i en w cer ifkte h reby ' roved for use kby[pmeW9ibusoE10ffR571.1. j g i 11.
Expiration d h ept dr b I/ ,
~
l REFERENCES h l Alpha-Omega Services, Inc. a h i 10 da k 1980. [ Supplement dated: April 12, 1983, May 22 and August 20, 1990, and January 30, and November 16, 1995. I
,1 l l l l
I FOR THE V.S. NUCLEAR REGULATORY COMMISSION ! l M ' William D. Travers,' Director i Spent Fuel Project Office ! , i i l 1 Office of Nuclear Material Safety I l and Safeguards N l Date: k ,A91 l l
( wwwwwwwwwwwwwwwwwwwwwwwwwwwwwmwwwmwwwwwwwwwwww
" " N N"3E "
'8 C'" 7' CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES b
65 f,i c PACKAGE IDENTinCATION NUMBER d. PAGE NUMBER e. TOTAL NUMBER PAGES t a ctRunCATE NrMBER b. REVISION NUMBER 1 2 El 5984 6 USA /5984/B( ) b
", 2. PRt AMBLE k
- a. His cemficate is issued to cemfy that the packagmg and contents descnbed in item $ below, meets the upphcabic safety standards set forth k in Title 10.
Code of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material" sj NI
- b. Ris ceruficate does not reheve the consignor from compliance with any requirernent of the regulanons of the U.S. Department of Transpmtation or other h apphcable regulatory agencies,includmg the government of any country through or into which the package will be transpmted. kl nj s 'l k
h
- 3 THIS a ISSULD CE RTif]CATE TO ( Amr and Addrrup IS ISSUED ON TffE BAS 15 OF A SAFETY AN ALYSIS REPORT OF THE PACKA a a
J. L. Shepherd and Associates application j' l i I J. L. Shepherd and Associates 1010 Arroyo Avenue dated September 12, 1974, as supplemented. g l
$ g j W
I San Fernando, CA 91340-8095 s l g! g
- c. oocKET NUMBER 71-5984 i E
h 4 CONDITIONS g g This certificate is conditional uptm fulfilhng the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. E 3 3. E e g 3 (a) Packaging E 9 g g (1) Model No.: 5984 W B g g (2) Description I
! A protective overpack which provides impact resistance, and thermal 8 E
resistance for its contents which are contained withinsa single snug- E fitting. shielded inner' container. The overpack consists of a vented- E steel jacketed, laminated plywood outer' container. Dimensions of the 8 a overpack are approximately 28" in diameter by 43" high and the plywood 8 y thickness is approximately 4" on the sides and 6" on the top and bottom. W g The total weight including weight of,the contents is approximately 1,780 g g pounds. l W R (3) Drawings ;
, W The overpack is constructed in accordance with J. L. Shepherd and
, m E ! j l c Associates Drawing Nos. A-0068-2C-1 dated March 8, 1969; and A-0068-2C E l
? dated April 26, 1995. E
? E
$ The inner shielded containers are constructed in accordance with J. L. W
?
Shepherd and Associates Drawing Nos. A-0068-18, Rev. 2, or A-0068-18-B, E dated April 26, 1995, or A-0068-1B-A, dated April 26, 1995 . The special i W
?
form source capsule is constructed in accordance with J. L. Shepherd and W 5 Associates Drawing No. A-0068-10 dated January 30, 1969. s i f 5 (b) Contents E
$j E
$ (1) Type and form of material W 5; El Cesium 137 as cesium chloride sources doubly encapsulated in stainless 81 Wl steel tubes which meet the requirements of special form radioactive E'
- material. W W
(2) Maximum quantity of material per package 12,000 curies.
-e. . . . . . . . . . . . . . . . . . . . . . .s . . .
sr w w w w w m w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w i g NRC FORM 618A CONDmONS kaumurds (s.es) U.S. NUCLEAR REGULATORY COMMISSION gi l 9 Page 2 - Certificate No. 5984 - Revision No. 6 - Docket No. 71-5984 g : ! B i E i
, E. Use of packaging fabricated after August 31, 1986, is not authorized. E g
M g! 7. In addition to the requirements of Subpart G of 10 CFR Part 71: E'
& s p a. The package shall be prepared for shipment and operated in accordance E 9 with ' Inspection Operation, Handling and Maintenance Procedures" in the g, '
g l l 9 p J. L. Shepherd and Associates submittal dated May 1, 1995. j
, b. The package must meet the " Acceptance Tests" and " Checkout and s ,
g Maintenance Procedures" in the J. L. Shepherd and Associates submittal g dated February 20, 1990. j l g 8. lg The package authorized by this certificate is hereby approved for use under the generi.1 license provisions of 10 CFR 671.12. E E
- 9. Expiration date: April 30,2 2001.
l R E 5 E l 9 REFERENCES E
!e J. L. Shepherd and Ass'ociates' application dated September 12, 1974.
E E i E Supplements dated: , January 20,.1975; February 20,-1990; February 6, and May 1, 1995;
!' and April 11, 1996. E E
5 E FOR THE U.S. NUCLEAR REGULATORY COMMISSION N I ' l $- h 5 B
' &m
, William D. Travers, Director E s . Spent. Fuel- Project Office E
-Office of Nuclear Material Safety E ;
!. and Safeguards E l
E a Date: M (\ M I % g 6 a 9; E B; B E l sj E s E B R E . i b t B d Bj W Bj E D E I E E E, i E i E i Ei i E j 82 E jl .
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" CERTIFICATE OF COMPLIANCE N
" FOR RAl)lOACTIVE MATERIAIS PACKAGES ,gl, l
5 g ". La CLRT111 CATI: N1'MHlJt b. REVISION NUMBER c. PACKAGE IDENTIl1 CATION NUMBLR d. PAGE NUMBER e TOTAL NUMBER PAGES 1 6 W!
# 6003 17 USA /6003/B( )F k l 2 PRFAMBLE l lq kl
- a. This certificate is issued to certify that the packaging and contents desenhed in licm 5 below, rnects the applicable safety standarda set fonh in Title 10, l
% Code of Federal Regulations. Part 71. " Packaging and Tiansportation of Radioactive Material " %
- b. This certificate does not reheve the consignor fmm comphance with any requirenent of the regulations of the U.S. Depanment of Transportation or other Nl NI lN apphcable regulatory agencies, including the government of any country through or into which the pacLage will be transported. d B 3 3.11tl$ CERTif1 Calli IS 11 a.'ED ON THE BASIS OF A $ AIETY ANALYSIS REPORT OF THE PACK AGE DLSIGN OR APPLICATION e g
i
. issued TO ruam, God Mm4 b TITLS AND IDENTII1 CATION OF REPORT OR APPLICATION:
a U.S. Department of Energy Safety Analysis Report for M-130 shipping j container dated December 30, 1968, as g p g Division of Naval Reactors Washington, DC 20585 supplemented. j g I B fg c. DOCKET NUMBER 71-6003 j g
$ 4 CONDITIONS This certificate is conditional upon fulfilhng the requirements of 10 CIR Part 71, as applicable, and the conditions specified below.
g g g
$ 5.
g R g g (a) Packaging g (1) Model No.: M-130 l la (2) Description l TheModelNo.M-130shiphingcontainerisanuprightcylinder84inchesin j, diameter by 158 inches.overall height. The container walls consist of a a 8 i finned 1-inch thick outer. shell, fabricated from either. carbon steel, l W t carbon' steel with stainless steel clad, or solid stainless steel,10 E inches 'of lead . shielding, and 'a.1-inch thick inner pressure vessel l l
- fabricated from carbon steel, clad with stainless steel. The top of the d
W , 8 container'is covered.with a' shielded closure head which is bolted to the W l ! 8 container and seals the' pressure vessel. _ An access opening with a bolted 5 l 8 shield plug is provided in the. closure head for loading and unloading W
# spent fuel. W B
The pressure vessel has an inside diameter of 55 inches. The central 4 l 8 W 8 region contains a secondary heat exchanger (not used during shipment) W 8 surrounded by 1/2-inch thick carbon steel backup cylinder 29 inches in ( diameter. The annulus which remains between the backup cylinder and the l B ! a ! E pressure vessel provides a space 13-inches wide and 130-inches high for a i B spent fuel. The spent fuel is contained in the annulus by module holders W : B designed for the particular core to be shipped. W B The container has external penetrations to the pressure vessel for steam (- B g and water relief lines and a fill and drain line (which are capped during 5 shipment) and a pressure sensing line which remains open to a pressure ( ) B g gage during shipment. The container also has penetrations which do not B (< open to the pressure vessel for secondary heat exchanger lines (which are l' B B capped during shipment) and a temperature sensing line. (ll B , The container is supported on its transport vehicle by an "A" frame El Bj structure. Gross weight of the loaded contair.er without its support ((l B- gi structure is approximately 228,000 pounds. Wl B B W< ei 5 B; bammmmmmmmmmmmmmmmmmmm>d22Tmmmmmmmmmmmmmmmmmmmmad t l
w w w ur w w w w w w w w w w w w w w w m w w w w w WWw w w w w w miw w w w w w w w w w w u g NRC FORM 618A cosomoNs tummmeds U.S. NUCLEAR REGULATORY COMMISSION g
, aem g
W Page 2 - Certificate No. 6003 - Revision No. 17 - Docket No. 71-6003 E R N F 5.(a) Continued ( E E s (3) Drawings s di El
$ The packaging is constructed in accordance with General Electric E
%{ Drawing Nos. 247E209, Sheet 1, Rev. R; Sheet 2, Rev. K; Sheet 3, Rev. T; E Bj Sheet 4, Rev. U; Sheet 5 of 5, Rev. F, and 247E228, Rev. F. N n!
p (b) Contents N s e Type and form of material 4 m (1) 9 u y 4 Irradiated fuel assemblies, activated corrosion products and structural ( y parts containing up to 40 gallons of residual contaminated water. The g p fuel assemblies and structural parts are of the following types: q B p 5 (1) S3W/S4W fuel subassemblies of core type 2. g b p (ii) . SSW fuel modules of core types 2 or 3. g N . W p (iii) 'SSW corner fuel modules of core types 2 or 3. N g l (iv): , DIG fuel modules of core types-1 or 2. l h (v) DIG removable fuel as'semblies of core types 1 or 2. l (vi) SIC /S2C fuel modules with control rods. l (vii) SIC /S2C peripheral fuel modules. l f (viii)~ S3G-3/3A fuel module.with.or without control rods. l (ix) SAD cell. , l ; (x)
~
S3G-3/3A trradiated thermocouples and thermocouple cases. l (xi) S8G full size fuel cell with or without control rod. N D B (xii) S8G partial size fuel cell with or without control rod. 8 8 E D (xiii) S5W-4A recoverable irradiated fuel modules with control rod. N D N D (xiv) S7G recoverable irradiated fuel cells. N b N i (xv) D2W fuel cells with control rods. N B
# N b
(xvi) NR-1 fuel modules with or without control rods. I { b d D (xvii) ATC fuel modules with or without control rods. N ) E D B (xviii) AlW-3 recoverable irradiated fuel modules. Fuel modules that E ! use control rods shall have control rods inserted. N B E D N D N
- 4. E g
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.. _ -. _ . . _- -_ _ _ . . .= -- -
I i JWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW U.S. NUCLEAR REGULATORY COMMISSION g! lg NR FORM 618A coNo:TioNs (umnm.rd) E 5 E B Page 3 - Certificate No. 6003 - Revision No. 17 - Docket No. 71-6003 E IB E iP 5.(b)(2) Maximum quantity of material per package. e-E B! (i) 52 fuel assemblies as described in 5(b)(1)(i). s, B 4 ,B (ii) 12 fuel assemblies as described in 5(b)(1)(ii) or 9 fuel ( lB assemblies as described in 5(b)(1)(ii) and 4 fuel assemblies , W fB as described in 5(b)(1)(iii). E lB 6 fuel assemblies as described in 5(b)(1)(iv) and 4 fuel g l5 (iii) assemblies as described in 5(b)(1)(v). g lB W ' B g D (iv) 9 fuel assemblies as described in 5(b)(1)(vi) and 8 fuel g assemblies as described in 5(b)(1)(vii). l5 ' d B g y (v) 10 fuel assemblies as described in 5(b)(1)(viii). ly (vi) 9 fuel as'emblies s as described in 5(b)(1)(viii) and 1 fuel g I assembly as described in 5(b)(1)(ix). g l (vii) 9 fuel assemblies as described in 5(b)(1)(viii) and 1 lg structure as described in 5(b)(1)(x). l p f l (viii), 4 fuel cells as described iniS(b)(1)(xi) or 2 fuel cells as ly l described in,5(b)(1)(xi) and:2 fuel cells.as described in y ' g 5(b)(1)(xii): , g l ( (ix)__ 6 fuel assemblies as described'in.5(b)(1)(xiii). l l l (x), 8 fuel cells as described in 5(b)(1)(xiv). l N 8 (xi)- 4 fuel' cells as described in 5(b)(1)(xvi plus 2 corner fuel 7 cells or 1 RFA fuel cell. j l l l I B (xii) 4 fuel modules as' described in 5(b)(INxvi). 8 B (xiii) 10, fuel modules as described in.,5(b)(1)(xvii). d i B 8 for contents described in-5(b)(1)(xviii), 6 fuel modules or 8 ! l B (xiv) fuel modules; as described in supplement dated March 30, 1992. W l E d l B W B (3) Shipments shall be further limited by thermal requirements as follows: d i D W B (i) Shipment of contents specified in 5(b)(1)(iv) and 5(b)(1)(v) N D and limited in 5(b)(2)(iii) shall be made no earlier than 75 W B days after shutdown and shall have a decay heat load not to W i B exceed 33,500 Btu /hr per shipment. E D N D (ii) Shipment of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii) N l B, and limited in 5(b)(2)(iv) shall be made in a stainless steel W B M-130 container and shall have a decay heat load not to exceed 8 D 18,960 Btu /hr per shipment. N
> N N
., B E B E D E 85 Bl
@m m a a m m m m m m m m mirim m m m m m m m m m m m m m m m m t _ _ _ _ . _ _ _ _ _ _ _
p w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w u3 = w w w wFw w w w w w w anse g NRC FORM 618A CONDmoNs (amimwds a ssi U.S. NUCLEAR REGULATORY COMMISSION b g Page 4 - Certificate No. 6003 - Revision No. 17 - Docket No. 71-6003 E D F E 5.(b)(3) Continued W L h B (iii) Shipment of contents specified in 5(b)(1)(viii), 5(b)(1)(ix), E E B and 5(b)(1)(x) and limited in 5(b)(2)(v), 5(b)(2)(vi), and E' 9 5(b)(2)(vii) shall be made at a time after shutdown, as E determined from Bettis Atomic Power Laboratory report WAPD- E W p OP(PP)S-4401 dated June 29, 1979, and shall have a decay heat a load not to exceed 28,620 Btu /hr for the shipboard core and E B 30,000 Btu /hr for the prototype core. 6 B y E p (iv) Shipment of contents specified ir. 5(b)(1)(1) and 5(b)(1)(ii) ( p shall be made no earlier than 72 days after shutdown and shall q g have a decay heat load not to exceed 33,500 Btu /hr per g shipment. g B y (v) E y Shipment of contents specified in 5(b)(1)(xi) or 5(b)(1)(xii), g ' as limited by 5(b)(2)(vii); shall have a fully loaded g y container heat load not to exceed 15,400 Btu /hr per shipment. g l (vi) '. Shipment of contents specified in 5(b)(1)(xiii) and limited in lg g 5(b)(2)(ix) shall have a heat load not to exceed 23,800 Btu /hr y and shall be made no earlier than 92 days after shutdown. g
! (vii) Shipment of conte ts specified in 5(b)(1)(xiv) and limited in j 5(b)(2)(x):shall have a heat load not to exceed 22,400 Btu /hr l p and shall be made no earlier than 122 days after shutdown.
g (viii)_ Shipment of contents. specified in 5(b)(1)(xv) and limited in N 5(b)(2)(xi) shall have =a heat load not to exceed 19,100 Btu /hr E l and shall be'made no earlier than 420 days after shutdown. l 8 E (ix) Shipment of contents specified in 5(b)(1)(xvi) and limited in E 8 5(b)(2)(xii) shall have a heat load not to exceed 6,000 Btu /hr E
, and shall be made no earlier. than 50 days after shutdown.
8 l 8 (x) Shipment of contents specified-in 5(b)(1)(xvii) and limited in E D 5(b)(2)(xiii) shall have a heat load not to exceed 27,400 E b Btu /hr and~shall be made no earlier than 195 days after E shutdown. E B B E R (xi) Shipment of contents specified in 5(b)(1)(xviii) and limited E B in 5(b)(2)(xiv) shall have a heat load not to exceed 43,800 E b BTU /hr and shall be made no earlier than 400 days or 175 days a for AlW-3E and AlW-3J fuel, after shutdown. E D E D (c) Transport Index for Criticality Control E W b W Minimum transport index to be shown on E B label for nuclear criticality control: E D E D Except for the contents described in W D 5(b)(1)(viii) and limited in 5(b)(2)(v) 100 W 5 W h For the contents described in 5(b)(1)(viii) E B and limited in 5(b)(2)(v) 50 E U 4 l 86 E
$mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmad.l L _ __ _ _ _ .. - _
I w w ist w w w w w w Ts7 Ts7 w TsT w w w w Tar m w Ts7 Ts7 w TsT Ts7 w Ts7 Ts7 w w w w w w w wDs ( ! NRC FORM 618A CONDITION %es no U.S. NUCLEAR REGULATORY COMMISSION gl { p 06) Page 5 - Certificate No. 6003 - Revision No. 17 - Docket No. 71-6003 E! l d i
- 6. For shipments involving the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii), sj l
lq the Model No. M-130 package shall be inspected to verify that boron poison El lB plates are in the module holders. E f !E . s' 7. For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix), or ( l9 5(b)(1)(x), the thermocouples and thermocouple cases if included or the vacant E l3 module holder shall be located in the mid-position of either cage and module
- 9- holder assembly. (
(l si l p!
- 8. Shipments shall be made in the dry condition, except for residual water as i
! pl p limited in 5(b)(1). n E l9 Container number three (M-130-3) has been modified by adding two 4-inch thick by n i s' 9. p 8-inch wide steel plates welded between fins 25 and 50 and between fins 110 and g lp 135 at approximately 14.75 inches from the bottom of the container. The cooling ( y fins in this localized area _ are removed to permit attachment of the plate g g directly to the outer shell of the container. g s g . pl 10. Container number four (M-130-4) has been modified by adding a 2-inch thick by 4- 2 y inch wide steel plate welded between fins 32 and 49 at approximately 18.4 inches s y from the bottom of the container. The cooling fins in this localized area are s : removed to permit attachment of the plate directly to the outer shell of the i ! 9 container, j ' a s , l 11. Containers M-130-3, M-130-4, M-130-6, and M-130-7 may be used for the contents il: specified in 5(b)(1)(viii) and 5(b)(1)(x) only.- Containers M-130-10 and M-130-l l 15 may be used for the contents specified in 5(b)(1)(viii), 5(b)(1)(x), and lg 1 t g 5(b)(1)(xviii) only. l 12. Container M-130-11 may be used for NR-1 shipments only. l E
! 13. For shipments involving the contents specified in 5tb )(1)(xvii) which do not 1 i f8 contain a full complement of fuel modules (i.e., one position is occupied by either two flux thimbles or a vacant fuel module holder with pocket shield l:
l
- E plug), that position shall be located in the middle' module holder of either half ;
! E of the cage assembly. 4 . p E l $ 14. Expiration date: December 31, 1997. E , s E D N , N p 6 i I E B W B 6 B E N E D E B E
. p E
s E D E t D
' E E
kl E p Ei E 87
>< ta = = = = = = = = = = = = = = = m = = = = = = = = = = = = = m m m m m m m m m m m m mis$l
wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww1u gf NRC FORM 618A CONDITIONS (comimeds U.S. NUCLEAR REGULATORY COMMISSION 046) g r' g b Page 6 - Certificate No. 6003 - Revision No. 17 - Docket No. 71-6003 8 D P E REFERENCES 5 L 5 WI Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, a b 1968. 5l E 4 5 Supplements: Naval Reactors letters A#2256 dated February 24, and G#1931 dated 4
> March 3,1969; General Electric Company letter ONP-74520-526 dated April 3, 1972; p a Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter a b ONP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6, 1972; p General Electric Company letters ONP-74570-635 dated October 25, ONP-74570-654 dated
( ' q > p December 4, and ONP-14570-666 dated December 12, 1972; ONP-74570-682 dated January 12, ( p ONP-74570-698 dated January 31, ONP-74570-687 dated February 6, ONP-74390-65 dated g i e March 26, and DLGN-85570-854 dated September 24, 1973; and DLGN-85570-901 dated q p January 10, 1974; Naval Reactors letter G#4061 dated January 29, 1974; General q ' y Electric Company letters DLGN-85570-924 dated-Februcry 15, DLGN-85570-923 dated ' g p March 6, and DLGN-85570-969 dated May-24,-1974;; Naval Reactors letter G#4991 dated g g November 25, 1975; General Electric Company letters-0NP-74340-JTT-73 dated g > g December 17, 1975; CGN-85570-1145 dated September 9, CGN-85570-1146 dated g ! p September 10, and CGN-85570-1148 dated September 14, 1976; Bettis Atomic Power g p Laboratory letters WAPD-R(K)-1378 dated August 30, 1976, and WAPD-0P(PP)S-4401 dated g , y June 29, 1979; Naval Reactors letters G#6197 dated July 13, 1979, G#7022 dated g y July 14, WAPD-LP-(CES)SE-170' dated July 1981; and WAPD-LD-(CES)SE-181 dated September g g 1981; WAPD-LP(CES)SE-96 dated February 1982, G#7136 dated March 17, 1982; G#7160 dated g 1 g May 18, 1982; G#7582" dated Se;stemberm 7, 1983; G#C87-5692 dated September 2, and g l y G#C87-5689 dated September 23,t1987; G#C87-8008 dated January 19,;G#C88-5931 dated g
, May 12, and G#C88-5961 dated July 25, 1988; G#C89-2825(dated March?29, and G#C89-2863 dated August 11, 1989; G#C92-03392' dated March3 30,tand G#92-03729 dated October 20, g y
'j
, 1992; and G#C93-10935 dated October;8 n1993.- <
g E US(NUCLfARR'GULATORYCOMMISSION l l , 3 l I I I N '" Wi[11abD.' Travers,Difector N 8 Spent fuel Project Office N 8 Office of Nuclear Material Safety I i B
'and Safeguards I !
4 , R D Date 3 6-( N E N l B ' b a d b b-I I b I d I u ; b I p u , b I i
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B q ! D ' E B E b , I - k m = = = = = = = = = = = = = = = = = m m m == =8 8 .......mmmmmmmmmm. J
, ge w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w m NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION g g p> CERTIFICATE OF COMPLIANCE i N '8 " " FOR RADIOACTIVE MATERIALS PACKAGES Nl
$1
! $ d. PAGE NUMBER e. TOTAL NUMBER PAGES
- 1. a. CERTlHCATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTlHCATION NUMBER g g
# 4 E i
6058 13 USA /6058/B( )F 1 k
- 2. PREAMBLE E
N a. This certificate is issued to certify that the packagmg and contents described in hem 5 below, meets the applicable safety standardh set forth in Title 10. N
.$ Code of Federal Regulations Part 71," Packaging and Transportation of Radioactive Material."
f h. This certificate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other cpplicable regulatory agencies,includmg the government of any country through or into which the package will be transported. N
, Sj
- 3. THIS CLRTlHCATE IS ISSUED ON WE B ASIS OF A 5 AHITY AN ALYSl5 REPORT OF THE PACKAGE DESIGN OR APPLICATION N lh a. ISSUFD TO (Name und Addren) b. TITLE AND IDENTlHCATION OF REPORT OR APPLIC ATION:
W i9 Cintichem, Inc., application dated W 8 Department of Energy .8 Washington, DC 20585 March 31, 1985, as supplemented. W d 9 E ! B ! g e. DOCKET NUMBER 71-6058 8 g p 4 CONDITIONS This certificate is conditional upon fulfillmg the requirements of 10 CFR Part 71 as applicable,and the conditions specified below. g i g g
$ 5.
d 9 W B (a) Packaging 8 l 9 ' N 5 (1) Model No.: .B-3 d l B d B (2) Description , 4 W ! 4 g l 9 The packaging consists'of a lead' shielded steel weldment in the shape of a right hollow cylinder with a. bottom and a recessede plug type gasketed g l P and bolted lid. The packaging provides a' minimum of.6 inches of lead g shielding. Packaging features include lifting and tie-down devices and a q l ,B p drain to the central cavity. The maximum weight of the loaded packaging g is 30,000 pounds. g l 5 E B y The outer shell is of a laminated steeljconstructi$n and is 41 inches in g y diameter and 57 inches ~high. The two laminates are of plate material y g 1/2-inch and 1/4-inch in thickness. The inner shell is of 1/2-inch thick p i y steel plate. ' The internal cavity dimensions are 26-1/2 inches in g I y diameter and 43-1/4 inches high. The lid is of the same construction as g y the sides and bottom and is secured to'the body of the packaging by g g twelve,1-1/4-inch diameter by 2-inch long high strength bolts and sealed g with a silicone 0-ring. g l p W B Drawing g p (3) W B g The packaging is as described and constructed in accordance with g p Cintichem, Inc. Drawing No. 330E2053E, Revision E. g E , B I E B d 8 Nl R
.! E p!
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w w w w w w wiiBur w w w w w w w w w w w-@~@ w w w w inBiBiBir w w @ w w @ w w inTh w w w w w w g NRC FORM 618A CONumoNs (<,munuds U.S. NUCLEAR REGULATORY COMMISSON gl 4 96) gl Page 2 - Certificate No. 6058 - Revision No.13 - Docket No. 71-6058 gl k
- M g
g (b) Contents g' j4 (1) Type and form of material 4( l (i) Byproduct and uranium enriched in the U-235 isotope, U-233 or plutonium as solids, non-powder, and dry, which will not decompose y j g at temperatures up to 525*F and packaged within DOT Specification j g 17H steel drums. 4 jf (ii) Byproduct and uranium enriched in the U-235 isotope, U-233 or $ g plutonium which meets the requirements of special form radioactive material. j 8 E (iii) Byproduct material and uranium enriched in the U-235 isotope, E B U-233, or plutonium as solids, non-powder, and dry which will not $ decompose at temperatures up to 525*F, packaged within a nominal R 5 1/2-inch < thick (24-inch OD) polyethylene High Intergity Container @ (HIC). Liquids must be solidified in Chemtree Iron Oxide mix in a m 5 steel container. Small items, including glassware, must be placed G 9 in 1-gal steel containers and compressed (as. required). @l e i (2) Maximum quantity-of, material per package E I Et 5 s For the contents described in.5(b)(1)(i) and 5(b)(1)(ii): Ej ( l F Not to exceed,400 watts thermal decay. (! Bj , . E B> B I For the contents described.in 5(b)(1)(iii): E ( B The HIC must be limited to 200 A2 quantities of solidified liquid i B radioactive material and not more that 50 2A quantities of other 6 i radioactive materials. The maximum thermal decay heat load must not E B exceed 15 watts. E B . E ! $ For the fissile' contents described in 5(b)(1)(i), 5(b)(1)(ii), and ' E B 5(b)(1)(iii) not to exceed the following: E B E B Fissile Maximum per gl B Material Package (arams) E' l B ' E b U-235 350 g B U-233 200 g B Plutonium
- 200 g B
fi B or, pro-rated mixtures such that the sum of the ratios of the quantity g B of each fissile material to its maximum per packaging does not exceed a B unity. g ! 8 E l B 4 i B
- Plutonium in excess of 20 curies per package must be in the form of g! l W reactor fuel, fuel elements, metal, or metal alloy. q i B
- {
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T@5mwwwwwwwwwwwww ' gl NRC FORM 618A CONumONS kommuds U.S. NUCLEAR REGULATORY COMMISSION g 0 46) g p Page 3 - Certificate No. 6058 - Revision No. 13 - Docket No. 71-6058 N l R E i P N
, 5. (c) Transport Index for Criticality Control N l 9 N D For contents containing special nuclear material: g R N g Minimum transport index to be shown (
y on label for nuclear criticality control: 10.0 g ; l B N i ! y 6. For gamma-emitting special form materials, at least 5 inches of additional lead g j g shielding may be added as required as a lining on all sides within the internal q g cavity. g l 9 R , g 7. The total weight of the contents including additional lead shielding as may be g
, required shall not exceed 9,000 pounds. g l
l 8. Prior to each shipment, the lid 0-ring shall be inspected. The 0-ring shall be g g replaced with a new 0-ring'if" inspection shows,any defects or every twelve (12) g months, whichever occurs first. l 9 g
- 9. Prior to the shipment of contents described in 5,(ti)(1)(i), the package must be l l leak tested as specified in Section I of the application. l
, g
- 10. In addition to the requirements of Subpart G of 10 CFR Pdrt 71:
l U 8 (a) Each package shall be maintsined in>accordance with Section I of the ; application, as supplemented; and l l l - (b) Each package shall be operated and prepared,for shipment in accordance U l B with Section I of. the. application, as supplemented. N ' W , N l N 11. Fabrication of additional packagings'is not authoris.ed. . s N 5 ' N Thepackageauthorized;bythiscertificate'isherebyapphovedforuseunder
~
l B 12. N I R the general license provisions of.10 CFR 971.12. N ! B N l B 13. Expiration date: December 31, 2000. N 9 N ! p N B N l 0 N i e N ! N i s B N N N D N ! p N b N b N N I N N i e N l p E ! m N i p N Dj 91 5 Pmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm==mm==========m5l -
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, REFERENCES g;
B 4 g Cintichem, Inc. application dated March 31, 1985. g B n y Supplements dated: August 30 and October 31, 1985, and October 2 and g p November 27, 1990. ; g ! B E y Department of Energy supplements dated July 15 and December 21, 1992, and g g November 20, 1995. g l FOR THE U.S. NUCLEAR REGULATORY COMMISSION D N
..h WilliamD. Travers,jirector fM- 8 U
N I, ' Spent Fuel Project Office E
, - Office of Nuclear Material Safety I l ar.d Safeguards r -
8 B Date: 9 ;;L d Y B E p o, ,
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" " " FOR RADIOACTIVE MATERIALS PACKAGES N l
h s E L a. Of RTIFICATE NUMBt'R b REVISION NUMBER e PACKAGE IDENTIFICATION NUMBFR d. PAGE NUMBLR e. TOTAL NUMBER PAGLS g d 6078 22 USA /6078/AF 1 3 g 2 PREAMBR k I a. This certificate is issued to certify that the packaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10, N I 5j Code of Federal Regulations. Part 71 *Packagmg and Transponation of Radioactive Material." k
- b. This certificate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other fj apphcaNe regulatory agencies, including the government of any country through or into which the package will be transponed. k 3 THIS CLRTIFICATE IS ISSULD ON Tile B ASIS OF A S AFETY AN ALYSIS RLPORT OF THE PACKAGE DESIGN OR APPLICATION I a ISSUED TO (hns ami AJJms) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION: k l B E
@ Combustion Engineering, Inc. Combustion Engineering, Inc. application E !
8 2000 Day Hill Road dated July 9, 1996. E ! B Windsor, CT 06095-0500 W t e g j i i c. DOnET NuMBtR 71-6078 g
$ 4. CONDITIONS ,, . .
E , This certificate is conditional upon fulfilhng the requirements of 10 CIR Part 71, as applicable.and the conditions specified below. g s B 5. E i B E y (a) Packaging g i N N (1) Model Nos.: 927Al and 927C1 N , B .
!p Description I (2) ,
a
!8 A steel fuel bundle shipping container. consisting of a strongback and fuel bundle clamping assembly, shock mounted to a steel outer container.
8 U The fuel bundles are separated by 3/16" thick, high carbon steel N ! l , segmented separator blocks permanently' attached to the strongback. The N i
- 5 segmented separator blocks;aret6"
- x-8" and:are installed (welded) in N l
! B segments to form a continuous block'for the entire active length of the d I fuel assembly. The Model No.'927Al' package'is approximately 43" in W l ~ B B diameter by 189" long.with an approximate gross weight of 6,700 lbs. The d B Model No. 927C1 package is approximately ~43" in diameter by 216" long a B with an approximate gross weight of 7,300 lbs. I B n Drawing d B (3) B 4 l B The Model Nos. 927Al and 927C1 containers are constructed in accordance d l B with Combustion Engineering, Inc. Drawing No. E-5022-8051, Sheets 1 4
)
B through 4, Rev. O. W B W W (b) Contents W B E p l (1) Type and form of material q a s h (i) Model No. 927A1: unirradiated fuel bundles consisting of 0.38" g y diameter uranium dioxide fuel pellets clad in 0.028" thick zircaloy g ' tubes in a 14 x 14 square array with a 0.58" pitch. Each fuel y g! p bundle consists of a maximum of 176 fuel rods with a mximum 5.0 g l w/o enrichment in the U-235 isotope, and contains not more than g pl p 19.6 kg U-235. g 0 E s' I E; l j hl B
$ 93 51 W
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- n!
k 5.(b) (1) Contents (Continued) b Wl W (ii) Model No. 927A1: unirradiated fuel bundles consisting of 0.381" $ B diameter uranium dioxide fuel pellets clad in 0.026" thick zircaloy 5 B tubes in a 14 x 14 square array with a 0.58" pitch. Each fuel 2 , B bundle consists of a maximum of 176 fuel rods with a maximum 4.76 E l N w/o enrichment in the U-235 isotope, and contains not more than E B 19.6 kg U-235. W l 9 E B (iii) Model No. 927A1: unirradiated fuel bundles consisting of 0.33" E B diameter uranium dioxide fuel pellets clad in 0.025" thick zircaloy ( b tubes in a 16 x 16 square array with a 0.506" pitch. Each fuel s B bundle consists of a maximum of 236 fuel rods with a maximum 5.0 n b w/o enrichment in the U-235 isotope, and contains not more than E D 20.76 kg U-235. ( B - E p (iv) Model No. 927A1: unirradiated fuel bundles consisting of 0.31" ( p diameter uranium dioxide fuel pellets clad in 0.024" thick zircaloy g g tubes in a 16 x 16 square array with a 0.472" pitch. Each fuel q a bundle consists of a maximum of 231 fuel rods with a maximum 5.0 s i w/o enrichment in the U-235 isotope, and contains not more than 11.68 kg U-235. g b g b N y (v) Model No. 927C1: unirradiated fuel bundles consisting of 0.33" s p diameter uranium dioxide pellets clad in 0.025" thick zircaloy
-tubes in a 16 x 16 square array with a 0.506" pitch. Each fuel j
j bundle consists of a maximum of 236 fuel rods with a maximum 5.0 y g g w/o enrichment in the U-235 isotope, and contains not more than g g 22.77 kg U-235. g lg (vi) Model No. 927C1: 'unirradiated fuel bundles consisting of 0.324" diameter uranium dioxide fuel pellets clad ~ in 0.0235" thick l
, zircaloy tubes in a 17 x 17 square array with a 0.501" pitch. Each '
N N fuel bundle consists of 264 fuel rods with a maximum 3.6 w/o enrichmentJin the U-235 isotope, and contains not more than 16.43 N kg U-235. l l (2) Maximum quantity of material per package N Model No. 927A1: Two fuel bundles weighing not more than 1400 lbs. each. N b 4 8 Model No. 927C1: Two fuel bundles weighing not more than 1506 lbs. each. I R 4 8 (c) Transport Index for Criticality Control N b d D Minimum transport index to be shown on E B label for nuclear criticality control: 15.7 8 5 N D 6. Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, N D
- polyethylene sheath which will not extend beyond the ends of the fuel assembly. E The ends of the sheath shall not be folded or taped in any manner that would N prevent flow of liquids into or out of the sheathed fuel assembly. E D
4 h N b a N 94 E N ammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm5
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!j Page 3 - Certificate No. 6078 - Revision No. 22 - Docket No. 71-6078 ! "I 5 P a k
s
- 7. In addition to the requirements of Subpart G of 10 CFR part 71: !a
!5 (a) The package shall be prepared for shipment and operated in accordance with the Operating Procedures of Chapter 7 of the application, as f
E l 9 supplemented. E 9 4 I s (b) The packaging must be maintained in accordance with the Maintenance E l 9 Program of Chapter 8 of the application, as supplemented. W 4
>l sj 8. Fabrication of additional packagings is not authorized. E
, 5 6 I l $ 9. The package authorized by this certificate is hereby approved for use E under the general license provisions of 10 CFR $71.12. sf E sj N l p 10. Expiration date: October 31, 2000. t l 9 E l s E l 3 REFERENCES g I B N al g s Combustion Engineering, Inc. application dated July 9, 1996. g a n jl FOR THE U.S. NUCLEAR REGULATORY COMMISSION g A 'y+ WilliamD. Travers,Direchor
- l !l l 'l Spent Fuel Project Office l Sj Office of Nuclear Material Safety and Safeguards l
!e Date: f f ! bs Y -
8 E f l B E l E 4 ! ;g ' N 9 d ' B 4
> d
, B E B d s a i p E B E b I p a p 8 s N b 8 P N N N 8 s E R R
# 95 8
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_______________________________________________________ y nec rons sie U.S. NUCLEAR REGULAT 1
**w CERTIFICATE OF COMPLIANCE 10 CFR 71 l FOR RADIOACTIVE MATERIALS PACKAGES I 1 a' CERTIFICATE NUM8EH tt REVISION NUMBER c. PACKAGE 40ENTIFICATsON NUMBER ' d PAGE NUMBER e. TOTAL NUMBER PAGES 6142 5 USA /6142/B( ) 1 2 l
S. PREAMsLE l
- a. Tnis c.riificate is issued to cortify tnat in. packaging and contents d. scribed in item s b.iow. meets ine opphcabi. safety standards set forth in Titie io. code I of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material."
l
- b. This certsf6cato does not rehove the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I apphcable regulatory agencies, including the government of any country through or into which the package will be transported. I I
I a TNggfiFiCAyS4SSUg THE BASIS OF A SAFETY ANALYLf8 RE T OF THE G S O APPL I ! V.S. Department of Energy Safety Analysis Report for Bettis Disposable a Division of Naval Reactors Waste shipping container dated September 30, 1969. Washington, DC 20585 l c ., , , i ti n4 ~ t. . l
' .V
- s. oOCxET NUMBER '71-6142 i
- 4. CONDITIONS ..v . .
This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71 as applicable. and the conditions specified below
- s. _
I I (a) Packaging '
, i
., . m I (1) Model No.: Bettis Disposable Waste I 1- 3
~, 5 %
(2) Deschiption 1 i y
,e
( :) -
. s .
g, , i The ! packaging consists.of'a disposable . concrete vault enclosed in a i reusable steel 'overpack. c The concrete vault is a poured concrete block I measuring 51"; square by d9N high. .The inner, cavity;is centered in the I vaultrand may be one of;twoisizes:. 15" square by.16" deep or 27" square I l by 28" deep. Theismaller cavitybis; surrounded by'18" of structural l l concrete'on the' bottoiii'and sides aridiby'.15" on the top; the larger cavity g i is surrounded by 12" con the'~ bottom,an'disides and:by 9" on the top. The h I overpack 1,sja weldment of 2--1/2" by'5"i rectangulhr steel tubes to 1/2" l I steel plate'and is sized and constructed tp(snugly enclose the concrete ~ l l vault. The lid is similarly constructediand is secured to the overpack I i by a bolted and gasketed closure. The overall dimensions of the package l l are 64" square by~60.5"jhigh, -The fir ~oss weight is approximately 16,000 i I pounds. ^ ' I I I l (3) Drawing j i The packaging is constructed in accordance with Westinghouse Electric l l Corporation Drawing Nos. 945F976, Rev. 4; 930C940, Rev. 4 and 976C870, i l Rev. 3. I I I I I I I I I I I I I I I I I I ' I I I I 96 ' ________________________________________ ____________J 4
~ - - ~ _ .- , . - _ . _ _ - - - - . . - .
--- ---------_--__-_----------- -------------------==m4
[ l CONOmONS (continued) [ l Page 2 - Certificate No. 6142 - Revision No. 5 - Docket No. 71-6142 I [ ! r i [ l (b) Contents [ [ (1) Type and form of material L [ Radioactive material in the form of waste material packaged in smaller h cans or pails or as unpackaged solid waste sealed in poured concrete. t ( (2) Maximum quantity of material per package [ l [ Total radioactivity per package shall not exceed five times an A2 l , quantity and the plutonium activity per package shall not exceed two f l times an A2 quantity. The total fissile material per package must be [ less than the exempt quantities defined in 10 CFR 671.53. [
.s . D. H [- Q ' , [
- 6. Only reusable steel overpacks? fab'ricated before ~I August 31, 1986, are authorized for [
use. V N 3 (
- 7. The lid of the vaults'siiall be poured in such a manner thd both packaged and (
l unpackaged waste areJsealed in concrete. In addition to the'9 inches of structural i ! concrete specified,iitsection 5(a)(2) of this certificate'for,the top (lid) of a ~ [ I large cavi+y vault @n additional concrete thickness,of at least 3 inches shall be i poured s. chat ttie , vault cavity'and its contents are surrounded,by at least 12 l inches of structur$1
~~
concrete'.- - i w a 6! b# ( ;
'. Expiration date:QDecember 31,71997.
, g y.. ) ,
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.y- o Q [
l 3 . , -1. s - -
,gg (
l" r [ ' REFERENCE c [ J ,' - < j<- L. (i) WS - .;;;;k7gth:(* - Safety dated Analysis September Report 30,1969) for Bettis p;_f,Disposable i*j ] J , jW[aste- _ # shipping j' contai6er, WAPD-0( (
., s .( "'. ,c. -
.- [
Supplements dated: July!27,1982, andJune8, land-December 18,[1992. , [ s ,e , .. 15: ry L
'/f/
i FORTHEU.S. NUCLEAR'RkGULATORYCOMMISSION
/}) '
L 1
,- l
/ I Charles E. MacDonald, Chief f Transportation Branch [ ;
Division of Industrial and [ j Medical Nuclear Safety, NMSS [ ! 1 [ [ l [ . prn 93 [ ! Date: [ i l [ i ( l 1 { [ i { ( [
- (
r I 1 97 l l ___________________________________________________! ; _~
,w I
w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w wi w w w g B NGC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION o* CERTIFICATE OF COMPLIANCE 4d io cm n FOR RADIOACTIVE MATERIALS PACKAGES Nl b $ g 1.a CI RTlHCA1T NUMHLR b. REYlSION NUMBLR c. PACKAGE IDENTIMCATION NUMBER d PAGENUMBER e TOTAL NUMBI.R PAGES g 6206 22 USA /6206/AF 1 3 N L 2. FREAMBLE k i
- s. This certificate is issued to certify that the packagmg and contents described in item 5 below, meets the applu Alc safety standaids set forth in Title 10, N
$ Code of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Material." g
- b. This certificate does not reheve the consignor frorn comphance evith any requirement of the regulations of the U.S. Departnwnt of Transpwtation or other N 1 N applicable regulatory agencies, includmg the governtnent of any country through or into which the pacLage will be transported. k l 1 THis CERTlHCATE IS IS3UED ON THE E ASIS Of A S AlTTY ANALYSIS REPORT OF THE PACK AGE DESIGN OR APPLICATION N a ISSUED TO(Numa and AddressA b TITLE AND (DENTlHCATION OF REPORTOR APPLICATION: k N
E B Framatome Cogema Fuels B&W Fuel Company application g B- P.O. Box 11646 dated April 23, 1990, as supplemented. E R Lynchburg, VA 24506-1646 4
- c. DOCKET NUMBfJt
$ c. CONDITIONS <
g
$ This certificate is conditional upon fulfilhng the requirenents of 10 Cf1t Puit 71, na applicable, and the conditions specified below. g l ' (a) Packaging ,
Model No.: Mod'el B l (1) U (2) Description N W W 8 A fuel assembly ship)ing container consisting of a steel strongback d 8 clamping assembly,!siock mounted to a steel outer container. Two, N E 3/16-inch thick, 8-5/8-inch high and. full length stainless steel plates d f L containing 1.5% minimum boron are positioned between adjacent fuel assemblies. .The' outer container is:approximately 40 inches in diameter d q B by 200 inches long. Gross weight of;the loaded container not to exceed
~
l N 7,600 pounds. :> f~ d N N N (3) Drawings l
- d 8 . .
4 5 The container is constructed:in accordance with B&W Fuel Company Drawing g
- Nos. 1215464,nRev. 1; 1215465, Rev. 0; and 1215466, Rev. 1. p 8
4 b (b) Contents a N E N (1) Type and form of material , y 4 B Unirradiated, sintered UO2 pellets in fuel rods. The maximum inner g b diameter and the minimum outer diameter of the fuel rod cladding, guide g b tubes and instrument tubes are in accordance with Table 3 of B&W Fuel g R Company supplement dated October 27, 1995; and the minimum guide tube g B outer diameter and minimum wall thickness are in accordance with g 4; Framatome Cogema fuels supplement dated February 7, 1996. The locations y b of the guide tubes and instrument tubes are in accordance with Figures 2 g B through 5 of B&W Fuel Company supplement dated October 27, 1995. The q b rods are assembled into fuel assemblies. The fuel assemblies may contain gl B, inserted control rod assemblies. gl Bl R. Wi q! E gl B' a B b< Ell ql i
- {; 98 N Escarm m, r= = = = = = = = = m . m m m m m m m m m m m m m . . . . . . . . . . . . . . . .rd ,
1 'gwwwwwwwwwwwwwwwwiimwww.wwwwwwwwwwwwwww.wwww ww.g g NR FORM 618A cost >tTIONs(umunud) U.S. NUCLEAR REGULATORY COMMISSION g B 4 l pl Page 2 - Certificate No. 6206 - Revision No. 22 - Docket No. 71-6206 4 9 N F W l6 5. (b)(1) Contents (continued) E
- 9 4 p Fuel assemblies as described above have the following specifications
- E B E Assembly Tvoe 15x15 15x15 15x15 17x17 17x17 15x15 l
, 9 No. fuel rods 208 208 208 264 264 204 5 No. non-fuel tubes '17 17 17 25 25 21 l iB fuel rod pitch, in. 0.568 0.568 0.568 0.496 0.502 0.563 i 9 E y Maximum fuel 0.3707 0.3742 0.3622 0.3232 0.3252 0.3671 g g pellet OD, in. g 8 Tube material Zr-4 Zr-4l 'Zr-4 Zr-4 Zr-4 Zr-4 4 W W g Maximum active fuel .144 144 144 ' 145.825 144 144 g g length, in. g 8 5.05 0 Maximum enrichment 5.05 5.05 4.98 5.05 5.05 8 N w/o U-235 W 9 g Maximum U-235 25.1978 25.6758 23.7220_ 24~.3108' 24.6126 24.2355 g n Loading (kg) ~ g B ~ . N 9 . , 8
- p. (2) Maximum quantity of material per' package - ,
g L a y Two fuel assemblies. Total quantity ofl radioactive material within a g g package may not exceed'a Type:A quantity. g g . , . . g g (c) Transport Index for Criticality Control g q 5 Minimum transport index to.beishown on g . g g label for nuclear criticality control: 6.3 g lg 6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, polyethylene sheath which will not extend beyond the ends of the fuel assembly. lg g The ends of the sheath must not:be folded or-taped in any manner that would g g prevent the flow of liquids into or out'of the sheathed fuel assembly. g 8 There must be a bow clamp to restrain each spacer grid and end fitting. The 7. ratio of assembly weight to the number of clamp bows must not exceed 168 pounds lg
! per clamp.
g g 8 8
- 8. The weight of the contents (fuel assemblies, control rods, spacers, etc.) must not exceed 3,360 pounds. l l 9. Fabrication of additional packagings is not authorized. l l
U
- 10. In addition to the requirements of Subpart G of 10 CFR Part 71, the package i shall be operated and maintained in accordance with Section 7.0 of the U{
5 application, as supplemented. g E s e n 8 99 u.............................................:
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# Page 3 - Certificate No. 6206 - Revision No. 22 - Docket No. 71-6206 8 B
E P 'N . k B E! ' n
# 11. The package authorized by this certificate is hereby approved for use under the E 8 general license provisions of 10 CFR s71.12. E B
Expiration date: September 35,2000. Ei B 9
- 12. El '
E B i l B B REFERENCES E: 4 1 B B&W Fuel Company application dated April 23, 1990. 4 5 E B Supplements dated: July 23, 1990; May 4, August 18, August 25, and October 14, 1992; E B September 24, 1993; and April 8, May 2; and November 23, 1994; February 26, 4 B March 17, April 7, July 31, October:27, and December ~ 1,1995. E y s .- q g B Framatome Cogema Fuels supplement dated February 7, 1996. E
~
B
, E B e
.- g B FOR THE V.S. NUCLEAR REGULATORY COMMISSION q B "
_, i N
-pj g
' i
.N B
t William D. Travers Director ~' g Spent'FuelsProject Office ~ g (l g ~,
~
< Office.of Nuclear Material Safety g B r 'and Safeguards y B 1 ,
n
!5 3 B
Date:
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8l 100 N hammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmms
---------------------------------------------------y une ronu sie u.s. NUCLEAR REGULATORY COMMISSION 'l i cm CERTIFICATE OF COMPLIANCE l i
io can " FOR RADIOACTIVE MATrRIALS PACKAGES l to REVislON NUMBER c fat nAGE iDEN18FICATION NUMBER g PAGE t' UMBER e. TOTAL NUMBER PAGEs ebiCATE NUMBER 9 USA /6244/B( ) 1 3 r
- paE4usts L
.. Tai. e.nincai. . e..u.a io c.n.e in r t tn. p.ca.oina ano content. o crid.o in stem s b.io.. m..t. in. .ppisc.bi. .af t r .tandaro. ..i tortn in Titi. to. coo. [
Me e.o.,.i R.guistion , Part 71. "P.ck.geng .no Tr.n.portation of Radio ctiv. M.terial." [
- b. Tn cones.c.i. no.. noi r.i.. in. con sanor from compn.nc. .rin any requir.m.nt o' m. e.ouistion. of in. u.s. o.p.nm.ni of Tren.ponation or omer L
.ppi. cab r.gui iory o.ncs . inciuo no in. gov.rnment at any country in,ouan or +o nien in package wiii be ir.nsport o. I t
I L 17sgri,r;cgsissguisE sasis or a sarErv auntvsis,nEgTgr,sggogg,ogoga ne, tic,4,Tg (
.(
l Chem-Nuclear Systems, Inc. Chem-Nuclear Systems, Inc. application 140 Stoneridge Drive Columbia, SC 29210 dated May 14, 1984, as supplemented. Y[ l h pi <; p E71-6244 h l' . T oocar wUuaEn I
- . como,rio~s .o .
I Th4 c rtifical. 6. conottional upon fulfimng in. f.quirem nt. of 10 CFR Part 71, s. applicable, ano (n. conostion. .p.cifs.d b.lo. 1 3 y. i I l (a) Packaging g,, y l' 1>' Model Nol: CNS 4-85 i ' l I l (1) l p, ( , 1 . (2) Description ?! , .[#. l ' , l 1 The package consists'of a steel and.14a'd shielded cask. The cask is I posit.ioned within an,overpack constructed of steel and honeycomb I mater 1~al . The^ gross weighti of the package is,46,000 pounds. I , e ss *i;- l The inchesmild' steel caskf(is'ahp'ro$im'aielh,lll-l/2 in' diameter. The walls,' top,-and bottom are of 2-inch inches thick sin steel lengthly and 5 plate. Shielding is provided by 2 inches of lead within the walls and 2- I inch thick' steel walls of the cask. The cask _ lid'is secured to the cask I body by twenty-four, 3/4-inch diameter bolts (and is sealed by a a compressible polyurethane seal. Lifting devices are attached to the lid I and body of the cask y mn l l The cask is positioned within an 'overpack approximately 139-1/2 inches in I overall length and 89-3/8 inches in diameter. Aluminum honeycomb i 1 material is confined by an outer steel shell 3/8-inch thick and an inner I ' steel shell of 1/4-inch thickness. The overpack cover is of the same l construction as the rest of the overpack and is secured to the walls by y I eight, S/8-inch diameter bolts. Lifting devices are welded to the outer l l shell of the overpack cover. I ! I
- (3) Drawings i I
t The package is constructed in accordance with Nuclear Waste Systems g Drawing No. D-6930-1, Rev. F (Sheet 1 of 2) and Chem-Nuclear Systems l Drawing No. D-6930-1, Rev. E. (Sheet 2 of 2). I I I 1 . p I I 101 p, I;
-----------------y----------------------------===vv=== -
l
[",C ""
- cowomONS (contsnued)
U.s NUCH AR REGULATORY COMMIS90N 7
< Page 2 - Certificate No. 6244 - Revision No. 9 - Docket No. 71-6244 !h k
'I q l h 5.(b) Contents f
d (1) Type and form of material fl 3 d (1) Greater than Type A quantity of byproduct material as process I I solids, either dewatered, solid, or solidified, in secondary l8 i [ g! container (s) which meet the requirements for DOT Specification 7A packaging; or j f gl I i g\ 1 (ii) Greater than Type A quantity of byproduct material as solid metal l [l components in secondary containers, as required, j l (2) Maximum quantity of a[trh1prhakcag, k hermal watts of byprodu tiaterial. The contents may (l Not include to fissile' exceed 10)saterials provided the mass lisits of %h10 8 not exceeded V Not to exceed a Type A quantity 6f/ transuranic materials. ,8 Al W M ? j f
- 6. (a) For any ackage containing water and/or organic substances which could g radioly) c611y ' gen @ ate combustible gasep,'pdetermin~at' ion must be made by
!j; tests a /measuremeqtiorby.analysipof 0 that the.followingichtter;ia iare'Inet ovprJ.a; representative package sucha l$
hl pl di time: [ (}lbj O f the exp%ectedshipmeng\\i, L s, _i%2x 5 .i ~;> P ( (i) Khe hydr 69en genera'thd must tie
- limited,tb a molat quantity that w9 eld be stot mur.e?tha I JyfvoTpme(or.equivalentlimitsforother j
i j ( 16 flammable at-ETP(j!s] l%, dl " nogas,eQ'.oftfuoc'ondarycontainerfa'svoidifprese more m 0.063 g-moles /ft3 at,14.7 psia and F
\ [ y q! (ii) The gecondary contain,er/and;caskicpvity be inerted with a mus{d to 5% by lvo gj toassuretha'toxygenmustbelimite i l
N; diluent',ft those po ons of the p'ackage which could'have hydrogen grea ! l di than5%.f/ N' '
*\ % s 5 NR ll f For packages to be deTiveh typt t,afrier for transport, the secondary container must be prepared for shipment in the same manner in which j ;
!g; gl!
d determination for gas generation is made. Shipment period begins when p d the package is prepared (sealed) and must be completed within twice the I E; expected shipment time. E d F: l l (b) For any package containing materials with radioactivity concentration not exceeding that for low specific activity material, and shipped within 10 (y lql. days of separation, or within 10 days after venting of drums or other l i secondary containers, the determination in (a) above need not be made, lj and the time restriction in (a) above does not apply. n {% V
,' i g.
l d I l l I : h i 8 I I l i 102
' .. .. . _ .....Wg
",,"[ # .. ORY COMSSG CONDITIONS (continued)
Page 3 - Certificate No. 6244 - Revision No. 9 - Docket No. 71-6244 (h
'I
- 7. The lifting lugs on the outside of the overpack shall be covered during trans- I l
y port to prevent their accidental use for the purpose of tie-down or lifting. lj i !, p 8. Shoring shall be placed between the secondary containers (or activated com- ' i ponents) and the cask cavity to minimize movement during normal conditions of I transport. lp l N 5 9. The package shall be prepared for shipment and operated in accordance with the I hl1 i (l operating procedures in Chapter 7 of the application as supplemented. l l 4 pi l 8 10. Each package must be maintained in accordance with the maintenance program in ;g Chapter 8 of the application as supplemented. [
- 11. Fabrication of additional agahngb[kgut 31, 1984, is not authorized. ;
k t
- 12. Thepackageauthorizdd.hthiscertificateis'herhy/ppprovedforuseunderthe general license prdvfsions of 10 CFR 571.12.
f b l I n e O
., p lci fl E!
- 13. Expiration date R April 30, 2000.
's. N e'7 4.
{W Ce) fn; REFERENCES {y l n vt -~ , Chem-Nuclear Syste ,Inc.appliatio,ndaIed O , j
. M ( ..Jh m .. 1$ yti)1984.
di a , , 2' -r i i l g l Supplements (f} dated \(4ugust@[;20,1989([gndSeptember.16,1994. 1984j\lijly{~ J# g f }.' l Rl 1 b HE N h UCLEAR NIGULAfDSY COMMISSION ! j u .- 7p. Ti
% g), l j \ i c
f, o) Q w.n. y
,', / >O l ,i g/ ,
a g4 R.LChappell,, y l l g! ! I i l q! Cast (Cer'tification S tt%ne tfbe Leader Cask l j h l 8l Storage and Transpor1 ystems Branch l l ) l trial and i l (lj ypDiisionofInd(hrSafety,NMSS
. ,dg1 hie i
i ' E! ]! i q! Date 04/13/95 ' l l g! lb Nl d I d' I i l l 1 1, l j Ni 4' Il ' l l I I E lI l t
'n ll l
d ll ' 4 q l 4 W I I (l! N l 103 I l{ I I
-------------------------------------------Ju.--------g senc Fons ets U.S. NUCLEA3 REGULATORY COaAMISSION I es CERTIFICATE OF COMPLIANCE I io cFR 7' FOR RADIOACTIVE MATERIALS PACKAGES I
- c. PACKAGE IDENTIFICATION NUMULR d PAGE NUMBER .. TOTAL NUMBER PAGES 1 a cLRTIFWUMBER b REVISION NU"EER USA /6280/8( ) 1 2 i
PRt Mote i
- s. The cortericate 6 inued to certify that the packaging and contents desenped in item 5 below, meets the applicable safety standards set forth in Title 10. Code l of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material." I
- b. The certificato don not rolsove the conssgnor from compliance with any requiremoryt of the regulations of the U.S. Department of Transportation or other I applicable regulatory agencies, including the government of any country through or into which the package will be transported. 1 1
I THE BA618 OF A SAFETY ANALYSIS RF RT TH GE SIG O APPL a TNisgR,TIFggtS;S8yU
, g I
J. L. Shepherd and Associates J. L. Shepherd and Associates application i 1010 Arroyo Avenue dated September 5, 1979, as supplemented. I San Fernando, CA 91340 8
, o p r ,. s I '
y it s s . , .. I C KoocxrTNuunER ' #71-6280 l a coNomoNs . v This conmcate i. conditionai upon fuifisiing tne reauirements of to err part ri. as appiicabie, aw ine condition. Specified beiow. l 5 g% . I i
,i g (a) Packaging 4) , ,
i. 1 (1) Model10.: A-0109,'IrradiatorinA-Oll7f0v'erpack' i '
,% ~33 a c I 7g (2) Descgiption , ;" / -
t
.)
Theipackaging cons A-0109 irradiator)jits1of . enclosed ~an~ within inner,' an outer lead-filled, protectivesteel enclosure weldinent(Model(Model I I . A-0117 over The irradiator is'a right cylinder, 31 inches m I diameter by; pack).36. inches.high,5lwith'aboltedtopplugclosure. The I overpack is a.doubleNalled steelicylinder' enclosing a shock absorbing l and thermal insulation ~ core of glue-bonded layers)of balsa wood (11 i lbs/cuift. density,tl2rinches thick on'the sides). The irradiator is I held in'pl. ace at each end. The void between the irradiator and inside I wall of the overpack is filled with hardwood' spacers. The overpack I cover is secured by 30, 5/8-inch diameter bolts. The dimensions of the 3 package are 50.5 inches diameter byt73 in'ches long. The weight of the l shielded irradiator isj7,000 lbs-and the weight of the overpack is e 3,400 lbs, totaling 10,400 lbs/ i I (3) Drawings a l' The overpack and irradiator are constructed in accordance with J. L. ! Shepherd and Associates Drawing Nos.: A-0109-Al, dated June 6, 1969; I A-0109-10, dated February 3, 1970; A-0109-20, dated February 5, 1970; I A-Oll7-8, change D (not dated); A-Oll7-C, dated April 2, 1970; and 1 A-Oll7-Cl, dated April 2, 1970, I I ll 1 I I I I I I I I i 104 I
. . . m. .. . . . . . . . .. ., ., . . , .- ;
-. - . ~ ..-. - - . - -~ - - - . . - -- - - -. - - . - - -
.7
?
U.S. NUCLEAR REGULATORY COMMISSION f (( " WA CONDITIONS (contsnued) I i Page 2 - Certificate No. 6280 - Revision No. 6 - Docket No. 71-6280 l I I
- 5. (b) Contents i I ,
(1) Type and form of material l l Cobalt-60 as metal, doubly encapsulated and heliarc welded in ! stainless steel. The source (s) is in an annular configuration I i approximately 6 inches in diameter by 6 inches long. The source (s) I . must meet the requirements for special form radioactive material. l (2) Maximum quantity of material per package l l - I ! 30,000 curies N 8
- 6. The overpack must be modi eh) ad i o o ndt ss than 14-1/4-inch -
diameter vent holes in two in the bottom, and ter shell (two each ih two side tiers of 4 holes ea op cap and cap side, t 90' separation, [ g l with each tier located bout one foot from each end). T lholes must be sealed i ; to prevent the inlA% ige of water but not so as to affect peir capability of I ; venting in the event of; fires. // A i l , W tA s
& i l
I[I l
'l 7. In addition to tN requirendets'of Subpart G of CFR Part %j Ih f I p y# g g (A . T [ s MththeMa6tenanceProgram l (a) The packaqs pust be ma1 ained in*acc'orda !
I described in the J LiShe s? submittal pted February pl990. q tj, $pherdjand:m Assoc'i i ~ l, 4? ,/f a l , t -% p ,- 3 'N,I (b) Thepackag, bust 3 feb drlsene nd 6pe hted Q accordance with l I descf! < -n i th 1 : I the Operatindg submittal d Fe ruar E g pl i. Q M $e Proc' ndJ. L./ Shepherd'ind g Associate I I I Q lt) tz 4 WV
' 8. te' I l ThepackageauthoripdbythisEertifia%{
general license pro 91 s of 10 CFRif71!!2:
" shier'abyap@pr l l 9. Expiration date: Januarhl,2000. !
RhRndrESk J. L. Shepherd and Associates' application dated September 5, 1979. [ll ! Supplements dated: November 29 and December 31, 1984, January 16, 1985, l 1 ' November 22, 1989, February 2, 1990, and December 6, 1994. I [ l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l
! AFc' Cass R. Chappell, ection Leader lI l Cask Certification Section l i g
' Storage and Transport Systems Branch , Division of Industrial and a Medical Nuclear Safety, NMSS I ; !l 'I 01/11/95 lDate: - 1os
= . - - - _ -_ -. _-
l gw! g NRC FORM 618w w w w warr w w w w w w w w w w w w w w w w w w w w w w w w Im U.S. NUCLEAR REGULATORY COMMISSION g
$ WR M CERTIFICATE OF COMPLIANCE l FOR RADIOACTIVE MATERIALS PACKAGES k '
s N 1 a CLRTinCATE NUMBLR b REVISION NUMBLR c. PACKAGE IDE;NTI;'ICATION NUMBLR d PAGE NUMBLR e. TOTAL NUMBLR PAGLS 6294 21 USA /6294/AF 1 3 EI ' 2 PRI.AMisLE k
- a. This certificate is issued to certify that the packaging and contents described in item 5 helow, meets the applicable safety standards set fonh in Title to, k
$ Code of Federal Regulations. Part 71," Packaging and Transportation of Radnusctive Material."
k f k b 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 wdl be transported. k N I8 g 3 THIS CI.RTIMCATE IS ISSULD ON THE B ASIS OF A 5 AITTY AN ALYSIS RLPORT OF THE PACK AGE DESIGN OR APPLICATION 3
- n. ISSULD TO (Nume and Adderu) b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION. 5 (
9 E l s Combustion Engineering, Inc. Combustion Engineering, Inc. application E s P.O. Box 107 dated July 27, 1990, as supplemented ( Hematite, M0 63047 5. W: ( p c. DOCKET NUMBER 71-6294 ( ' g y 4 CONDITIONS g
$ This certificate is conditional upon fulfilhng the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. g 4
5. ( : Packaging El 3 (a) g 5 E g (1) Model No.: UNC-2901 g ' B q g (2) Description g P q s A maximum 10.80-inch square by'30-inch long inner container constructed of i; g minimum 14-gauge steel, with bolted and gasketed top flange closure and g sealed welded bottom sheet. Inner container is centered and supported in a p 22.5-inch ID by 34-inch high 18-gauge steel drum with 16-gauge head and DOT U Specification 17H closure by asbestos or ceramic sheet,. plywood, hardboard, E hl g and insulating material. Gross weight of the package is 660 pounds. (3) Drawings . 5 The packaging is constructed in accorda'nce with Combustion Engineering, E Inc. Drawing Nos.'D-5007-8086, Rev. 6, and B-5007-8112, Rev. 1. E N (b) Contents E! Bjl Bj (1) Type and form of material @! E 9 E4 (1) Sintered uranium oxide pellets and rejected pellets enriched to a E !j 1 s maximum 5.0 w/o in the U-235 isotope. Ell n (ii) Uranium oxide as powder enriched to a maximum 5.0 w/o in the U-235 El @ isotope. Ej e ei (iii) U 0,3 powder, placed in polyethylene bags then pressed and compacted Nf N into blocks, with a maximum enrichment of 4.5 w/o in the U-235 E %j isotope. Water may be injected into the blocks. El S 3 t El & (ll p l si El % m! E $ El ) 106 E! ast a m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m mE!
I L wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww5WWWWWwwwwww! gl NRC FORM 618A CONDITIONS hmmwd; U.S. NUCLEAR REGULATORY COMMISSION g! o*> g bj W Wl Page 2 - Certificate No. 6294 - Revision No. 21 - Docket No. 71-6294 $ P wl k nj ! 8 5. W (b) Contents (cont'd.) 8 1 Bj (2) Maximum quantity of material per package E R E W Maximum weight of contents within the inner container is 427 pounds, E W including radioactive material, secondary containers, and other E B packaging material. E 4 W D (i) For the contents described in 5(b)(1)(i): i W B D 320 pounds of pellets, with the U-235 content not to exceed 6.4 W D kg. Pellets must be packaged in trays in accordance with E D Combustion Engineering,;Inc. Drawing Nos. D-5018-2001, Rev. 1, W p and NFM-D-4263, -Rev. 2,i or' NFM-E-4661, Rev. 2 and NFM-D-4721, W g Rev. 1. Trays containing pellets must contain a maximum of g i n 9.07 kg and a minimum of 6.7 kg of pellets with a maximum (l p pellet diameter of 0.4 inch. e n B E y (ii) For the contents described in 5(b)(1)(ii): gf 9 -
. W pl 4220 pounds of powder, with the U-235 content not to exceed 1.5 g gl kg. Powder.must be packaged in secondaryLcontainers in g g accordance with Combustion Engineering, Inc. D; awing Nos. g y NPM-C-3389, Rev. O or Rev.;3, and NFM-D-4750, Rev. 1. g L M g (iii)Forthecontentddescribedin.5(b)(1)(iii):
L g 30.4' kg of U3 04, with the U-235 content not: to exceed 1.15 kg l l per package. The U3 0, blocks shall be placed in perforated g y . g saluminum' cans,"which shall then.be packaged in secondary g y containers in accordance with-Combustion Engineering, Inc. g g Drawing Nos. NPM-C-3389, Rev. 0 or Rev. 3, and NFM-D-4750, g g RevVI. , g B
+
E g g g (c) Transport Index for Criticality Control y (1) For the material described in Items 5(b)(1)(i) and 5(b)(1)(ii): g 8 Minimum transport index to be shown 8 on label for nuclear criticality control: 0.5 l g l (2) For the material described in Item 5(b)(1)(iii): l 8 Minimum transport index to be shown on label for nuclear criticality control 1.3 l l a f S. Prior to each shipment the insert (containment vessel) gasket shall be inspected. l , This gasket shall be replaced if inspection shows any defects or every twelve g i l,l (12) months, whichever occurs first. g
.! .l l
, hi . - - . . . . . . . . . . . . . . . . . 10....-......--------.....o 7 I
5 w w w w w w w sus w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w wr g NRC FORM 618A CONDITIONS famimud; U.S.HUCLEAR REGULATORY COMMISSION (3-96) gi-W Ej Page 3 - Certificate No. 6294 - Revision No. 21 - Docket No. 71-6294 k f E
!5 7. For the contents specified in 5(b)(1)(i), the pellet trays and wood spacers must N provide a snug axial and cross sectional fit in the inner container. For : " packages with fewer.than 16 loaded pellet trays, wood spacers or pellet trays "
with wood spacers inside must be substituted for pellet trays. E r s (j n 8. For the contents specified in 5(b)(1)(ii), powder cans and wood spacers must ' s $ provide a snug axial and cross sectional fit in the inner container. For M
$ packages with fewer than two loaded powder cans, a wood spacer or a powder can E e with a wood spacer must be substituted for the powder can. N 9 9 W 9. In addition to the requirements of Subpart G of 10 CFR Part 71: n 2 E R (i) Each packaging must meet the acceptance tests and be maintained in 5 accordance with Chapter 8'of the application; and 9 E $ i 3 (ii) The package must be prepared for shipment and operated in accordance with (
p the Operating Procedures of Chapter 7 of the application, i n E
- 10. The package authorized by this certificate is hereby approved for use under the p
E g general license provisions.of 10 CFR 971.12. p a E i 11. Expiration date: 'Harch 31, 2001. ~ q n , E a n [ ' REFERENCES g a j Combustion Engineering, Inc. application dated July 27, 1990~. 4 g n E g Supplements dated: October 19, 1990; January 27,'and July 28, 1994; and g g August 17, 1995. g 5
'F R;THE V.S. NUCLEARTREGULATORY COMMISSION ! !
5 u Trave bliiamD.:
\ w (rs, Director l 5
5 Spent Fuel Project Office ! 1 r Office of Nuclear Material Safety 7 and Safeguards l y 5 Date: b ha .
!e B E B E l B W l l B d I i p
' N I
$ N 4 W B
N 5 W I y W I
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l ,l B N L - - - - - - - - - - - - - - - - - - - 10 8----------------------- J
l wwwwwwwwwwwwwwFwwwwwwwwwwwwwwwwwwww.wwwwwww , ; NRC pI p> FORM 618 U.S. NUCLEAR REGULATORY COMMISSION N i l CERTIFICATE OF COMPLIANCE I'OR RADIOACTIVE MATERIALS PACKAGES N
# E , E a CrRTlHCATE NUMBER b REVISION NUMBER S. PACKAGE IDENTIHCATION NUMBER d. PAGE NUMBLR e. TOTAL NUMBER PAGE.S g
r 6346 26 USA /6346/B( )F 1 5 g N L PREAMBLE k l c. This certificate is issued to certify that the packaging and contents described in item 5 telow, meets the applicable safety standards set forth in Title 10 N l $ Code of Federal Regulations. Part 71,' Packaging and Transportation of Radioactive Material." ! l N
- b. This certificate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transpwtation or other.
apphcable regulatory agencies, including the government of any country through or into which the pacLaFe will be tranhported. N
- 3. THIS CEkTIFICATE IS ISSUED ON THE B ASIS OF A S AITTY AN ALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
' k a ISSUED TO(Name and Addren) h. Tr!LE AND IDENTIRCATION OF REPORT OR APPLICATION-. k R E Public Service Company of Public Service Company of Colorado E l Colorado application dated March 28, 1996. E 2420 W. 26th Avenue, Suite 1000 8 8 Denver, CO 80211 71-6346 E g c. DOCKET NUMBfJt g N 6 CONDITIONS , g g This certificate is conditional apon fulfilling the requirements of 10 CIlt Part 71, as applicable,and the conditions specified below. g W s. N B q
# Packaging (a) N
# 5 B (1) Model No.: FSV-1 E B E B (2) Description 4 D . .
. 4 1
2 The FSV-1 is a stainless steel-encased, depleted uranium-shielded cask. d P The cask body is a' cylinder 208-inches'long and 28 inches in diameter, 4 x except.for the top flange area,'which is 31 inches in diameter. The N b cavity,is approximately 17.7 inches in diameter..and 187.6-inches long. g B -. E D The cask may be used in one of seven configurations ~ (A through G) g g depending on contents. . Configurations A, B, C, and'D are used to ship g p solid, non-fissile irradiated hardware; These configurations use an outer g g lid consisting of a 3.75-inch thick stainless steel plate and a 2.25-inch g y thick depleted uranium shield. The lid is bolted to the cask body by 24 g ; p 1.25-inch diameter fasteners. The primary seal;is a silicone elastomeric g ! p seal ring between the outer lid and cask body. Configuration 8 does not g g require an inner container. Configuration C uses a supplemental stainless g g steel shield ring and cover plate. . Configuration D uses a supplemental g g carbon steel shield ring and cover plate. g 9 4 y Configuration E is used to ship Fort St. Vrain (FSV) high temperature gas g , g reactor (HTGR) fuel elements. This configuration uses the stainless steel y l g inner container (as shown in General Atomic Drawing Nos. GADR 55-2-1, g 1 g Rev. C, and GADR 55-2-2, Rev. A) as the containment vessel. The inner g g container lid is a stainless steel shell containing depleted uranium q b 4.15-inches thick. The inner lid is secured to the inner container body , y by 12 0.5-inch diameter fasteners. The primary seal is a silicone g g elastomeric seal ring between the inner lid and inner container body. g l 3 Configuration E is equipped with an impact limiter on the upper end. g l Bj Ef I 9, 0l [ Wl D' @ . p! gl l pl El i Bj 109 dl Nmmrrm7srm a m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m$
5 W W W W W W TF W W W W W W W W W TF TF W W W W W W T TF W W W W W W W W W W W W W W W W W W W g 'NRC FORM 618A roNDmoNs rumimus) U.S. NUCLEAR REGULATORY COMMISSION gl
&" Page 2 - Certificate No. 6346 - Revision No. 26 - Docket No. 71-6346 gl d El h El, M Configurations F and G are used to ship solid non-fissile irradiated and gl , contaminated hardware from the FSV HGTR. These configurations use a 4.75- gr <
st inch thick steel outer lid. The lid is secured to the cask body by 24 El h 1.25-inch diameter fasteners. The primary seal is a molded silicone el gI elastomeric seal ring between the outer lid and cask body. Configurations gl 3 F and G both use an impact limiter on the upper end. Configurations F and g g G also use a burial canister with a 12-inch thick carbon steel plug. The s y shielded spacer in the burial canister is used only in Configuration G. j B E a The overall weight for the FSV-1 package is 46,025 pounds for g j Configurations A, B, C, and D and 47,600 pounds for Configurations E, F, j g and G. g 8 E j (3) Drawings y The FSV-1 package is constructed in accordance with the following !
, drawings: j 5
9 Confiouration A !m 5 National Lead Company Drawing Nos.: 70086F, Rev. 7; 70296F, Rev. 2; and Ni l
- 8 General Atomics Drawing No. 1501-003, Rev. C.
f, Confiauration B 4 9 E B Same as for Configuration A except that an inner container is not E P required. E ! E 9l Confiaurations C and D' E B E s In addition to the drawings for Configuration'A, General Atomics Drawing E f Nos. GADR 55-2-10, Issue D, and GADR 55-2-14, Issue N/C (optional). E s Configuration C uses a. supplemental stainless steel shield ring and cover E 9 plate constructed in accordance with Drawing No. GADR 55-2-11, Issue B. E R Ccnfiguration D uses a supplemental carbon steel' shield ring and cover E; 9 plate constructed in accordance with Drawing No. GADR 55-2-11, Issue A. E B E B Confiauration E E B E l! 9 In addition to the drawings for Configuration A, General Atomic Drawings l s Nos. GADR 55-2-1, Issue C; GADR T,-2-2, Issue A; and GADR 55-2-3, Issue B. El g 9 s! $ Confiaurations F and G il 9 sl p In addition to the drawings for Configuration A, General Atomic Drawings il y Nos. GADR 55-2-1, Issue C; GADR 55-2-2, Issue A; GADR 55-2-12, Issue C; gl g and GADR 55-2-13, Issue A. g! B E' 9 4 9 E %; E 9: W W % E Bj E! 2 ut w .... .. . .. m . _ . . . 110...................... 4 Ej i
7 1 i W I_bdETUNdW TE7 W W T57 ((Fil TE( T57 TET TE( TRI TET TEI i3( W TB7 TNT W TEI TB( 15715( W( TRT TET CONumoNs a,,nn=d> U.S. NUCLEAR REGULATORY COMMISSION g g FORM 618A N,R I 71-6346 $l N I Page 3 - Certificate No. 6346 - Revision No. 26 - Docket No. N
!j !! % 5. (b) Contents $ i (1) Type and form of material g gl Irradiated fuel elements consisting of graphite body, hexagonal in Nf f (i) .
horizontal cross section, approximately 31.2-inches high and 14.2 @l 0 inches across the flats. Prior to irradiation, each fuel element 8 contains thorium and uranium enriched to a maximum of 93.5 w/o in n! 8 the U-235 isotope, or @l w* Wlj (ii) Solid, irradiated, and contaminated hardware, which may include , 8 W 8 fissile material, provided the quantity of fissile material does not W, 9 exceed a Type A quantity and does not exceed the mass limits of 10 CFR 571.53 and neutron source components, or Wl l
# g !
b (iii) Solid, nonfissile, irradiated and contaminated hardware which has ( l 9 been removed from the Fort St. Vrain High Temperature Gas Cooled ( B W l s Reactor and the' surface contamination does not exceed 51 mil 11 curies g s per package. gl i gi i (2) Maximum quantity of material per package ' d
$ g s Decay heat not to exceed 4.1 kw and:
W 9 g s; (1) Item 5(b)(1)(i) above: W si
~ Six fuel elements each containing a maximum of 1.4 kg of enriched gL uranium, having a thorium / uranium ratio greater than 8.1:1 and gl weighing approximately 300 pounds. The gross weight of the cask g g g cavity contents, including the component spacers, inner container, and irradiated fuel elements shall not exceed 4,430 pounds, g
@al g
Contents must be shipped in Configuration E. g Wi s , (ii) Item 5(b)(1)(ii) above: g. The gross weight of the cask cavity contents, including appropriate h component spacers, liners, inner containers, shield rings and solid, lJ p nonfissile, irradiated and contaminated hardware shall not exceed l i 3,720 pounds. Contents must be shipped in Configurations ldl A, B, C, or D. [? (iii) Item 5(b)(1)(iii) above: (m ' J N 9 The gross weight of all of the cask cavity contents, including 8 burial canister and spacers, with or without supplemental shielding $ < I 1 ? 8 shall not exceed 4,430 pounds. Contents must be shipped in Configurations F or G. g l WI 9 Wl i 8f, 4
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~ w w w IrIw w w w w w w w TERir w isi w w TmBiBiBir w w w w w w w w w w w w w w w w w w w w w w g CONDITION romim.eds (NRC 1 96) FORM 618A U.S. NUCLEAR REGULATORY COMMISSION gl s Page 4 - Certificate No. 6346 - Revision No. 26 - Docket No. 71-6346 E m @j M 5. (c) Transport Index for Criticality Control 9 Minimum transport index to be shown on (l!
ti s g label for nuclear criticality control: 100 (jl E' g 6. As needed, appropriate component spacers must be used in the cask cavity when E g l g, shipping the contents described in paragraph 5(b) to limit movement of contents g y during shipment. gl ;) g
- 7. s' '
g g For transport of the contents of Item (b)(1)(ii) in Configuration D, the dose rate measured on the surface of the package must not exceed 200 mr/hr. For the j ' g a purpose of this requirement, the surface of any personnel barrier may not be j considered the surface of the package. s j l 8. The Model No. FSV-1 cask may be wrapped with reinforced plastic when shipping [> g g the contents described in Item 5(b)(1)(ii) or (iii) provided the heat generation rate does not exceed 500 watts. The applicable requirements of 10 CFR 671.87 j l j must be satisfied prior to wrapping the cask. , g
- 9. Use of packaging fabricated after August 31, 1986, is not authorized. ,
l 10. In addition to the requirements of Subpart G of 10 CFR Part 71: 5 ( 8 (a) Configurations A, B, C, and D of the Model FSV-1 shipping cask shall be E i ! 5 prepared for shipment and operated in accordance with the Operating E 1 ! # Procedures of Section 7.0, Volume I, of the application, as supplemented. @ The package shall be maintained in accordance with the Maintenance Program E t 5 in Section 8.0, Volume I, of the application, as supplemented. #
# t (b) Configurations E, F, and G of the-Model FSV-1 shipping cask shall be E l @ prepared for shipment and operated in accordance with the Operating i 5
Procedures of Section 7.0, Volume II, of the application, as supplemented. E B The package shall-be maintained in accordance with the Maintenance Program E s in Section 8.0, Volume II, of the application, as supplemented. E l 5 (c) t '. l b The main flange seals must be replaced within twelve (12) months prior to E any use of the packaging and must be replaced if inspection shows any 6
- 9. defect.
Bj ( 5 (d) El The silicone 0-ring on the inner container primary plug in Configuration E 9 tust be replaced within the twelve (12) months prior to any use of the (l B @ packaging and must be replaced if inspection shows any defect. B E'! N E
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- w w wisidiw w m 5 w w w w w w w w w w w w w w w w w w w w w w w w w w w w w CONumoNs romemwd; U.S. NUCLEAR REOULATORY COMMISION gi g INRC FORM 618A i l j Ei l
Ej i 9l s (34m)Page 5 - Certificate No. 6346 - Revision No. 26 - Docket No. E i 71 B l EI L"I g
- 11. The package authorized by this certificate is hereby approved for use under the lh
' general license provisions of 10 CFR 971.12. E Ei ll ,p I3 12. Effective date: May 1, 1996 Expiration date: May 31, 2001. il s,l 5 s, i i g REFERENCES j s a j Public Service Company of Colorado application dated March 28, 1996. j E s El
- s FOR THE U.S. NUCLEAR REGULATORY COMMISSION
- E
, W. kl i
- 5 m II1
- w _ -
E 8 William D. Travers, Director 5 Spent Fuel Project Office ! 5 Office of Nuclear Material Safety 3 and Safeguards ; l f5' i
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N l E Date: April k , 1996 5
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i I see pones ets U.S. NUCLEAR REGULATORY COttefl8SION I I - CERTIFICATE OF COMPLlANCE I ' I io can n FOR RADIOACTIVE MATERIALS PACKAGES I !
. cEMMICATE NUMptR l D REVislON NUMMR c PACKAGE IDENTIFsCATiON NUMBER l e PAGE NUMBER ~e . TOTAL NUMBER PAGIS I 6347 8 USA /M47 /AF 1 1 9 l l!
~
l : Pne4uste I a. Tnia certificate is issued to cenefy inat ine packaging and contente desenbed in item s below. meets the apphcabie safery standards set forth in Titie to. code l ; l of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Matenat" I l '
- b. Tnis cerishcate does not reheve the consignor from comphance with any requiremer.it of sne reguistions of ene u.s. o partment of Transportation or other N l applicable regulatory agencien, includmg the government of any country througnor into whicn the package will be transported.
I I N I I s7Nigri,,
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, 4ssyu,N tNe sAsis or A 6Arriv ANAtysis naga,1,o,r,t,N,e gg asgogogPPgt e,A,rgow ,
i i General Atomics General Atomic Company Application dated I I i P.O. Box 85608 February 19, 1982, as supplemented. I I San Diego, CA 92186 g ar l g (v -(Xit DC-ly l Q I I ..ooexerNuusen I yi;pg7 I I a coNomoNs . (j /) . I This certificate is conditional upon fulfilhnggequirements of 10 CFR Part 71, as applicable, and the coretions specified below. l
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Inney, container ik,ad875" ID x 34";high,18-gage sidel drum. j} - (] I I l t Inner l container ih' centered l arid iuppbitedi.in a 22.5" ID iI38.25" high,16-gage i i steel Jrum.bVoid spaces Stwee I i the itpar contahutr areffil e
!the inner and outeF container and within i j
th vermiculite. *' Total weight, including I I contentsi w is 500 q NdsN p q G
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i DrawingY Q I i (3) Q{j h I i The packaging'Is constructed in accordance ith General Atomic Company I I Drawing No. FFE-61h Issue D. W I (b) Contents k Y ( 'pk I i (1) Type and form of material I I i I I I Fuel element consisting of a graphite body, hexagonal in transverse I cross-section approximately 14.2" across the flats and 31.2" high. I l Dispersed in columns within the fuel element body there is a maximum 1.41 l kg U-235 plus U-238 and Th-232. The U-235: U-238: Th-232 atomic ratio l i i I is about range 1:0.07:8.3. of 1800 to 1. The atomic ratio of carbon to the U-235 is in the l I I l
,1 (2) Maximum quantity of material per package l l l l One fuel element containing not more than 1.41 kg U-235 and weighing not i I. more than 320 pounds. Total quantity of radioactive material within a I l I
package may not exceed a Type A quantity. I i l I I I I I I I l 114 I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , ,I
l _ U.S. NUCLEAR REGUI.ATORY COMMISSION coNomoNS (continuDd)
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- Page 2 - Certificate No. 6347 - Revision No. 8 - Docket No. 71-6347 l l
I I l 5 . (c) Transport Index for Criticality Control l I l I , Minimum transport index to be shown I ( - I on label for nuclear criticality control: 1.3 h l
- 6. In addition to the requirements of Subpart G of 10 CFR Part 71: l (i) The package must be operated and prepared for shipment in accordance with lIlI the operating procedures of Chapter 6 of the application. I (ii) Each packaging must meet the Acceptance Tests and Maintenance Program of l Chapter 7 of the application. y l 7. The package authorized by thi i c e s by approved for use under the !!
general license provi of 10 CFR 671.12. ll
- 8. Expiration date: hh31,1997. Q l g REFERENCE y General Atomic Companf/)pp55c'ation dated February 19, A I i
MN 4 C I l Supplements dated: h(2ch9,19)8( Fehrpar.y 2 , f;
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Date: /7, ' l l 'J 'Q @O l l lo 4 4*d li l l l l I 1 l l i I I l I I I 5 l i l l l l i i I i I d I E gl l I e l' I us l l l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
1 l pwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwg N "" Ues CERTIFICATE OF COMPLIANCE E
$ ecm n 5I FOR RADIOACTIVE MATERIALS PACKAGFS I 1 a GRTIFICATE NuMBut b REV SiON NUMBER c. PACKAGE I N I MHER N
- d. PAGE UMBER c. TUTAL NU BER PAGES g
k
- 2. PREAMBLE k
- a. This certificate is issued to certify that the packaging and contents described in liem 5 below, meets the applicable safety standards set forth in Title 10 N
$j Code of Federal Regulations, Part 71, " Packaging and Transportation of Radioactive Material."
k
- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation ork othe s
applicable regulatory agencies, including the government of any country through or into which the package will be transported. k n h 3. THIS CERTillCATE IS ISSUED ul ON THE BASIS OF A SAFETY AN ALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION q a.iSSuEo Toru ,oam
- 6. Trn.E ANo loENTiriCATION OF REPORT OR APPLICATION:
s 4 Bj e i Babcock & Wilcox Company Babcock & Wilcox Company application g 5 P.O. Box 785 dated February 28, 1991. s E Lynchburg, VA 24505 E B g G c.noCKETNuMBER 71-6357 g h 4. CONDITIONS g g This certificate is conditional upon fulfilling the requirernents of 10 CFR Part 71, as applicable, and the conditions specified below. g
$ 5 g
B 4 (a) Packaging E g n 4 B (1) Model No.: NNFD-10 g B p q (2) Description g B g The packaging consists of a containment vessel, 5-9/16 inches OD by 4 a g 22-3/8. inches high, constructed ~from a 5-inch scheduled 40 steel pipe g with a screw-type u p and a welded bottom plate. The containment g g vessel .is centered and supported in 'a 55-gallon DOT specification 17C y or 6C steel drum by industrial cane fiberboard. g g l" The nominal gross weightlof the pa' ckaging and contents is 350 pounds. ,N j (3) Drawing d g
! The packaging'is constructed in accordance with Babcock and Wilcox 8 y Fuel Company Drawing No. 1198767E. 4 s 4 E
? 5 5 E E 5 4 5 5 B E B E E E W E 8 W E
- j 4
Bj % 4 s q e h E n g)1 a % di om 9= = = m m m are m m m m m m m .
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's p Page 2 - Certificate No. 6357 - Revision No. 7 - Docket No. 71-6357 E
- W E
E W p 5.(b) Contents W 5 g p (1) Type and form of material E s p Urr.nium metal, alloys or compounds. Uranium may be enriched to any degree g g in the U-235 isotope. g E 9 g (2) Maximum quantity of material per package g E B y Contents shall not exceed 100 pounds, and the U-235 content shall not g g exceed 350 grams. Maximum quantity of radioactive material within the g g package may not exceed a Type.A quantity. g l (c) Transport Index for. Criticality Control' l l Minimum Transport index to be shown on label for nuclear criticality contrc1: lg j - 2.1 8j In addition to'the requirements of Subpart G of.10 CFR Part 71: 6. E
$ (a) Each package must meet the Acceptance cTests and Maintenance Program in j
Chapter 8'of the application'. l (b) Each package shall be operated.and prepared'for ship $tinaccordancewith # the Operating Procedures' in Chapter.7 of the application. G h 2 ' B 7. The package authorized by this certificate is hereby' approved for use under the 8
# general license provisions;of 10 CFR;67.1.12. N 9 ,t . %
8 l @ 8. Expirationdatei April 30,-2001, , s
- E s
B
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REFERENCES (, W , a l n W B Babcock & Wilcox application dated February 28, 1991. 5 8 E B Supplement dated: March 21, 1996. W B E 5 FOR THE U.S. NUCLEAR REGULATORY COMMISSION i B' n f 9 l 4 A/M"L - William D. Travers, Director l W
- $ Spent Fuel Project Office W l 2 Office of Nuclear Material Safety W l
p and Safeguards W ' W B W M Date: Ml\n E s s-
$j E s; E Rj E 5 117
$m m m m m7mrrm m ansnm m m m m m m m m m = = = = = = m m m m m a m a m m m
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powwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwg N "3 " " " " "
C" " CERTIFICATE OF COMPLIANCE N FOR RADIOACTIVL MATERIALS PACKAGES N n
gl t a CtRTinCATe NUMBER n>
- 6. REviSiOouMstR j .. PACKAGE :DENTinCATiON NuMuERd. PAGE NUMBER e. TOTAL NUMMR PAGES 6386 14 I USA /6386/B(U)F 1 4 E s 2. PREAMBLE N{ l
- a. This certificate is issued to certsfy that the packaging and contents described in hem 5 below, meets the apphcable safety standards set forth in Title 10, Nj <
Code of Federal Regulations. Part 71, " Packaging and Transportation of Radioactive Material." k
- b. His certificate does not reheve the consignor from comphance with any requirement of the regulationn of the U.S. Department of Transport 2iion or other N
$ apphcable regulatory agencies, including the government of any country through or into which the package will be transported. Nj N 3. THIS Ct~RTiflCAllIS ISSUED ON THE B ASIS OF A S AIETY AN ALYS15 REPORT OF THE PACKAGE DESIGN OR APP!JCATION a ISSUED TOIName and AddicuJ b TITLE AND IDENTIFICATION OF REPORTOR APPLICATION: k B
g U.S. Department of Energy Safety Analysis Report for 235R001 Nj g1 Division of Naval Reactors p Shipping Container dated August 11, 1970, y p Washington, DC 20585 as supplemented. y B g ' g c. DOCKET NUMBER 71-6386 g l 0. CONDITIONS y g nis certificate is conditional upon fulfilling the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. g
$ i l
B i
, (a) Packaging N l
g l (1) Model No.: 235R001 l . l (2) Description I l E The 235R001 shipping container l structure is horizontal, having an oblong I P cross section and is fabricated from 0.104-inch thick.. carbon sheet steel. N The container is 313 inches'long and has.a maximum weight of 4,640 N 8 pounds, empty. The oblong cross section dimensions'are approximately N . 8 35.5 inches high by 33.0 inches.'. wide. The container was originally I , N designed to ship;unirradiated fuel modulest of the AlG/A4W type. I 8 Subsequently, the container <has'been. adapted to ship AlW-3 fuel modules N 8 using a strongback, partial _ AlW-R3 fuel modules using module support E 4 8 assemblies,. standard size or partial S8G fuel modules by use of a special d 8 frame assembly and cradle clamps, S3G-3 ' refueling modules using cell 4 support assemblies, rodded-or unrodded DIG fuel modules, rodded ASNPP W B b fuel cells and rodded or unrodded D2W fuel cells. The loaded container i < maximum weight is 12,421 pounds. , 4 9 4 8 Drawings (3) a W N B The packaging is constructed in accordance with Container Research e B Corporation Drawing Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005, e
# Rev. O, and Westinghouse Electric Corporation Drawing Nos. 9730425, -
E B Rev.1, 903E693, Rev. 3, Sheet 1, 2 and 3 of 3, and 947J076, Rev. O. ( B-g 9 El gi R p! Bi NI B' ' qi B m. E! a! : BI El b @ b l El , 118 mammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm g d(!
l gwwwwwwwwwww_wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww l I NR FORM 618A coNomONs tc,mimurd, U.S. NUCLEAR REGULATORY COMMISSION g e sj i Page 2 - Certificate No. 6386 - Revision No. 14 - Docket No. 71-6386 l
# E i
l 5.(b) Contents N (1) Type and form of material !e B
!e Unirradiated fuel assemblies of the following types: N 6
i 5 (1) AlG and A4W reactor cell without upper mechanism and with E 5 control rod, leadscrew and shipping fixture installed on rodded # 1 9 type modules. 6
- 5 E
's (ii) A1W-3 rodded-type module without upper mechanism and with control N
- 5- rod, leadscrew, and control rod holddown device installed. G lB E n
' N (iii) AlW-3 unrodded-type module. l $ i n s (iv) Standard size 58G reactor cluster,with regular or substitute E
$ support adapters and regular control rods or Boral poison rods W with control rod holddown devices installed. If only one cell i sll 9 is shipped per container, a dummy load shall be installed for t ,
i balance. E l5 . Partial size S8G reactor ciuster with regular or substitute n W (v) E -
- p. support adapters and regular control rods or Boral poison rods E l gl with control rod holddown devices _ installed. If only one cell E h is shipped per container, a dummy load shall be installed for (
balance. g E l 6 6 , y (vi) S3G-3 refueling cells, with a maximum 'of one 0-1 reactor cell g I y assembly per container. , y j l B 4
- y (vii) DIG fuel module, ' rodded. g
! B G g (viii) DlG removable fuel assembly (RFA), unrodded. g W W ! (ix) AlG fuel cluster, fueled erd only of full AlG reactor cell, gl 9
- y rodded. g g (x) ASNPP fuel cell'with control rod, and control rod holddown device g installed, g y
', (xi) 02W side or central fuel cells with control rod and control rod !
j l l g holddown device. l (xii) D2W corner fuel cells, unrodded. l (xiii) STC fuel cells, unrodded. l l l (xiv) D2W fuel cell and shear block with control rod inserted in rodded fuel cell, l , g yk 6 m! W s Wl p! Wl [ d > l l h E! l M 119 W l "b o mvammverggra m m m = = = = m m m m = = = = = = = = = = = = = = m l
wwwwwwwwwwwwwwwwwwwwwww31wwwwwwwwwwwwwwwwwM g NRC FORM 618A CONDm0NS (umimwdj U.S. NUCLEAR REuULATORY COMMISSIGN no6) g g Page 3 - Certificate No. 6386 - Revision No. 14 - Docket No. 71-6386 l l
- a 5.(b) Contents (continued) ll (2) Maximum quantity of material per package (1) One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(ii), N 5(b)(1)(iii), 5(b)(1)(x), or 5(b)(1)(xiv).
(ii) Two fuel assemblies as described in 5(b)(1)(iv), 5(b)(1)(v), E 5(b)(1)(vi). 5(b)(1)(vii), 5(b)(1)(ix), 5(b)(1)(xi), E 5 5(b)(1)(xii), 5(b)(1)(xiii). E B E B R (iii) Four fuel assemblies as described in 5(b)(1)(viii). E E B (c) Transport Index for Critica11ty Control E 9 ,
+
E W Minimum transport-index to be shown on ' E D label for nuclear criticality control: ' t B 4 p p (1) For the-contents described in 5(b)(1)(ii) W and limited in 5(b)(2)(1): 100 E 9 . . 4 g (2) For the contents described in 5(b)(1)(iii) e and limited in 5(b)(2)(1):, g s - 7.0 ( n - c'
'. E gI (3) For the content's described.in!5(b)(1)(vii), q i 5(b)(1)(viii), 5(b)(1)(1x), 5(b)(1)(x), -
g g 5(b)(1)(xi),.5(b)(1)(xii),s5(b)(1)(xiii)/ , g n 5(b)(1)(xiv),;and limited in 5(b)(2)(i), q g 5(b)(2)(ii),and-5(b)(2)(iii): r 31.3 g ly (4) For contents describ'ed in 5(b)'(1)(1) and g 5(b)(1)(vi), and limited in 5(b)(2)(i) and 4-g 5(b)(2)(ii): g ' 25.0 g (5) For contents described in 5(b)(1)(iv) and l - y 5(b)(1)(v), and limited in 5(b)(2)(ii), and y y shipped with regular control = rods: 25.0 g g l (6) For contents described in 5(b)(1)(iv) and 5(b)(1)(v), and limited in 5(b)(2)(ii), and l , shipped with boral poison rods: 32.0 g b E
- 6. Expiration date: July 31, 1997.
. l E R N D 4 h 8 D N b u ! E D El 4 5 B E B 120 gi bammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma
I i wwwwwwwwwwwwwwwwwwwwwwwwwwwT M Emwwwwwwwww g NRC FORM 618A CONDmONS (umimmeds U.S. NUCLEAR REIULATORY COMMISSION g am , l Page 4 - Certificate No. 6386 - Revision No. 14 - Docket No. 71-6386 l P E REFERENCES l E l5 Safety Analysis Report for 235R001 Shipping Container, WAPD-0P(R)RD-357 dated j!- August 11, 1970. l E
# Supplements: Knolls Atomic Power Laboratory letter AlG 25-159, dated E l8 October 2, 1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, dated E
l8 October 9,1970; WAPD-0P(R)RD-476, dated October 26, 1970; and WAPD-0P(R)RD-488, E lB dated October 30, 1970. Knolls Atomic Power Laboratory letters AlG 25-181, dated E lB April 9. 1971; and AlG 25-191, dated May 11, 1971. Bettis Atomic Power Laboratory E B letters WAPD-0P(R)C-94, dated May 16, 1972; WAPD-0P(R)C-199, dated December 13, 1972; E B and WAPD-0P(R)C-229, dated March 6, 1973. Naval Reactors letters G#5078, dated 5 January 26,1976; G#5776, dated September 8,1977; G#5905, dated January 23, 1978; E B G#5923, dated February 22, 1978; G#6095, dated August 17, 1978; G#6208, dated W i l B March 8,1979; G#6373, dated September 4,1979; G#6813, dated October 17, 1980; E B G#C85-0467, dated July 17, 1985; G#C88-8112, dated October 18, 1988; G#90-03655, W B dated August 10, 1990; G#92-03560, dated June 15, 1992; and G#96-03371, dated E B March 15, 1996. E B d i B FOR THE U.S. NUCLEAR REGULATORY COMMISSION W l E l B l B ( W l ' William D..Tra rs, Director g E
)
j l B i Spent' Fuel Project Office' q B Office of Nuclear Material Safety g i B and Safeguards g i [ Dated: $ N B e N B W l B ? B l B d B n ' E B ' E B E B E
- B
! B E l E I t B E l B ' B W E B N D 8 B N 5 N B B W E N B! M Bl a, l B 121 Wj l Bf 2 l L............................................ l
pw_w w w w m w w w w w w w w w afwrGTZNTWTw w w w w w w w w m 4Ter w w w w w w w w w w w w g g kNRC FORM 618 CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION d hl mm 10 CFR 71 S FOR RADIOACTIVE MATERIALS PACKAGFS %
- 1. a. CERTlf1CATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTif1 CATION NUMBER N
- d. PAGE NUMBER e. TOTAL NUMBER PAGES g
M 6400 22 USA /6400/B( )F 1 9 g L 2 PREAMBLE N ,
- s. This cemficate is issued to certify that the packaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10, k l '!f Code of Federal Regulatmns, Part 71," Packaging and Transportation of Radioactive Material?
- b. This certificate does not relieve the consignor from comphance wah any requirement of the regulations of the U.S. Departmen' of Transportation or other N I applicable regulatory agencies, includmg the government of any country through or into which the package will be transp(w ed. .
k i l 'i
- 3. THIS CE RTlHCATE IS ISSUED ON THE BASIS OF A S AFETY AN ALYSIS REPORT OF Tile PACK AGE DLSIGN OR APPLICAllON
- a. ISSUFD TO INanw nad Adsbru) b TITLE ANDIDENTIFICATION OF REPORT OR APPLICATION. kI l N t ,
9 Westinghouse Electric Corporation Westinghouse Electric Corporation application E B P.O. Box 355 dated August 7, 1981, as supplemented. El' W Pittsburgh, PA 15230 ( , N E N c. DOCKET NUMBER 71-6400 g l $ 4 CONDITIONS g W This certificate is conditional upcm fulfilling the requirements of 10 CfR Part 71, as applicable, and the conditons specified below. g
$ 5.
g 5 W B (a) Packaging g 8 5 g (1) Model No.: "6400 g 5 l p (2) Description E g l b a p A protective overpack'which provides impact and thermal protection for y p its contents. The inner shell (cavity). is approximately 76" x 76" x 172" g constructed of 3/16" thick- and-10-gauge mild steel. - Closure of the g y cavity is by a,1/4"' thick aluminum plate with silicone rubber gasket , , g which is bolted to the main; inner shell. The cavity is centered and ! g supported in an. outer 3/16" thick steel jacket by approximately 32" of N l n polyurethane foam insulation at the' end and 10" on the sides. A N l j removable section or cap consisting of approximately 34" of polyurethane N g foam insulation encased in steel with a silicone rubber gasket is bolted E y to the main outer steel jacket. The overall dimensions of the package N l y are approximately 8' x 8' x 20'. Vent holes are provided on the sides 8 ; and ends of the container. Set into each corner of the outer container 8
!, are standard I.S.0. steel castings. The total weight including weight of N
, the contents is 45,000 pounds.
l (3) Drawings 8 ' l, Packaging is constructed in accordance with one of the following sets of 6 drawings: (1) Protective Packaging, Inc, Drawing Nos. 32106, Sheet 1, e l
; Rev. F and 32106, Sheet 2, Rev. 0; or (2) Westinghouse Electric E 1
E Corporation Drawing No. 2020D08, Sheet I and 2, Rev. 0; or (3) Babcock e N and Wilcox Company Drawing No. Il-D-2130, Rev. 0; or (4) Protective E 5 Packaging, Inc., Drawing Nos. 32106-1, Sheet 1, Rev. F and 32106, W ' 5 Sheet 2, Rev. O, as modified by Nuclear Packaging Inc. Drawing No. Nl , E.G.-60-OlD, Sheets 1 and 2, Rev. 0; or (5) Protective Packaging, Inc. E l k Drawing No. 32395, Sheets 1 through 9, Rev. B, as modified by Sandia E' l E Laboratories letter dated May 8, 1980; or (6) Lawrence Livermore National W
$j Laboratory Drawing Nos. AAA81-108683-00, Rev. O and AAA81-110194-00, E E Rev. O. El #j di > d N
h
% 122 $m m m m m m m m m m m m m m munnsnsTrsnzngn 1 m m m m m m m m mp m m m
p! = w a n w w w isi w is w w w w w ini w w w w w w w w w ini sni ini w w w w w w w w w w w w w w w g N FORM 618A CONDRIONs mmumnds U.S. NUCLEAR REIULATORY COMM2SION g ls E Page 2 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 l l9 WI ( hs 5.(b) Contents !u
%j (1) Large, decontaminated equipment waste of such size as not to fit into a $
8' 55-gallon drum (with legs or other readily removable appendages removed). 5 8 Not to exceed 200 grams plutonium within the package. E i ! 5 W l 5l Equipment waste surfaces containing more than 0.5 C1 must be decon- W 2 l 5 taminated to a smearable level of no more than 150,000 dpm/100 cm prior E l 5 to fixation or until successive decontamination cleaning operations do E l 95 not reduce the smearable contamination levels by more than ten percent. # l After fixation, equipment waste surfaces must have2 a smearable level of E 5 contamination of no greater than 10,000 dpm/100 cm . Outer surfaces must E B have a smearable level of contamination of no greater than 20 dpm/100 cm . E 8 Prior to fixing of contamination, large equipment waste must be inspected I f to insure that: (a) all sharp or protruding objects have been removed, E B blunted or protected with packaging material, and (b) pipe caps, gasketed E 5 blind flanges, covers, etc., have been installed wherever possible. W B Following such inspection, the inner surfaces containing more than 0.5 Ci W l 5 must be fixed with " strip" or " clear" coating. The inner surface (s) may 6 l B alternatively be fixed with a polyurethane foam. El l > The large equipment waste must be enclosed "in a tight-fitting, 1-inch 6 9j thick plywood box constructed in accordance with Westinghouse Electric E l B; Corporation's Drawing No. 1620E43, Sheets 1, 2, 3, and 4, Rev. 3; a tight a
# fitting 3/16" thick corrugated steel' box constructed in accordance with 8 i Rockwell Hanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. O N N (modified or unmodified); or enclosed in'a tight fitting box constructed 4
- 9 in accordance with General Electric Company Drawing Nos. 908E614, Rev.1, g l B and 908E619, Rev. 2 or 908E648, Rev. O or 908E649, Rev. 0; or enclosed g p in a tight fitting box constructed.in accordance with Babcock and Wilcox g g Company Drawing No. LRC-70019 H, Rev
- 2. The space between the equipment g 3 and the box must be filled'with foam (l" minimum foam thickness) and g l 3 between equipment (1/2" minimum foam thickness). Alternatively, q l 3 gloveboxes contaminated and fixed as described above may be broken down g y as follows: g 4
9l g Glovebox windows are removed and separately phckaged in 12-mil thick PVC g ! g bags and sealed. The inner bag is tape sealed and the outer bag is heat g g sealed. g i 8 s m Glovebox panels are cut to dimensions to fit inside the 3/16" thick g j corrugated steel burial crates constructed in accordance with Rockwell Hanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. 0 (modified or g g g g unmodified). All sharp or protruding objects are removed, blunted, or g g protected with packaging material. The glovebox panels are bundled such g g that internal box surfaces are facing inward. Cut glovebox panels from g i y not more than one glovebox are banded with metal strap banding such that g y two metal strap bands in each direction are placed around the length and g g width of the glovebox sections. The glovebox window and cut panel y y packages are enclosed and foamed in place within the box. g a g i Blocking or dunnage is placed within the box to ensure a one inch foam g i 2 barrier on the sides and bottom of the box. Likewise, dunnage is y l @ provided between the banded glovebox sections to maintain a 1/2" thick y p foam barrier between banded packages. 4 5 ... .......mmm.... m. m g m m cw====m .....--=4
l p{
- Ej Page 3 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 l
P El E l h 5.(b) Contents (continued) f?
!8 (2) Decontaminated hard waste items, such as equipment, metal cans, tools, $l etc., must be double bagged within 12-mil thick PVC with each bag heat l Nj sealed. The total fissile quantity of all the sealed packages in one li N
h B container must not exceed 200 grams. [ Hard waste surfaces must be 2decontaminated to a smearable level of no @ E more than 150,000 dpm/100 cm prior to fixation or until successive
$ decontamination cleaning operations do not reduce the smearable ]N N contamination levels by more than 10 percent. After fixation, hard waste El 9 surfaces must have a smearable level of contamination of no greater than El 2
9 10,000 dpm/100 cm . Prior to fixing of contamination, hard waste must be N N inspected to insure that sharp or protruding objects have been removed, E R blunted, or protected with packaging material. Following such inspection, E N the outer surfaces must be fixed with " strip" or " clear" coating. Hard 6 9 waste items such as furnace shells, muffles, or other items with large r B cavities not accessible for decontamination must be filled with foam H R within the cavities. Surfaces that are not easily accessible, e.g., 6 B interiors of small diameter tubing and piping which were in contact with E N process materials, must have been swabbed or immersed in cleaning E 9 solution to insure removal of residual material. Open ends of the tubing 4 , 9 and piping must be sealed using mechanical fittings. Ej ! 9 n 1 L Alternately, large heavy walled process glassware must be painted inside (
% and outside to fix contamination and double bagged in 12-mil thick PVC E p with each bag heat sealed. ,The glassware must be secured in a box g g constructed in accordance with General Electric Company Drawing No. g I
W 272E81-4, Rev.- O. . The box must be filled with foam and total activity n! g limited to less than two (2) Ci in a box. g
# E p AlternatelyL stainless steel transfer tubes and HEPA filters must be g b double bagged in 12-mil thick PVC with each bag heat sealed. The g g tubes / filters must be secured in a box constructed in accordance with g g General Electric Company Drawing No. 272E81-28, Rev. O. The box must be q g filled with foam and total activity limited to less than 0.5 Ci in a box. g 9 0 g Alternately, round steel ducting must be capped and secured in a box g g constructed in accordance with General Electric Company Drawing No. g g 272E81-29, Rev. 0; 272E81-30, Rev. 0; or 272E81-31, Rev. O. Outer y g surfaces ducting will2 have a smearable level of contamination no greater g l g than 20 d/m/100 cm . The box must be filled with foam and total activity g g limited to less than 0.5 Ci in a box. g
! B W l B ' 4 B l N b b Wl ql B E Wl e M 4 N E' l Bj l El 9 s 7mnu m m m m m m m m m m m m ansnanwavrm m m m mammmmmmmmmmmmmmmmmmmhi
1 fiWWWWWWWWWWTurewiWhimmwwwwwwwwwwwwwwwwwwwwwwwwwww mNDmoNs umumwd> l g NR FORM 618A u.S. NUCLEAR REGULATORY COMMISSION g di El l Page 4 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 5.(b) Contents (continued) Ej N i Sealed packages and boxes of hard waste must be enclosed in a tight-fitting, 1-inch thick plywood box constructed in accordance with [ Westinghouse Electric Corporation's Drawing No. 1620E43, Sheets 1, 2, 3, 8 l Bi and 4, Rev. 3; a tight-fitting 3/16" thick corrugated steel box B' N ' ' s constructed in accordance with Rockwell Hanford Operations' Drawing No. I W{ H-2-91888, Sheet 1, Rev. 0 (modified or unmodified); enclosed in a tight E sj fitting box constructed in accordance with General Electric Company Wl B Drawing Nos. 908E614, Rev. I and 908E619, Rev. 2 or 908E648, Rev. O or El l
#j ! 908E649, Rev. 0; or enclosed in a tight fitting box constructed in d '
l l % accordance with Babcock and Wilcox Company Drawing No. LRC-70019 H, E; l 6 Rev. 2. The space between the packages and the box must be filled with N l W foam to a minimum thickness of 1 inch. Void spaces between the sealed W ) W packages must be filled with foam-(1/2" minimum foam thickness). d' i
, B W l N (3) Glove box absolute (HEPA) filters must be double bagged within 12-mil 4; I W thick PVC, with each bag heat sealed and packaged within DOT E p Specification 17H or 170 steel drums (maximum size of 55 gallons). Each 4 l p drum must be lined with a sealed plastic liner and equipped with a E l 9 standard drum closure. Each drum must not exceed a fissile quantity of a W
I 60 grams. Sealed. drums must be enclosed in a tight-fitting 1-inch thick g l g plywood box constructed in accordance with Westinghouse Electric g g Corporation's Drawing No. 1320E43, Sheets 1, 2, 3, and 4, Rev. 3; a g tight-fitting 3/16" thick corrugated steel box constructed in accordance a g! with Rockwell Hanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. O g p , g (modified or unmodified); enclosed in'a tight fitting box constructed in g
- , accordance with General Electric Company Drawing Nos. 908E614, Rev. I and g l 908E619, Rev. 2, or 908E648, Rev. O, or 908E649, Rev 0; or enclosed in a g i
- p; g tight fitting box constructed inlaccordance with Babcock and Wilcox g Company Drawing No. LRC-70019 H, Rev. 2. The space between the drums and g . g l g the box must be filled with foam to a minimum thickness of 1 inch. Void g l
9 spaces between drums must be filled with foaa (1/2" minimum foam g g thickness). g i ly (4) Soft waste items such as sheeting, gloves, paper, prefilter media, l polyethylene bottles, shoe covers, etc., must be double bagged in 12-mil y , y thick PVC, with each bag heat sealed (bag size must not exceed 22" x 16" g l l g x 10") and packaged within DOT Specification 17H or 170 steel drums g i (maximum size of 55 gallons). Each drum must be lined with a sealed g i g plastic liner and equipped with a standard drum closure. Each drum must y g not exceed a fissile quantity of 60 grams. Sealed drums must be enclosed y in a tight-fitting 1-inch thick plywood box constructed in accordance g ; N ! with Westinghouse Electric Corporation's Drawing No. 1620E43, Sheets 1, g N 2, 3, and 4, Rev. 3; a tight-fitting 3/16" thick corrugated steel box g l 8 constructed in accordance with Rockwell Hanford Operations' Drawing No. 8 8 H-2-91888, Sheet 1, Rev. 0 (modified or unmodified); or enclosed in a 8 tight fitting box constructed in accordance with Babcock and Wilcox > # Company Drawing No. LRC-70019 H, Rev. 2. The space between the drums and l 8 y the box must be filled with foam to a minimum thickness of 1 inch. Void spaces between drums must be filled with foam (1/2" minimum foam
% l f thickness). ,
s' Wl l l b N.
>!i Nl s e t r
#EmTEin mrEFaira m KIurim m_m m m a m a m m m m m m m m a a m m m m m m m m m m m m m
wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww*1a(w g NRC FORM 618A C m pitto h rm ud, U.S. NUCLEAR REGULATORY COMMISSION gl 046) g g J Page 5 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 fl d i[ 5.(b) Contents (continued) [ fl 8' (5) Liquid waste (decontamination solutions only) must be solidified in concrete in a 30-gallon drum which must be sealed in a plastic bag and b 9 e centered and supported in a DOT Specification 17H or 17C 55-gallon steel #l
# drum by absorbent material. The 55-gallon drum must be lined with a Nl N sealed plastic liner and equipped with a standard drum closure. Each drum El 4 must not exceed a fissile quantity of 60 grams. El dj B Alternatively, liquid waste is solidified in concrete in maximum size one N B (1) gallon packages which are double bagged and heat sealed in 12-mil W ll s{q thick PVC and placed with a DOT Specification 17H or 17C steel drum E!
Wl (maximum size of 55 gallons). The drum is lined with a sealed plastic nl W liner and equipped with a standard drum closure. Each 55-gallon drum must tl 9 not exceed a fissile quantity of 60 grams. For drums smaller than 55 % W gallons, the total fissile quantity of all the sealed packages (drums) in El
# one container must not exceed 200 grams. Sealed drums must be enclosed (!
e in a tight-fitting 1-inch thick plywood box constructed in accordance (ll 9 with Westinghouse Electric Corporation's Drawing No.1620E43, Sheets 1, E p I 2, 3, and 4, Rev. 3; or a tight-fitting 3/16" thick corrugated steel box i W constructed in accordance with Rockwell Hanford Operations' Drawing No. g hl H-2-91888, Sheet 1, Rev. 0 (modified or unmodified); enclosed in a tight- g g fitting box constructed .in accordance with General Electric Company g pl Drawing Nos. 908E614, Rev. I and 908E619, Rev. 2 or 908E648, Rev. O or g gl 908E649, Rev. 0; or enclosed in a tight fitting box constructed in g , i accordance with Babcock and Wilcox Company Drawing No. LRC-70019 H, g; g' Rev. 2. The space between the drums and the box must be filled with foam g t g to a minimum thickness of I_ inch. Void spaces between drums must be g g filled with foam (1/2" minimum foam thickness). gl B El g (6) Uranium 233 oxide and. thorium oxide in the form of intact LWBR-type fuel g! g rods with the following limitations: gl lg (i) Rods must be packaged within the Model No. 6400 packaging as described in Section 1 of WAPD-LP(FE)-220, Rev. 3 (February 1983); . g l (ii) The fuel content must not exceed 50 kg U-233 per shipment; l f g (iii) All rod storage containers must be filled to capacity (at least 70% of cross-sectional area) with rods or aluminum shim stock; l g 8 (iv) Each rod storage container must contain not more than one sub- 5 container of 5/9 or 12 w/o BMU seed rods; Each rod storage container must weigh not more than 2,000 pounds; f l (v) l (vi) The fuel rod heat generation must not exceed 30 watts; and 8 1 (vii) Operating Procedures and Acceptance Tests and Maintenance Program Ul h must be modified to meet the requirement of Item 11 of this approval. g h 4[ p El E E U; i 126 $ 8m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m
l l wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww l g NRC FORM 618A roNDmoNS fomtmwo U.S. NUCLEAR REGULATORY COMMISSION g (3% Page 6 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 E
?
5.(b) Contents (continued) !m 5 (7) Liquid analytical residues from the dissolution of spent reactor fuel l 8{ rods, solidified in cement (see table, p. 3 of application *). The cement - is contained in 1.5-gal steel can closed with a slip cover lid. The two E Blj primary cans are packed in a secondary steel can sealed with a press fit El i 5; lid (see Figure 2 of application *). The secondary containment package E Bj contents are placed within a radiation shield (lid secured with six (6), # 8j 1/2"-13UNC bolts with welds in accordance with application *) centered in W l I Rj a DOT Specification 17-C 55-gal steel drum (see Figure 1 of 4 l 9 9 application *). The drums are sealed with styrene-butadiene rubber gasket 4 l b. contained with a standard drum closer. Total weight of the drum will be E i $ less than 1,450 lb, and each drum will not exceed a fissile quantity of W l Bl 12 g and 435 Ci of fission products. W l i klj
$ Six (6), 55-gal sealed drum assemblies will be enclosed in a tight-N E
l W fitting 3/16-in thick corrugated steel box constructed in accordance with 9 l 9{ Rockwell-Hanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. 0 E i b (modified or unmodified). The space between the-drums and the box must d l i i be filled with foam to a minimum thickness of 1-inch. Void spaces q l pl between drums must be fitted with foam to a minimum thickness of ( l l g 1/2 inch. Two'(2) _ corrugated steel box assemblies may be transported in E I l g the packaging. N l 2 4 l a E h
- U.S. Department of Energy letter dated April 15, 1983. g N
El g (8) Uranium 233 oxide and thorium oxide in the form of intact LWBR-type fuel y gi rods with the following limitations: g B N g (i) Rods must be packaged as shown in Figure 4,. Application dated g g July 8, 1983, and contained within the Model No. NNFD-SA-2 g l g packaging (Certificate of Compliance No. 5910); g N l (ii) The fuel content must not exceed 2.0 kg U-233 per shipment; g l l (iii) Each loaded LWBR Rod Transport Box must weigh not more than 99 l pounds; g l 9 l (iv) The fuel rod heat generation rate must not exceed 2 watts; and l l l (v) Operating Procedures and Acceptance Tests and Maintenance Program l , must be modified to meet the requirement of Item 11 of this l approval. g B N W 4 5 W s N Bj d d Bj
- p. a E N N
>l B; W Bj W Bi L......................................a 127 f
g NRC FORM 618A CONI)tTIONS (owmwe U.S. NUCLEAR REGULATORY COMMISSION g . g m l g Page 7 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 l p Nl 5.(b) Contents (continued) B N (9) Maximum of four (4) Cf-252 sources with the following limitations: f I B (i) Each source must be doubly encapsulated with the inner capsule N' B meeting the requirements for special form radioactive material; E p E ! B (ii) The total Cf-252 content must not exceed 6.1 mg; E B N B (iii) The sources must be packaged in a shielded container as described E B in Chapter 1 of WAPD-LP(CE)P08-591 (January 1984); and W B E D (iv) The decay heat generation from the source material must not exceed E B one watt. 4 B E R (10) Compressed krypton-85 gas in mixture with other non-radioactive gases E 5, that are chemically compatible with the 3AA2015 cylinder. No fissile E p material (Requirement of 5.(c) does not apply). Shipment of krypton-85 n p gas is subject to the following limitations: E B . E y (1) Radioactivity not to exceed 2,700 curies. ' Maximum internal decay q. p heat not to exceed 15 watts. Maximum volume of krypton-85 and q 1 y other non-radioactive gases shall not exceed 1480 liters at STP g y (1 atm, 25'C); g a . . (ii) The maximum initial fill pressure shall not exceed 500 psig at ( [ g 25'C; g gl Wl 4 g (iii) The DOT Specification 3AA2015 gas cylinder shall be certified for g y an operating load of 2,015 psig, at least once every 5 years by g g testing to 3,360 psig; y ly (iv) A minimum of 24 hours after loadihg with krypton-85 gas the krypton packaging primary containment shall have a leak rate of less than g
, 0.0014 microcuries per second. The leak test shall be performed g , with the containment vessel within the lead shield container prior g g to placement within its thermal overpack; g (v) Content of the package shall be verified by mass spec analysis; l
l (vi) Acceptance, maintenance and use of the krypton package shall be in , accordance with the procedures and requirements of Chapter 7 and 8 l g of Westinghouse Idaho Nuclear Company, Inc. Report No. WIN-236, l Revision 1, March 1988. The retaining ring shall be tightened N around the gas cylinder to a 40 to 50 inch-pound torque; N l 0 (vii) The position and securement of the krypton package within the Model 8 No. 6400 is as specified in Westinghouse Idaho Nuclear Company, 8 Inc. Drawing No. 059888; f (viii) Krypton package must be enclosed within a tight fitting plywood box constructed in accordance with Westinghouse Idaho Nuclear Company, E g 9 Inc. Drawing No. 059886. gl
- b. E 8
128 4 k a msomnsrm a a a = a a mnvasca m a m m a ,a m m a m m macm m m m m m m m m m a , ,m m m$
l wwwwwwwwwwwwwsWwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww g NRC FORM 618A coNotrioss tr,=rmuds U.S. NUCLEAR REGULATORY COMMISSION gl l Me) gl f l pI Page 8 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 di ! 5.(c) Transport Index for Criticality Control l 5 Minimum transport index to be shown on E l 8 label for nuclear criticality control: 100 #
$ E The polyurethane foam must be Instapak 200, or equivalent.
8 6. E B 4 s 7. The maximum weight of the contents including secondary packaging, dunnage, N B shoring and bracing must not exceed 30,000 pounds. N B E R 8. Sufficient dunnage, shoring and/or bracing must be utilized to minimize W Bj secondary impact of the secondary packaging within the cavity under accident E 9 conditions. W , B E B 9. Protrusions from secondary packaging such as lifting eyes, etc., must be W D positioned such that they will not contact the cavity walls, or shoring must be E p provided to prevent puncture of the cavity walls by the protrusions under the E accident conditions. D E , 9 N g 10. Contents must be positioned in the cavity such that the center of gravity of N p the loaded package is substantially the same as the center of gravity of an d p empty package. W
$ - , a g 11. The cavity of the overpack must be vented through an absolute filter to q p equalize pressure between tro outside and inside of the overpack. g
- r. E
@ 12. Contents packaged under the conditions of this certificate of compliance are g j exempt from the requirement 3 af 10 CFR 671.63. Condition 5(c) of this certificate of compliance is not applicable where the fissile material is g
y g g excluded as provided by 10 CFR 971.53. g E B, 13. In addition to the requirements of Subpart G of 10 CFR'Part 71, the package g must be prepared for shipment, operated, and maintained in accordance with g g{ g " Operating Inspection and Maintenance Procedure No..CSK-003, Rev. 0," included g
, in the Westinghouse Electric Corporation supplement dated April 14, 1992. g
- 14. The package authorized by this certificate is hereby approved for use under the lp g general license provisions of 10 CFR 571.12.
- 15. Expiration date: June 30, 1997. l-l p V p A B E B N :
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___w w w w W w ur w w w W W w w ar w w w w w s w w W w W W W W W W WFW W W w W w W W w W W W gI CONumoNs inmim-di U.S. NUCLEAR REGULATORY COMMISSION gl (NRC 3-96) FORM 618A 8 Page 9 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 N p N l i p d i k, REFERENCES N U N{ B Westinghouse Electric Corporation application dated August 7, 1981. U
${l W General Electric Company supplement dated: October 1, 1981.
W E B E D Babcock and Wilcox Company supplements dated: March 8, 1982; and January 10, 1985. # B W D Department of Energy, Division of Naval Reactors, supplements dated: April 22, and 4 5 July 8, 1983; and March 5, 1984. E B 4 b Department of Energy, Chicago Operations Office, supplement dated: April 15, 1983. E D E B Department of Energy, Washington, DC, supplement. dated: June 6, 1988. E R ... E p Westinghouse Electric Corporation' supplement dated: April 14, 1992. E D E F G p FOR THE U.S. NUCLEAR REGULATORY COMMISSION q N 4
. M' '" ?-. g 3 -William D.~ Travers, Director g
- p. . Spent' Fuel Project Office g 4 Office of Nuclear Material Safety g g t r and. Safeguards q l Date: 3, dt.? M g a ,
a B 4 9 4 B . E
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B d D E R d N E b E D E D E R E B 4 5 E N I B d D E D d b 4 b d b W R H , Bl 8 m el al u B 130 W b=maaaama aaa aaaama mamamaamamaamaaamaamammaamaad
w w w iT@ w w FiRiFiF@ w w.y w womuntw iner w w w w w w w wTars w w w w w w w w w w w w w NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION gI l P* CERTIFICATE OF COMPLIANCE J { iocrnri l'OR RADIOACTIVE MATERIALS PACKAGES % E ' l L a cisrinCATt Nuunis b Revision NeuntR c PAcKAct:Di NTiriCAriON NeuntR 4 Pace Nt watR e TOTAt Nt usi R Paces g I 4 l 6406 10 USA /6406/AF 1 gl
- 2. PREAMhti k
$ a. This certificate is issued to certify that the packaging and contents described in Item 5 below, nects the apphcable safety standards set forth m Title 10, N i $g Code of I:ederal Regulations, Part 71,' Tac kaging and Transportation of Radioactive Matenal." W
, b. This certificate does not . dieve the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportation or other
$j apphcable regulatory agencies, including the government of any country through or into which the package will be transported. 4 5 W d
W; 3 THis cLRTIflCATEIS ISSUED ON THE BASIS a issutDTom ~,ns4ss,ruJ OFAND h TITLE A IDENTIFICATION S ARTY ANALYSTS OF REPORT OR REPORT APPLICATION:OF THE PACKAGE DLSIGN k OR AP a j U.S. Department of Energy Division of Naval Reactors U.S. Energy Research and Development Administration application dated si j g g Washington, DC 20585 July 19, 1977, as supplemented. f
- c. LXX'KET NUMBER
- 4. CONDITIONS .
g This certificare is conditional upon fulfilhng the requirenrnts of 10 CIR Part 71, as applicable.and the conditions specified below. g
- 5. g (a) Packaging N d
(1) Model No.: .None specified 8 8
. (2) Description N 5 d B Specific packaging is not required. ' Safety is independent of packaging. d B 4
' P (b) Contents d
- E B
(1) Type and form.of material' N E E B Unirradiated fuel assemblies lof the following typesi d 9 d B (i) S5G Fuel Experiment Assembly (FEA) in the Model No. FEA shipping g W container. d b d D (ii) S5G Double.. Fuel Experiment Assembly (DFEA) in the Model No. DFEA q h shipping container. E B E E (iii) AlW-3 Removable Uninstrumented Subassembly (RUS) in the g p Model No. 25.0 shipping container. g 5 5 5 (iv) A1W-3 Prototype "A" Module or AlW-3 Shipboard "A" Module in the g 3 Model No. 2.7/3.6 shipping container. g B WI y (v) Rodded instrumented SIC fuel module in the Model No. 7481E12 gl g shipping container. gl l . Et l p! (vi) SIC fuel module or SIC peripheral assembly in the Model No. SIC g! p! l bird cage shipping container. ql g\ q 5\ d (vii) SIW-3 Removable Subassembly (RSA) in the Model No. SlW RSA/ Metal g (I Box. d; E g f "! (viii) S5W-2 Removable Subassembly (RSA) in the Model No. S5W RSA/ Bird gl
- p Cage. El l gI dj 8
h A . ... _ . . .. . . . . . . .. .. 131 ..................... -
gwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwg; i p NRC FORM 618A CONDmONS nonunu,4; U.S. NUCLEAR REGULATORY COMMISSION g B El Page 2 - Certificate No. 6406 - Revision No. 10 - Docket No. 71-6406 , P di l h 5.(b) Contents (Continued) N! l Y\ , i %sj (1) Type and form of material (Continued) 6 9 d .> 4 B (ix) S5W-R2/R3 or S5W-2 module in the Model No. S5W New Module B container. E B Er . 9 (x) A1W-2/R2 cluster or half cluster in the Model No. 658C shipping 4l B container. El 9 d B (xi) S3G-2A/2B fuel module in the Model No. 7481E12 or Model No. 95K218 N B shipping container. E D E D (xii) D2W rodded fuel cell =orunrodded corner type D2W fuel module in a E D Model No. 658H1AB shipping and storage container. Rodded type fuel N p module shall.have a control rod and control rod holddown device 4 p installed.. , g , B .X e . E t ! p (xiii) S7G unit cell or reactor cell assembly in a Model No. 658EIAB gl p shipping and storage container, with shipping clamp installed. g B E y (xiv) Advanced Test Core (ATC) welded fuel ~clustep or ATC cage assembly g ! p fuel cluster in a Model.No. 66081/660C1 container. g B E a (xv)' DIG fuel module {iri a model'572Al or 572B1 shipping container and g [ in a Model No. 573Al or 573B1 g y
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1 DIG Removable shipping Fuel Assembly container.:.A control ro(RFA)d'and 'controle rod holddown device g l 9 need not be installed in the DIG fuel module. g l (xvi) DIG . Removable FuelL Assembly (RFA) in a Model' No. 573Al or 573B1 g shipping container. l g (xvii) PWR Core 1 (Seed 2, 3. or,4) >unrodded seed fu'el assembly or PWR lg Core 2'(Seed 1 or 2) unrodded seed fue1 assembly, in unspecified l g g shippingJcontainers. . g l (xviii) PWR Core 1 (Seed 2;' 3 or 4)!unr'odded seed fuel subassembly or PWR
, Core 2 (Seed 1 or 2) unrodded seed fuel subassembly, in unspecified l t shipping containers. , l 1 N
(xix) S8G rodded fuel cell in unspecified shipping container with control N rod holddown device installed. l ; (xx) S5G type unit cell in a Model No. 658EIAB shipping container. U (xxi) A1W-3 Prototype Peripheral Subassembly or AlW-3 Prototype Center I ; Subassembly in the Model No. 2.7/3.6 shipping container. ' 8 (xxii) 57G Partial Fuel Cell Subassembly in a D0T specification (Type 20 8 ; l WC-3) container. l i . Bj u b} E a , 132 E _.........................................n .
i W W W W W W W W W W Bf W W W W WI W W WT W W W W W Wl W W W W 5 W Wi W W W W W W W W Mt WI W W W W cosomoss <c ,s> u.s.nucteAn neoutArony couuission gl pl n,n,c,ronusina Bj E i Page 3 - Certificate No. 6406 - Revision No.10 - Docket No. 71-6406 f l
.i E 5.(b) Contents (Continued)
~
f Type and form of material (Continued) f (1) (xxiii) S5G Central Subassembly B (xxiv) S3G-3 Removable Noninstrumented Fuel Assembly (RNFA) in a Model E B No. 95K-218 shipping container. E B E B (2) Maximum quantity of material per package E D E B (i) One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii), E
# 5(b)(1)(iii),5(b)(1)(iv),5(b)(1)(v),5(b)(1)(vi),5(b)(1)(vii), E 9 5(b)(1)(viii),5(b)(1)(ix)',5(b)(1)(x),5(b)(1)(xi),5(b)(1)(xii), E B 5(b)(1)(xiii),1 5(b)(1)(xiv),s5(b)(1)(xvi), 5(b)(1)(xvii), E B 5(b)(1)(xviii); 5(b)(1)(xix), 5(b)(1)(xx), 5(b)(1)(xxii), E p 5(b)(1)(xxiii), and 5(b)(1)(xxiv). ~
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n p (ii) Two fuel assemblies as described in 5(b)(1)(xv). E D - T E p (iii) Three fuel ' assemblies as described;in 5(b)(1)(xxi). E p -
,. s g g (c) Transport Index for Criticality Control c',, ;. , N g 1 4 g
pl Minimum transport index to be shown on' , s q
- p. label for nuclear criticality; control: i; '
.c g pl . . +-c.< <
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l (1) For the contents describ'ed in'5(b)(1){iv); 5(b)(1)(vi), g g , 5(b)(1)(xiii),5(b)(1)(xiv), g 9 5(b)(1)(xi),5(b)(1)(xii)i),15(b)(1)(xix);'5(b)(1)(xx), 5(b)(1)(xy),5(b)(1)(xvi y B 5(b)(1)(xxi),5(b)(1)(xxi_i),-5(b)(1)(xxiii), < g y and 5(b)(1)(xxiv), and limited in 5(b)(2)(1), Q g , 5(b)(2)(ii),. and 5(b)(2)(iii):;, - p 100 g lp (2) Fortheconthnts'describedin5(b)(1)(iii), l l 5(b)(1)(v),5(b)(1)(ix),.5(b)(1)(x),and g g 5(b)(1)(xviii), and limited in 5(b)(2)(1): 62.5 g l (3) For the contents described in l g 5(b)(1)(viii) and limited in 5(b)(2)(i): 41.7 g I U (4) for the contents described in l 5(b)(1)(vii) and limited in 5(b)(2)(i): 31.3 l I (5) For the contents described in l 5(b)(1)(xvi) and limited in 5(b)(2)(i): 15.7 g l N (6) For the contents described in l 5(b)(1)(1) and limited in 5(b)(2)(1): 41.7 l g ; I (7) For the contents described in l h 5(b)(1)(ii) and limited in 5(b)(2)(i): 100 g i B! E l b E l Bl j 133 E I Nmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm5
1 l Tafiii w w wfii7 m a w w w w w w w w w w w w w w w w w w w w w w w w w a w w w w w w w w w w w g! NRC FORM 618A coNomoNs tomrmwds U.S. NUCLEAR REGULATORY COMMISSION g! (3%) P Page 4 - Certifi: ate No. 6406 - Revision No. 10 - Docket No. 71-6406 f E e$ 1 5 6. Expiration date: Dacember 31, 1997. N B $ 9 E B 6 s REFERENCES E B W W E B U.S. Energy Research and Development Administration application dated July 19, 1977. Ni 9 4 5 Supplements: Department of Energy letters G#5868 dated January 4, 1978, with E , 5 enclosures; #6291 dated July 13,1979; G#7609 dated September 30, W 9 1983; G#C85-0435 dated April 19, 1985; G#C87-8027 dated E W December 23, 1987; and G#92-03690 dated September 11, 1992. E B E 5 _ E B FOR THE U.S. NUCLEAR REGULATORY COMMISSION N B 4 s s l g William b. Travers, Director g 4 - Spent Fuel' Project Office g y 0ffice of Nuclear Material Safety g pl and Safeguards g 7 e I g Ej Date: $ 49.C( f g sj E sj E 9' W B 4
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g INRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION g! I p> CERTIFICATE OF COMPLIANCE
**" FOR RADIOACTIVE MATERIALS PACKAGES Nl!
g! I a CLRTIMCATE NUMBLR b. REVISION NUMBER c. PACK AGE IDENTIFICATION NUMBER d. PAGE NUMBER c. TU1 AL NUMBER PAGES gl P 4 _fi441 6 USA /6441/Bf )F 1 3 L 2. PREAMBLE N'
- a. Thm certificate is inued to certify that the pac kaging and contents desenbed in item 5 below, mecis the applicable safety standards set furth in Title 10 N
$ Cixie of Federal Regulations. Part 71.
- Packaging and Transportation of Radioactive Matenal." !I
- h. This certifmate 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,includmg the government of any country through or into which the package will be transported. !!!
$ 51 I - 3 THIS CERTIFICATE IS ISSUED ON THE B ASIS OF A S AIETY ANALYSIS REPORT OF THE PACK AGE DLSIGN OR APPLICATION a ISSUED TO(Name and Addern) b. TITLE AND IDENTIRCATION OF REPORT OR APPLICAT10N. k I $ (1 8 U.S. Department of Energy Safety Analysis Report for D2G Power Unit E N Division of Naval Reactors Shipping Container dated August 4, 1969, E Bl kshington, DC 20585 as supplemented. E B E pl e.DOCKETNuMBER 71-6441 g B d. CONDITIONS g p This certificate is conditional upon fulfillmg the requirements of 10 CIR Part 71 as applicable, and the conditions specified below. g @ 5.
g 5 W B (a) Packaging N 4 Bl 4 9 (1) Model No.: .D2G Power Unit E . W D (2) Description d n . 6 B The D2G Power Unit shipping container assembly consists.of five main u
?j assemblies; (1) the barrel assembly, (2) the upper cover, (3) the lower g s cover, (4) the main shipping skid, and (5) the barrel trunnion supports. g B To prepare the power unit shipping container for shipment of a power unit, a 5 the container barrel is rotated to the vertical position, the upper cover g 9 is removed and the power unit is-loaded into the barrel and secured in the g B container with eight (8) shipping studs. The upper cover is then installed g p and the container is rotated to the horizontal position for shipment. The g p container assembly is 31 feet long_ and 8-1/2 feet wide and it is attached g ;
y to a government owned permanently assigned depressed center railroad car; g j p the maximum Feight above the rails is 13 feet, 10 inches in the shipping g p configuratic.i. The power unit is shipped complete with design control rods g 3 and mechanisms installed. g d I W ' e a s E , B E i 1 pl g l 9 1
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l !! mj E, 5.(a)(2) Description (continued) E sj t l, Bj The closure head in a Type A and Type B power unit contains an integral 2l 9 bolting flange. This type of power unit is retained in the container by E B means of eight shipping bolts which clamp the power unit to the barrel E R upper flange of the shipping container. The control rods in a Type A or B 8 9 power unit are restrained in the power unit by means of control rod hold- E ! 5 down latch pawls located in the upper control rod drive mechanism. The E
$ Type C, D, or E power unit is also retained in the container by means of E B' eight shipping bolts but because the closure heads on these power units do E p not include a bolting flange, a special shipping ring is used to clamp the E 5 closure head and core cartridge assembly to the barrel upper flange of the E p shipping container. The control rods in a Type C, D, or E power unit are W W restrained in the power unit by means of rebound and outmotion latches g located in the latching portion of the control rod drive mechanisms. The p '
g s container assembly weighs about 100,000' pounds empty and about 270,000 g g pounds loaded. g B i y (3) Drawings g! s t y The packaging is constructed in accordance with Baldwin-Lima-Hamilton g g Corporation Drawing Nos. R-126361, Rev. E,'and R-126347, Rev. K, and g a Westinghouse Electric Corporation. Drawing Nos. 955F632, Rev. 5, and j 972D940, Rev. 5. g j al n [ (b) Contents j (1) Type and form of material' ' B ls
. Unirradiated enriched uranium as contained in Naval Reactors Type A, B, C, j D, or E power units consisting of core barrel, unirradiated fuel j s
i assemblies, closure head, mechanisms and associated hardware, with all i g! design control rods and mechanisms installed. n q j h (2) Maximum quantity of material per package l One power unit as described in 5(b)(1). ,E Transport Index for Criticality Control (c) Minimum transport index to be shown f on label for nuclear criticality control: 100 l s
- 6. Expiration date: December 31, 1997. I R
N 5 B E 4 El B N!
- l B;i E!
Ei t >l sl 5l 9 a sn! l B 136 5! kmm--mmmmmm...1 ...1,.m omm,1 .1m,1 .mm,1,1 ,, m,1,d
M w w w w w w w w w w w w w w w w w w w m w wii.<w w w w w w w w w w w w w w w w w w w w w i NRC FORM 618A conor 11oss tc, irm,<d; U.S. NUCLEAR REGULATORY COMMISSION g( 'g M g! ,p _a B Page 3 - Certificate No. 6441 - Revision No. 6 - Docket No. 71-6441 9 4 El E 9 l6 E E D REFERENCES B E W Safety Analysis Report for D2G Power Unit Shipping Container, ONP-74252-13 dated E E D August 4, 1969.
' E 9 Supplements: Bettis Atomic Power Laboratory letters WAPD-DP(CH)-1252, dated November E N 30, 1973; WAPD-DP(CH)-1466, dated October 18, 1974; Knolls Atomic Power Laboratory E W letter CGN 85542-250, dated February 5,1981; and Naval Reactors letter E 9 NR:RR:ESSNIDER G#92-03731, dated October 7, 1992. m E
b D FOR THE U.S. NUCLEAR REGULATORY COMMISSION E l lp Ale William D. Travers; Director E i I p Spent Fuel Project Office E y Office of Nuclear Material Safety E p and Safeguards ( E , B l Date: 3 M % k E , s E R E s E B E R E s E 9 W n W s E B E B E l l 9 l E 3 p E p E l p E W s E l B
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! 9 E i p E D E , B E g E D E D p M E y Y l 5 gI E gl
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g wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwg NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION gI nee CERTIFICATE OF COMPLIANCE N socr)n n u FOR RADIOACTIVE MATERIALS PACKAGI3 E I $ eI dI b. REVISION NUMBER c. PACKAGE IDENT1HCATION NUMBF R d PAGE NUMBER c. TOTAL NUMBER PAGE'S h .a CLRTlHCATENN 3 'MBER 9
# USA /6553/AF 1 2 !lI e!
1 PREAMBLE
- n. This certificate is issued to certify that the packagmg and contents described in Item 5 below. nrets the apphcab> .anty standards set forth in Title 10.
h I % Code of Federal Regulations, Part 71. "PacLaging and Transportation of Radioactive Material." e
- b. T.iis cert 4Gcate does not reheve the consignor from compliance with any requirement of the regulat.ons of the U.S. Department of Transportation or other I
applicable regulatory agencies, includmg the governnent of any country through or into which the package will be transported. k l $ l 1 THIS CERT!HCATE IS ISSUED ON THE B ASIS OF A SAFTTY ANALYSIS REPORT OF THE PACKAGE DLSIGN OR APPLICATION k i b a ISSUED 10(NuwandAddrruf -I I
- b. TITLE AND IDENTlHCATION OF REPORT OR APPLICATION: e l B United States Enrichment Corp. Safety Analysis Report on the "Paducah Tiger" E l p. 2 Democracy Center Protective Overpack for 10-Ton Cylinders of 3 6903 Rockledge Drive Uranium Hexafluoride, Peport No. KY-665, June 16,
( g a Bethesda, MD 20817 1975 and Supplement 1, dated May 20, 1977, as supplemented. g i g
~
- c. DOCKET NUMBER G l h 4. CONDITIONS k
j $ nis certificate is conditional upon fulfilling the requirements of 10 CIlt Part 71, as applicable, and the conditions specified below. n
!$ * (a) Packaging $
e B (1) Model No.: Paducah Tiger N E g (2) Description 5 l A protective overpaEk which provides. impact and thermal resistance for N 5 5 the Model No. 48X.10-ton cylinder. Mhe cylinder is a welded steel, and E
#l is 48 inches in diameter, 12 inches long, and has a 5/8-inch thick wall. N The cylinder has a 108.9 ft '[_ volumes. and is rated at 200 psig servi N h pressure. The protective'overpack has overall. dimensions of N
@j approximately 153 inches x;76' inches x 72. inches. The overpack consists N ij of two parts, a body and ailid,Lwhich are clamped and secured by four, N B; l-3/8-inch ratchet type. binders;'and.eight, 1-3/4-inch guide pins, fitted N Bj with 3/4-inch high strengthilatch pins _. .The closed, assembled overpack 4
$! consists of. an outer 1/8-inch steel shell backed on both long sides, top 4 B
and bottom by two,10-gauge stainless steel breakaway plates. The valve 4 M end is protected by a 3/8-inch stainless steel breakaway plate. A 5 5 centrally located 3/16-inch steel shell, 60 inches in diameter x 128 6 < 9 inches long is separated from the outer shell by fire retardant N 5 polyurethane foam. The cylinder is held in the overpack by rubber shock 6 5 isolators. Four mild steel brackets are provided on the body for E R lifting. Four, 2-inch bolts are used in conjunction with the ISO corner E 9 fittings for tie-down. The maximum gross weight of the package is i 3 37,500 pounds. E Bj E g (3) Drawings E h 6 gl The Paducah Tiger overpack is constructed in accordance with Martin p! i Marietta Energy Systems, Inc., Drawing Nos. M-1209-NRC-1, Rev. 0; e p M-1209-NRC-2, Rev. 0; and M-1209-NRC-3, Rev. O. g E l s%j 4 El Ei (, Ei El' Wl E s E s' al E 138 g
.tist a m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m mQ
WWWWwwwwWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW g NRC FORM 618A CONDITIONS konimus; U.S. NUCLEAR REGULATORY COMMISSION g !p D Nge 2 - Certificate No. 6553 - Revision 9 - Docket No. 71-6553 E D N 5.(b) Contents E
/g 4 (1) Type and form of material E , '1 E gJ Solid uranium hexafluoride (UF ) at not more than 4.5 w/o U-235 isotope s
, enrichment,andanH/Uratiooknomorethan0.088. E s l (2) Maximum quantity of material per package. i s i The maximum weight of UF 6 not to exceed 21,030 pounds (9,540 kg). The maximum U-235 content not to exceed 640 pounds (290 kg). ig g (3) Transport Index for Criticality Control ls b. Minimum transport index to be shown on label for nuclear criticality control: 0.4 ig l s
# Each Model No. 48X cylinder must'be inspected [ tested, maintained, assembled, 5
- 6. i and used in accordance with American National Standards Institute (ANSI) s s
N14.1-1990. The cylinders must be designed and fabricated in accordance with ANSI N14.1-1990 or. an earlier version of ANSI N14.1 in.effect at the time of j a B N fabrication. The cylinders must be fabricated in accordance with Section VIII, Division I, of the American Society of Mechanical Engineers (ASME) Boiler and j ' g Pressure Vessel: Code and must be ASME Code stamped. g 9 7. In addition to the requirements of.Subpart G of 10 CFR Part 71, each package
# shall be maintained, repaired, operated and, prepared for shipment in accordance y with Paducah Gaseous Diffusion Plant. Standard Operating Procedure g - CP4-CU-CH6423, Rev, 0, dated February 9, 1996, Land United: States Enrichment Corporation supplement dated May 29,11996.-
W l B ^ i B 8. Use of Model No. 48A cylinders;isJnotiauthorized. -s E R E
. . . u B 9. Use of Model No; 48X cylinders made of_ A-285 steel is not' authorized. E b E D 10. The package authorized by this certificate is'hereby' approved for use under the E B general license prov_isions of 10 CFR 971.12. 4 E g 4 E
- p 11. Expiration date
- November 30, 1998. E R $
p REFERENCES $ e " l p Safety Analysis Report on the "Paducah Tiger" Protective Overpack for 10-Ton E g! Cylinders of Uranium Hexafluoride, Union Carbide Corporation Report No. KY-665, June E l p 16, 1975, and Supplement 1, May 20, 1977. E \ p E t y Supplements dated: June 10 and 14, 1988; July 1, 1993; August 15, 1994; E g March 29, 1995; March 28, 1996 (GDP 96-0061 and 0062); and May 29, 1996. E B E g FOR THE U.S. NUCLEAR TORY COMMISSION E N William D. Travers, Director E gi Spent Fuel Project Office Ej g r Office of Nuclear Material Safety El gi l and Safeguards E d Date: YlN 8 L . . . . . . . .'. . . . . . . . . . . . . 139 m . . . . . . . . . . . - - - - . - - 8
g! g NRC FORM 618wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwy U.S. NUCLEAR REGULATORY COMMISSION g( l ow CERTIFICATE OF COMPLIANCE 8 10 CFR 7' FOR RADIOACTIVE MATERIAIJS PACKAGES Nl 1.a Cf RT!!ICATE NUMBE R b REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER e TOTALNUMBER PAGES pl 6568 9 USA /6568/A 1 4 ql b .. PREAMBLE Nj' 8 m. This certificate is issued to certify that the pacLaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10. h 5 Code of Federal Regulations. Part 71,"Packagmg and Transportation of Radioactive Maierial."
!!l-
- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other h h applicable regulatory agencies, including the government of any country through or into which the package will be transported. 4 };
- 3. THIS CERTIFICATE 15 ISSUED ON THE B ASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a ISSUED TO(Nume and Adderul b Ti1LE AND IDENTIFICATION OF REPORT OR APPLICATION: k 8 6 8- n p Tennessee Valley Authority Tennessee Valley Authority application g g 1101 Market Street dated August 16, 1976, as supplemented. g y Chattanooga, TN 37402 g g c. DOCxET NUMBER 71-6568 g y 4 (UNDITIONS q '
g This certificate is conditional upon fulfilling the requirements of 10 CfR Part 71, as applicable, and the conditions specified below. g 9 5. g
> c g 8 8 g (a) Packaging g 8 4 g (1) Model No.: LL-60-150 g
# d y (2) Description '
, y Thecaskiscylindricalinshape93sincheslongand82.5inchesin
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; diameter. Lead, shielding, 3-1/2 inches thick, is encased within the I n inner and outer steel shells that are welded to a laminated steel base U plate' assembly.' The cover is a steel plate assembly-secured to the top U lg flange by 36 steel bolts. ' Encircling the. top of the. cask is a partial I length: steel shell of 1/2-inch thickness. Silicone 0-rings provide seals N at the top cover and at all plugs. The inner container is right circular N
steel cylinder with~a capacity of 150 cu ft. The, total weight, when N loaded, is approximately 73,000 pounds. l , (3) Drawings N
- 4 8 The packaging is constructed in accordance with the following ATCOR Inc. 8 8 Drawing Nos.: 0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 05268-B-0010, 8 8 Rev. E; 0568-B-0016, Rev. 0; 0568-B-0018, Rev. A; 0568-B-0025; and E 8 0568-R-0001, Rev. J. 8 8l N 8l 4 8 E 8 8 8 8 8 E 8 E 8 8 8 8 8j 8 Ni a f g '
8 4 8 E 8 8 8 140 W $mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm.... mmmmmmmmmmJ !
I I gwwwww wwww wwwwww.wwwwwwwww.wwwwww ww.wwww.ww q l g NR FORM 618A CONDITIONS uunimurdj U.S. NUCLEAR REGULATORY COMMISSION g ! B E i B Page 2 - Certificate No. 6568 - Revision No. 9 - Docket No. 71-6568 E
- 5 E F E k 5. (b) Contents E B E i B (1) Type and form of material E B E i B Process solids, either dewatered, solid, or solidified waste, in E l B sealed containers, and limited to the following
- E i B E B (i) Materials in which the radioactivity is essentially uniformly E B distributed and in which the estimated average concentration E per gram of contents does not exceed:
B E B E B 0.0001 millicurie of radionuclides for which the A quantity 2 E s in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; E B . E i B quantity in E B 0.005 Appendixmillicurie A of 10of CFRradionuclides Part 71 is more for which thecur than 0.05 A,ie, but not E B more than I curie; or E B E i B 0.3 millicurie of radionuclides for which the A, quantity in g g Appendix A of 10 CFR Part 71 is more than 1 curle. g , B E p (11) Objects of nonradioactive material externally contaminated g with radioactive material, provided that the radioactive p g material is not readily dispersible and the surface l g g
> contamination, when averaged over an area of I square meter, g does not exceed 0.0001 millicurie (220,000 disintegrations g l 9 per_ minute) per_ square centimeter of radionuclides for which g g the A2 quantity-in Appendix A of 10 CFR Part 71 is not more g
, g than 0.05 curie, or 0.001 millicurie g
- y (2,200,000 disintegrations per minute) per square centimeter g for other radionuclides.'
y y
~
l (2) Maximum lquantityofmateria1perpackageL l l l Greater than Type A quantity of radioactive material with the l l weight of the package contents and secondary containers not g 9 y exceeding 12,500 pounds. g j l B E B E B E i B E B E B E B E B E l B E B E B E B E
- E E
' E E
E l 141
. . . . . . . . . . . . . . .,1x.,m, . . . m . . . .m1. . . . . . . . . . . . a
.__.___.m._ _ _ . _ _ _ _ .__,_.-._._._-___.m.. _ _ _ _ _ _ - . _ . _ _ . _ _ _ _ _ _ _ _
I gewwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwug) g NRC FORM S1SA CONDWONS tmatuwd) U.S. NUCLEAR REGULATORY COMMISSION gI A-96) g b Page 3 - Certificate No. 6568 - Revision No. 9 - Docket No. 71-6568 I b E l L 6. (a) For any package containing water and/or organic substances which could I b radiolytically generate combustible gases, determination must be made by I D tests and measurements or by analysis of a representative package such a B that the following criteria are met over a period of time that is twice d B the expected shipment time: E B E D (1) The hydrogen generated must be limited to a molar quantity that E D would be no more than 5% by volume (or equivalent limits for other El !. R inflammable gases) of the secondary container gas void if present E: B at STP (i.e., no more than 0.063 g-moles /ft3 at 14.7 psia and a N 70*F); or d B 4 The secondary container and cask cavity must be inerted with a 5 (2) e B diluent to assure that oxygen must be limited to 5% by volume in a p those portions of the' package which could have a hydrogen g , j p concentration greater than SL s a ; ' D . _ d p For any package delivered to a carrier for transport, the secondary a p container must be prepared for shipment in the same manner in which a t p determination for gas generation is made. Shipecat; period begins when g p the package is prepared (sealed) and must be completed within twice the g : p expected shipmentctime. g ! B
! f E p (b) Foranypackageshippedwithin10daysofpreparation,iorwithin10 days g after venting of drums'or other secondary containers' . the determination e ,
g !
' in (a) above need not be made/and the~ time restriction in (a) above does g !
s not apply. ~1 - g ! p .: ! .. : , . e E i- g
- 7. In addition to the requirements of.Subpart_G of 10 CFR Part_71:
p g ! (a) Eachpackagemust-bsmaintMnedinaccordancewith"ReactorCleanupCask y Maintenance Program in the: supplement dated Februhry 20, 1991. l i g g e ,t
- c;s g t p (b) The package mu't s be prepared:for shipment and' operated in accordance with .
g ' l g the Reactor Cleanup Cask Operating Procedure;in the supplement dated g g February 20, 1991. y , y y ,
^
lg 8. The package authorized by this certificat must be transported on a motor vehicle, railroad car, aircraft, inland water craft, or hold or deck of a l g
, seagoing vessel assigned for sole use of the licensee, y
l 9. Fabrication of additional packagings is not authorized. l lg 10. The package authorized for use by this certificate is hereby approved for use U under the general provisions of 10 CFR 571.12. l e l ! a . D g D E i b d I E ! D d i el a 8 4 142 U
1 i difw w si siii w w w w w Tsfii sTTsnsT isTTs7 w w w w w Ts7 w w w in-( w Tat w Ist is7 Ts7 w w Ts7 w w w w w wRI w w wa 9 CONtHTioNS mmemurd; U.S. NUCLEAM REIULATORY COMMISS60N g i g NRC FORM 618A -
, (3 96) R l B. E sj Page 4 - Certificate No. 6568 - Revision No. 9 - Docket No. 71-6568 E Bj E P
E , n 11. Expiration date: April 1, 1999. This certificate is not renewable. E B si B E B REFERENCES E m E B; ! E l B Tennessee Valley Authority application dated August 16, 1976. E B E B- Supplements dated: October 8, 1976; October 5, 1979; October 23, 1980; B February 20, 1991; February 29, 1996. E, i g E B g l FOR THE U.S. NUCLEAR REGULATORY COMMISSION B -
}
I b A /e William D. Travers, Director g 3 Spent Fuel Project Office g 3 g i p Office of Nuclear Material Safety and Safeguards g , 3 Date: N 1Ahb. E l e
- E 8
' E E
B. g e E i 9 E B E B E B E ! B E ! B E l 9 E
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, B E B E 4 s 5 143 i
$m 1m m m m m m m m m m m m m m m m m m m m ist a m m m m m m m m m m isusum m m m m m m m m mt m
gwwwwwwwwwwwwwwwwwwwwwwwwwwdWwwwwwwwwwwwwwwwwwwwg g NRC FORM 618 chm U.S. NUCLEAR REGULATORY COMMISSION g CERTIFICATE OF COMPLIANCE 10 CFR 71 FOR RADIOACTIVE MATERIALS PACKAGES N g I. a CLRTIFICATE NUMBLR b. REVISION NUMBER N
- c. PACKAGE IDENTIFICATION NUMBLR d PAGE NUMBER e. TOTAL NUMBDt PAGES a 6574 g 23 USA /6574/B( ) 1 3 ( ,
- 2. PREAMBLE k
Ng a. This certificate is issued to certify that the packaging and contents described b Item 5 below, rnects the applicable safety standards setIforth Code of Federal Regulations, Part 71,
- Packaging and Transportation o' Radioactive Material?
k N b. This certificate does nas reheve the consignor from compliance witt any requirement of the regulations of the U.S. Department of Trans applicable regulatory agencies, including the government of anv .ountry through or into which the package will be transported. k 6 ;
- 3. THIS CERTIFICATE
- s. ISSUED IS ISSUED ON T}iE BASIS OF A SA8T.TY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION TO f Name omf Address; i
B
- b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION: k a Scientific Ecology Group, Inc. Scientific Ecology Group, Inc. 4 j 1560 Bear Creek Rd. application dated December 27, 1990, g j Oak Ridge, TN 37831-2530 as supplemented. g h g p 71-6547
$ d. CONDITIONS
- c. DOCKET NouBE, l
g . E This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable. and the conditions specified below.
$ 5.
g 4 (a) Packaging E 4 (1) Model No.: 3-828 N 5 4 B (2) Description U B E B Thepackagingconsistsofasteel-lead-steelannulusbaskfabricatedin U B the form'of a right circularecylinder and three diffe' rent types of inner N L containers. The shielded cask,- closed at one end and a lid closure at the N W other, is 60.25 inche's in diameter by 74.5 inches in height. The cask I 8 wall consists of a 3/8-inch inner steel shell, 3-3/4l inches of lead 8 B shielding, one-inch outer steel 'shell, and a steel flange connecting the N two shells. The cask outer shellt is surrounded by.a' one-inch layer of 4 B m insulating material- and canned.in ll-gauge steel. 8 R R B The lid, sealed by a silicone flat gasket, is bolNd to the cask body. A E B cylindrical shield plug is located in the center of the cask lid and is a sealed by a silicone flat gasket. Lifting and tie-down devices are W B attached to the cask body. Impact skirts, consisting of removable rings B 4 R of shock absorbing foam, are attached to the ends of the cask. N R (3) Drawing E 9 g 9 4 p The package is fabricated in accordance with the following Scientific 6 B, Ecology Group, Inc. Drawing No.: STD-02-076, Sheets 1 through 3, Revision 7. E R E W E 4 B 6' R 4 B E B E ' b e B E. F E i Bj E sj W e E B E 144 E $kmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmd
I l _ -. w w w wiw wTTs w w w w w w w w w w w w w w w m W W W W W W W W W W W W W W W W W W W W W W y coNumoNs kvaimed; U.S. NUCLEAR REGULATORY COMMISSION g , g NRC FORM 618A (3-961 g g l Page 2 - Certificate No. 6574 - Revision No. 23 - Docket No. 71-6574 W E R W P W 5.(b) Contents g Type and form of material l (1) ! 5 ,l Byproduct material consisting of dewatered, solid radioactive waste, , ig including spent ion exchange resins, filter sludges, solidified evaporator l9 concentrates, spent filter cartridges, and contaminated or irradiated s i f solid materials. i (2) Maximum quantity of material per package l G l5 Greater than Type A quantity of byproduct material, which may contain not i 5 more than a Type A quantity of fissile material, provided the fissile material does not exceed the limits specified in 10 CFR 671.53. The cask is lN contents must be contained within one of the following inner containers i !5 and limited as follows: i i - B g 5 (a) Single disposable cylindrical containers constructed of metal or i
- 5 high integrity plastic with tightly fitted covers. A maximum decay j l
8 heat load of 205 Btu /hr. g i E (b) Two pallets with four, 30-gallon drum size containers per pallet. Drums to be constructed of. metal or high integrity plastic with a lg l 9 l 9 tightly fitted cover. A maximum-decay heat load of 84 Btu /hr. g I i P (c) One pallet with three, 55-gallon drum size containers. Drums to be constructed of metal or high integrity plastic' with tightly fitted
! j l
l $ covers. A maximum decay. heat load of 116 Btu /hr. ;g ' 9 i I
# 6.(a) For any package containing water 'and/or. organic substances which could '
p radiolytically generate combustible ~ gases, determination must be made by tests s and measurements or by' analysis of a representative package such that the $ i p following criteria are met over a period of time that is~twice the expected 5 E p shipment time: - W i B W y (i) The hydrogen generated must be limited to a' molar quantity that would be W l 3 no more than 5% by volume (or equivalent limits for other inflammable I l g gases) of the secondary coptainer gas void if present at STP (i.e., no W p more than 0.063 g-moles /ft at 14.7 psis and 70*F); or W a j (ii) The secondary container and cask cavity must be inerted with a diluent to assure that oxygen must be limited to 5% by volume in those portions of 6 W I a l j the package which could have a hydrogen concentration greater than 5%. W W l s W
',I For any package delivered to a carrier for transport, the secondary container !
must be prepared for shipment in the same manner in which determination for gas W i pl W gl generation is made. Shipment period begins when the package is prepared l (sealed) and must be completed within twice the expected shipment time. W 9 l g s,l E m (b) For any package containing materials with radioactivity concentration not exceeding that for low specific activity material, and shipped within 10 days of a y E preparation, or within 10 days after venting of drums or other secondary a g containers, the determination in (a) above need not be made, and the time y restriction in (a) above does not apply. E 5 0 E B karmammmmmmmmm,,,,,,,,,3 145;,,,mmmmmmmmussammmmmmmmm$ 1
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*NRC FORM 618A U.S. NUCLEAR REGULATORY COMMISSION g 31 p E Page 3 - Certificate No. 6574 - Revision No. 23 - Docket No. 71-6574 p N B E i
- 7. E:
The total weight of the package must not exceed 50,000 pounds and the weight of ( l y the contents (including dunnage, etc.) must not exceed 8,195 pounds. E ; W g 8. In addition to the requirements of Subpart G of 10 CFR Part 71: 9
# (
(a) n h The package shall be prepared for shipment and operated in accordance with g; g Operating Procedure STD-P-02-024, Rev. 3, in the supplement dated g March 7, 1996. g a y j (b) The package shall be maintained in accordance with the maintenance program g g g in the supplement dated March 13, 1991. g
!: 9.
Except for close fitting contents, sufficient dunnage, shoring, and/or bracing must be utilized to minimize secondary impact of the contents within the cavity l g l under accident conditions of transport. g 8
- 10. Prior to each shipmenth the seal on the main cover and the seal on the shield E
! plug cover, if opened, or if the security seal is broken, must be inspected. ~
The seals must be replaced if the inspection shows any visible defects or every 8 l 12 months, whichever occurs first.
!5 11. The packaging m'ust be leak tested in accordance with Section 8.2.2 of the f
U application.
!5 12. The package authorized by this'certificatexis hereby approved for use under the U general provisions of 10 CFR -671.12. 5 i b; 13. Expiration date: M'ay 31, 2001. E B
B E
^
9 E 5 'REFERENCET E B 5 ScientificEcologyGroup).IncorporaYedapplicationdatedDecember 27, 1990. E B ' E B Supplements dated: March l3n 1991; and March 7, 1996. " d t 5 g > B E < F R THE U.S, . REGULATORY COMMISSION ' p A% William D. Trdvers, Director i g 3 Spent fuel Project Office g p l p Office of Nuclear Material g ! Safety and Safeguards y { Date: L10 p r'- l g i
#i l Wi 8 P i' B N B; E %j E 4
8j 146 El
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I u.s. NUCLEAR REGULATORY COMMISSION I fe e rona eis I I us> CERTIFICATE OF COMPLIANCE I I w CFR n FOR RADIOACTIVE MATERIALS PACKAGES D REVISION NUMBLR c. PACKAGE IDENTW eCATION NUMBER e PAGE NUMBER e. TOTAL NUMBER PA6E'S e CEMICATE NUMBER l 6581 23 USA /6581/AF 1 3 I g I I PREAuBLE I a This certificate is issued to certify that the packaging and contents described in item 5 below, meets the apphcable sa fety standards set forth m Title 10 Code l of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material." l l
- b. This certificate does not relieve the consignor from comphance with any requiremoryt of the regulations of the U.S. Department of Transportation or other I
I apphcable regulatory agencies. includmg the government of any country through or into which the package will be transported l l f 1 I i I S. THIS CERTh ICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION !
! a IS3UED TO (heme omr Ad@esas b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION l l l l l Siemens Nuclear Power Corporation Advanced Nuclear Fuels Corporation application i I 2101 Horn Rapids Road dated October 15, 1990, as supplemented. I 3
I Richland, WA 99352-0130
- 6. M b b / ' ,,
I l , v '.. DOCxET NuMBEa i71r6581 4 CONDITIONS ,() s. I This cettificate is conditional upon fulfilling {herequirements of 10 CFR Part 71, as apphcable, and the coretions specified below. l ., l I 3- y tj l (a) Packaging Q - I , (1) Model No n-. 51032- N g.q .
,/
c, q- l l i . g4.) is <p - g fs - a i (2) Description . '
- , r < f \'
i~; a
- m. g
.- rq x .m.s (- s i '
I n n I ( A steel shippingLeont'ainerJor fuel thindles, consisting 7of a strongback and I l I fuel bundle clamping assemblygshock mounted to a fsteelTouter container. Minimum 3/8" thipk? wall,'6Q $' M 841/2" long steel separators are bolted l ! lg 0 uter , container n is approximatelh43" diameter by 216" i betweenfuel. long. The" maximum we bund 1)s@ig@[ofuthi[patkage a including contents, is 7,400 l s l pounds. W , P% /-(h?s */ ,j/) 1 (3) Drawings , A W) ' i l I The packaging is tonstructed and assembled n[ accordance with: i Jersey Nuclear Compan DrkingjNo.1f( JN-200002, Rev. , l l and Exxon Nuclear Company, Inc., Drawing Nos.: l l 1 l 1 i XN-NF-303,359, Rev. 2 I I XN-NF-303,360, Rev. 1 I XN-NF-303,898, Rev. 1 l XN-300,607, Rev. 1 i l XN-300,609, Rev. 1 i i I i XN-NF-303,364, Rev. 1 I I I I and Siemens Nuclear Power Corporation / Advanced Nuclear Fuels Corporation 1 Drawing No.: i
, l EMF-303,897, Rev. 2 I l I I I I 1 l I
! ll 147 I ' -- =====--" l.___________-______--------------------------
_ _ ~ _ . m eroa m U.S. NUCLEAR REGULATORY COtetNSSION
.. cONDmONS (continued) l Page 2 - Certificate No. 6581 - Revision No. 23 - Docket No. 71-6581 1 I
g 5.(b) Contents t i l (1) Type and Form of material I I i I i Unirradiated fuel rods consisting of uranium dioxide fuel pellets clad in l zircaloy or stainless steel tubes. Uranium is enriched to a maximum of 5.0 l i w/o in the U-235 isotope. Cladding must have a minimum wall thickness of i g l l 0.02 inch and a minimum nominal pellet-clad radial gap of 0.003 inch. The 1 i maximum length of the active fuel region is 196 inches. Fuel rods must be in l l one of the following configurations: I l i (1) Fuel assemblies consisting of a maximum of 204 fuel rods in a 15 x 15 square array with a m ' m Rmjtighfgel rod pitch of 0.563 inch and a l;' y i maximum assembly ti d bf W4 7)nches square. The fuel rod i i I claddingmust)dg. OD not less tha(n % Q) inch and not greater than i 0.430 inch. 1 l applicati UW Tuel rod arrangement is as7spwn in Figure 11.1 of the
' O I y (ii) Fuel asse s consisting of a ma timum of)6 i fh rods in a 17 x 17 l square ay%11 a maximum nominal fue to l itchdf 0.496 inch and l l a maxi asse tross section of ches s re. The fuel rod i I cladd must h n qq; a 5 inch not greater than I l 0.38 ch. They rd angem 19 sshownigigure11.2ofthe l appigion. p Q 5 g
(iii) Fuel hrrsemb ikco" g o.f anx of//p(1ro in a square array i I I with g imu Jembry s ; : c g .gf/fjpehes are. The fuel rod 1 claddrng mus > e an 0.2 ' anch not greater than I l 0.500 g h. {g. % An'ddp L '" l i
! (iv) Any num M of fd b s pph .i Ndcontshper. The rod ' '
i I containegoysistsof deh 96 i pip th a maximum nominal i ' I diameter oV nches. Thel J od cla dina t have an OD not less l l than 0.260 nd not greater than 0.500 ~ . l (2) Maximumquantityofmateh ka M i I Total weight of fuel assemblies, or fuel rods and rod containers, not to i exceed 3400 pounds, and 1 l l (1) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), and 5(b)(1)(iii): I l ; i I i Two full length fuel assemblies. Two short fuel assemblies may be a I substituted for each full length fuel assembly provided the two short i assemblies are shipped end-to-end and the total fuel length does not I l exceed the maximum fuel length for a full length assembly. l
! ii) For the contents described in 5(b)(1)(iv):
l l l l Two rod containers. l I i I I I I I i l 148 (
P0ntistaA U.S. NUCLEAR REGULATORY C0000AISS40N CONDITIONS (continued) I I Page 3 - Certificate No. 6581 - Revision No. 23 - Docket No. 71-6581 I I I
- 5. (c) Transport Index for Criticality Control l I
I Minimum transport index to be shown on label for nuclear criticality control: 0.4 l
- 6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed l polyethylene sheath which will not extend beyond the ends of the fuel assemblies. l The ends of the sheaths must not be folded or taped in any manner that would I prevent the flow of liquids into or out of the sheathed fuel assemblies. l
- 7. Hydrogenous shims are not permitted within the fuel assemblies. j
- 8. Q t clamp assemblies must be in !
l Separator accordance blocks, shock with Tables 2. mountsh ,.an f .. geapplication. l
- 9. The fuel assembly cro shetion is defined as the r %chtimesthenumberof l rods on the edge of assembly. Q i
- 10. Rods containing (niaorotherneutronpoisonar, apt ed but not required.
- 11. In addition to g requi' of Subpart G o Part I (a) f pm n operatedgaccordancewith l Thepackab(esinChapthall the proce 0ofgthe app be h.n. i bh e r =t in nc dh t rocedures in I (b) Eachpackk@ngs l l' Chapter 3 ft ' ' > '
licat)h ,,, Chap) ) 4.0 of the l i l (c) Each packag g sha n t a c : ti 't a p es i y +/ VJ
~
l i . l application.g t
- 12. The package author y this erkf byapp(bydforuseunderthe I l
i general license pro s of 10 CF 1 2. U A ! l'13. q Expiration date: May 31,/199 i , 1 l E CE i I 3 Advanced Nuclear Fuels Corporation application dated October 15, 1990. l l Siemens Nuclear Power Corporation supplements dated September 18, 1991, April 22, 1992, ! and January 25, 1994. l ' l l l I N FOR THE U.S. NUCLEAR REGULATORY COMMISSION - I t \ l b) M William D. Travers, Director I I I I Spent Fuel Project Office I Office of Nuclear Material Safety l and Safeguards i (
! Date: 5i A C!9/ I i
s I I 149 y g l l
rwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwmwwwwww _ US CERTIFICATE OF COMPLIANCE M C#" " Nl N l'OR RADIOACTIVE MATERIALS PACKAGES Nli I a CERTIFICAT1i NUMBER b. REVISION NUMBER kI ,
- c. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e. TOTAL NUMBLR PAGES 1
6601 25 USA /6601/A 1 4 E N k L PREAMBLE kl
- a. This certificate is issued to certtfy that the packaging and contents descrshed in item 5 below, meets the applicable safety standards set forth in Title 10. Nl Code of Federal Regulations. Part 71
- Packaging and Transportanon of Radioactive Material."
k i
- b. This certificate does not relieve the consignor frorn compliance with any requirement of the regulations of the U.S. Department of Transportation or other h
applicable refutatory agencies, including the government of any country through or into which the package will be transported. k 0
- 3. THIS CLRTIFICATE IS ISSUED ON THE B ASIS OF A SAFETY ANALYSIS REPORT OF THE PACK AGE DLSIGN OR APPLICATION 3
- s. ISSUE D TO (%me and Address) b TITLE ANDIDENTIFICATIONOFREPORTOR APPLICATION. N D
B E1 E N Chem-Nuclear Systems, Inc. Chem-Nuclear Systems, Inc. application ( b 140 Stoneridge Drive dated August 23, 1985, as supplementei. E B Columbia, SC 29210 p (
- c. DOCKET NUuBER 71-6601 g 9 4. CONDITIONS g
g This certificate is conditional upon fulfillmg the requirements of 10 CTR Part 71, as applicable, and the conditions specified below. g N 5.
$ (a) Packaging g B
y E (1) Model No.:. CNS 8-120A g B . p (2) Description E g B - - N N The packaging is a steel-encased, lead shielded shipping cask which g g weighs approximately 70,000 pounds when loaded. The cask is 73.5 inches g e in diameter by 92 inches high, with an' effective cavity 62 inches in g [ diameter by 75 inches long. -Gamma' shielding equivalent to 4.5 inches of i lead is provided by lead and steel. The outer shell is fabricated of g g g two, 3/4-inch thick steel plates and the inner shell of 1/2-and 1/4-inch g g thick plates. -The' cavity is closed and sealed by thirty-two, 1-3/4-inch y bolts and a silicone 0-ring within a recessed groove on the flange of the g g cask. A steel l collar encircles'the outer shell in the lid area. y Shackles are used for lifting the packaging and the lid. Tie-down is I g accomplished through a steel structure which is'not attached to the U g package. The lid provides'several threaded and sealed access plugs and U g the base has a drain line.
- l j (3) Drawings W
The package is constructed in accordance with Chem-Nuclear Systems, Inc. 4'
! Drawing No. 29008-1, Sheet 1 Rev. 2, and Drawing No. 29008-1, Sheet 2, d ? Rev. 2. 8 5
E B q B g E 5 e B4 R , l B e E' i Bj Nj N E Bi
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7=wwwwwwwwwwwwwwwww=musL*w====wwwwwwwwwwwww=wwwwug! NR FORM 618A nWHTioNs sc<mimudi U.S. NUCLEAR REGULATORY COMMISSION g E p Page 2 - Certificate No. 6601 - Revision No. 25 - Docket No. 71-6601 g bl EI Bj ! P b 5. (b) Contents (! g 1 h pj (1) Type and form of material 6l g g p Process solids, either dewatered, solid, or solidified, or solid !! e reactor components, in secondary containers, and limited to the ilj' ' a following: Sl (i) Materials in which the radioactivity is essentially uniformly ! y distributed and in which the estimated average concentration s y per gram of contents does not exceed: j E B 0.0001 millicurie of radionuclides for which the A2 quantity s
,J in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; ;
1 0.005 millicurie of radionuclides for which the2 A quantityinl lg Appendix A of 10 CFR Part 71 is not more than 0.05 curie, but g not more than 1 curie; or ;p 5 '
'0.3 millicurie of radionuclides for which the A2 quantity in E !j Appendix A of 10 CFR Part 71. is more than 1 curie; $l h (ii) Objects of nonradioactive material externally contaminated E d
Si with radioactive material, provided that the radioactive E i Bj material. -is not readily dispersible and the surface !e
? contamination, when averaged over an area of I square meter, does not exceed 0.0001 millicurie-(220,000 disintegrations per !
h minute) per. square centimeter of radionuclides for which the e Bj bj A2 quantity in Appendix A of 10 CFR part 71 is not more than W 9 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per E B minute) per square centimeter for other radionuclides. W W W
$; (2) Maximum quantity'of material per package t
6 h ,. 91 Greater than Type A quantity of radioactive material, not to ( (1 9 exceed 2,000 times a Type A quantity, 40 thermal watts, and 20,000 W l 5 pounds including weight of the contents, secondary container (s) 6 s and shoring. The ' contents may include fissile materials provided ( p the mass limits of 10 CFR 971.53 are not exceeded. E N 9 i Except for close fitting contents, wood shoring must be placed between the g e 6. h secondary container (s) (or activated components) and the cask cavity to ( e prevent movement during normal conditions of transport. E e s h 7. Prior to each shipment, the lid gasket must be inspected. The gasket must be ig l p! replaced if inspection shows any defect or every 12 months which ever occurs p! first. E p! E y 8. Prior to each shipment, a determination must be made that closure seal gl replacement is current with the seal replacement schedule in Section 8.2.2 of gl 9
/
the application. Ej El WI
#l e' Ei ki Wl $ 151 k
_$sriscrmrimusi a a sisrrm- m a a a a a m a m a m m m m munninsi m a mjsusus m a a m m m a m urs
ptwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww g! NRC FORM 618A coNomoNmmimuss U.S. NUCLEAR REGULATORY COMMISSIOfi gl y 046) 3 Page 3 - Certificate No. 6601 - Revision No. 25 - Docket No. 71-6601 4 (l
* (I . 9. The packaging must be leak tested once every 12 months in accordance with qli
(
*! Section 8.1.3 of the application. ej E!
- 10. The drain line and access plugs must be appropriately plugged and sealed prior g to transport. g 3
3 11. (a) For any package containing water and/or organic substances which could ( t g , 3 radiolytically generate combustible gases, determination must be made by (l g tests and measurements or by analysis of a representative package such p g that the following criteria are met over a period of time that is twice g 3 the expected shipment time: g 8 E
, (1) The hydrogen generated must be limited to a molar quantity that g , would be no more than 5% volume (or equivalent limits for other j inflammable. gases) of the secondary container gas void if present a
j g at STP (i.e... no more than 0.063, g-moles /ft* at 14.7 psia and y
, 70'F);:or
(
! (2) The secondary container and cask cavity must be inerted with a di h diluent to assure that oxygen must be limited to 5% by volume in b
"{
, those portions of the package which could have hydrogen greater U than 5%.
8 For any package delivered to a" carrier for transport, the secondary N J container must be prepared for shipment in the same manner in which N ' determination for gas. generation is made. Shipment period begins when W the package is prepared (sealed) and must be completed within twice the #
$y expected shipment time. E i ej 4 (b) For any package sh'ipped within'10 days of preparation, or within 10 days E
$oj after venting of drums or other' secondary containers, the determination f(i , !
$ in (a) above need not be made, and the time restriction in (a) above does E ,
*{ not apply. m 8
4
- 12. The package authorized by this certificate must be transported on a motor '
$'l j vehicle, railroad car, aircraft, inland water craft, or hold or deck of a E
(l h seagoing vessel assigned for sole use of the licensee. %l . a sr -
# 13. In addition to the requirements of Subpart G of 10 CFR Part 71: 5l 8
i; s\ (a) Each packaging must meet the Acceptance Tests and Maintenance Program of nl Chapter 8 of the application; and e g (( g ( 9 (b) The package must be operated and prepared for shipment in accordance with g li t; the Operating Procedures of Chapter 7 of the application. gl e, sl
# 14. The package authorized by this certificate is hereby approved for use under il ' # the general license provisions of 10 CFR 571.12. (
s ll 8l
# 15. Expiration date: April 1, 1999. This certificate is not renewable. 5l 2
i i 5!i 1 6 ll t 152 N mm mm==mmmmmmmmmms1mmmmmmmmmmmmmmmmmm.m ,m,, mod l
l I l wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww g NRC FORM 618A coNomoNs fu=nandi U.S. NUCLEAR REGULATORY COMMISSION gl (3-es) . ! p Page 4 - Certificate No. 6601 - Revision No. 25 - Docket No. 71-6601 g l Wj E l r 4 : i s E l p REFERENCES gj p m , y Chem-Nuclear Systems, Inc., application dated August 23, 1985. (l ' l B d l g Supplements dated: December 30, 1985, January 16, 1991, October 29, 1991, g January 7, 1992, and January 29 and March 19, 1996. p y , b Eli l j g Northeast Nuclear Energy Company supplement dated: February 9, 1984. g l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l l l . , - . : B E kM1'e 'A William D. Travers, Director 8 l 8 Spent Fuel Project Office I l 8 Office of Nuclear Material Safety 8 ' l 5 and Safeguards N D E Date: d lb iG3 8 Bj a l Wi 8 R d W g
- W l p! N pl E
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l i uneconu m u.S. NUCLEAR REGUMTORY COtnelS$lON I i *=> CERTIFICATE OF COMPLIANCE I .
#Cm7 i FOR RADIOACTIVE MATERIALS PACKAGES I l i . ceRTiricaTe. NuuetR tt REVISION NUMBER .. PACKAGE IDENilFICAT40N NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGES 6613 6 USA /6613/B(U) 1 2 l g ,
i rRemusu I l 3. This certifscate is lasued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10, Code l l of Federal Regulations, Part 71," Packaging and Transportation of Rad *oactive Material." l
- b. This certificato does not rehove the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportation or other I l apphcable regulatory r.gencies, including the government of any country through or into which the package will be transported. I I
I
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, cays issyurTse eAsis or a sareTv ANatvsis RegTgT,HEgKAGE s o PPL ON i
Amersham Corporation Amershai Corporation application dated i l 40 North Avenue November 27, 1991, as supplemented. I' Burlington, MA 01803 p
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(; 7 '71-6613 g
- o. coNomoNs <ti I This cattificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the Conditions specified below. I I
a
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(a) Packaging l i O g (1) Model No.: '702 .3 - 1
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. s I
-(2) Description- i, kI ,
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l The cask : system overall dimensions. ~are-19":x 21" x 20". UThe cask is a i l stainless steel ~weldment containing depleted ' uranium shielding. The cask has 3 a central ~ cavity which is'2.26 inches in diameter by 3.25 inches long. l l Clonre isf accomplished by a; neoprene! gasket, six, 3/8-inch bolts and a a t stainless steel stepped plug containing! depleted uranium' shielding. The 1 I closure is equipped with an' eye bolt'and:two-drain and vent plugs. The cask l < is mounted onca and a tie-down's.19" ystemxconsisting 21" rectangular of four;steel' 1/2-inch skiddiameter with four,1/2-inch threaded rods bolts i I . which connect a' clamp ring at 'the top of the cask to' channel brackets welded a to the skid. A protective cage constructed of.1-1/4-inch square steel tubing - 1 L and perforated 18 gauge steel sheets tack welded to the tubular frame I i surrounds the cask and'is~ bolted >to.the skid by four,1/2-inch bolts. l Maximum gross weight of the' packaging 'is 410 pounds. g I I I I l-1 I I I I I I I I I ' I I I I l l
- 1 154 l ,
_____------___________________________________________)
=---------------_--- -----
CONDITIONS (continued) Page 2 - Certificate No. 6613 - Revision No. 6 - Docket No. 71-6613 (a) Packaging (Continued) (3) Drawings The cask and other system components are constructed in accordance with Technical Operations, Inc. Drawing Nos.: 70290, Sheet 1 to 4, Rev. D. (b) Contents . t 1 (1) Type and form of material Metallic iridium 192 sources which meet the requirements of special form : l radioactive material. g7c .
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(2) Maximum quantity of; material per package; g 10,000curiesh
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(3) Maximum decay heat per package ;, ,
, s 100 wattsi ,,
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- 6. The name plate must be fabridated;of msterials' capable of resis ing the fire test of 10 CFR Part 71,.and maintainingitheir ' legibility. * , '..,
i; . ,
. In addition to the requirements of'Su' apart Gfof 10/CFR Part 716 u, , , . , . . ,
(a) Each packagIshall:be operated) Ud m Section 7.0 of therapplication,[as' supplementedt. NepareIfor s.T shi.p' ent'I}$ accord (b) The package ust meet the'Accep n .T thandMainten,dceProgram,Section 8.0 of the application, asisupplemented.- - 4' s-
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- 8. The package authorized'by,this certificate is hereby approved for use under the general license provisions Lof 10 CFR 671.12.
A'
- 9. Expiration date: March 31, 1998. J l
REFERENCES l Amersham Corporation application dated November 27, 1991. Supplements dated: April 20, December 1, 1992; and March 19 and 26, 1993. FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS APR 1 1093 Date: 155
U.S. NUCLEAR REGULATORY COMMISSION 3 CERTIFICATE OF COMPLIANCE So crR 71 FOR RADIOACTIVE MATERIALS PACKAGES l IT" 1 e CE@ffTE NUMBER 2 PREAMBLE b REVISION NUMBER 5
- c. PACKAGE IDENTIFICAT80N NUMBER USA /6642/B( )
c PAGE NUMBER e. TOTAL NUMBER PAGES 1 2
- a. This certifscate is issued to certify that the packaging 6nd contents described in item 5 below, meets the applicable safet y standards set forth in Title 10 Code of Federal Regulations. Part 71,"Packagmg and Transportation of Radioactive Material."
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- b. This certificate does not reiweve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or other apphcable regulatory agencies, including the government of any courdry through or into which the package will be transported.
N N a 17,.g c4ysissguErsE easis or a sarETv ANatvsis REga,Tgt,sgggeysgLgpggy, U.S. Department of Energy Safety Analysis Report - Packages SRL 4.5 Washington, DC 20585 -! Ton Californium Shipping Cask, DPSPU 74-124-6, 1 December 1974, Rev.1, March 1976, as supplemented. l y
- c. oocxEr NuueER 71-6642 l
stt f6cate is conditional upon fulfilling the requirements of to CFR Part 71, as applicable, and the conditions specified below. s. I (a) Packaging I i 1 (1) Model No.: 14. 5 -Ton Cf 1 1 I (2) DescriptionI i~ l A shielded packaging for special form materials. . The outer container is a l i 3/4-inch thick, 61-1/2-inch OD spherical steel shell filled with borated I water extended polyester-(WEP); shielding. Outer shell is fitted with nine I (9) fusible' plugs and a: vent valve for relief of gases generated in the WEP I material. The cylindrical ~ containment cavity approximately 4-inch diameter by 6-3/8 inches,high~is centrally located in the sphere and surrounded by l lead of 2 inches,- 1.9 inches and 1.75 inches thickness on the bottom, sides i and top, respectively. The containment vessel is an integral part of the I outer container, and'is held by a 31-1/2-inch long 4-1/2-inch OD tube welded I to a 3/4-inch thick 22-1/2-inch diameter top plate mounted to the outer container closure assembly. Closure of_the containment vessel is ( y accomplished by'a flange plate and sleeve insert assembly. The sleeve is a i 27-inch long, 4-inch OD tube filled with lead and water extended polyester I and is gasketed and bolted to the top closure assembly of the container. A I 22-1/2-inch diameter protective cover bolts to the closure assembly sleeve. I A hexagonal shaped assembly, approximately 5 feet across the flats mounts, to the spherical shell as a base. Four equally spaced lifting lugs are provided l around pounds. the upper hemisphere. The cask gross weight is approximately 9,500 I I 1 i i B 1 I I I I l N l l m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - 156 1 l-
l
.------------------------------------------------------g i CONDETtONS (contrnuett) p ll Page 2 - Certificate No. 6642 - Revision No. 5 - Docket No. 71-6642 I
I l (3) Drawings I I l The SRL 4.5-Ton Californium shipping cask is as described, and is constructed in accordance with E.I. duPont de Nemours Company Drawing Nos.: ST5-15813, [ p l Rev. 33; STS-15814, Rev. 29; STS-15815, Rev. 0; STS-15816, Rev. 0; STS-15817, I i Rev. 0; and ST5-15818, Rev. 5. I l I 1 (b) Contents l l (1) Type and form g I Californium 252, as sealed sourcegwhich. meets the requirements of special I l form radioactive material.ig'M s i C (j [/ . l
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, (2) Maxit..a quantity chte[ial per package. [y l 46 curies (85me>? qu O4 I g
- 6. Priortoeachshipment,theWEPshieldingspaceshallbeve$ted,usingthe '
I 1/4-inch angle valve which issthen closed. ,% f l 7. M/ NM s _. .
/ (6' Q g j In addition to p.: reauirementsofSubpart,Goffl0CFRPart71% i
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* ;- T / f i \ t? 1 L> I (a) The package must be prepared.forfshjpment and operated in accordance with the i Operating Procedure describ'edJ n the application, 'as supplemented dated September' 18,1991.q;;
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. wJy y l
y Thepackagemustbe1 'n , maintained;in??{$IF_ accordance
/ .h ~ s ! [ gp with'the Maintenance Program I wip (b) 1 describedin..theapplicstionkas!s;upplement,eddatedSeptember i 18, 1991. I !
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- 8. Use of packaging f abricated af ter Abgust 31', .1980p' is nots authorized. l l ls y \l (1 ' p ,
- 9. The package authorized by,this certificate is hereby approved for use under the p
general license provision ~s,lof 10 CFR 71.12. . N
- 10. Expiration date: October 31, k 967f + i(.T REFERENCES l l l
Safety Ana'iysis Report - Packages SRL 4.5-Ton Californium Ehipping Cask, DPSPU i 71-124-6, December 1974, Revision 1, March 1976. I I Supplements dated: September 18, 1991. l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l l 1 Char {dI E. MacDonald, Chief y Transportation Branch y Division of Safeguards 1 00T 0 9 % and Transportation, NMSS I Dates , 2 l
' 157 I l
l ,-------------------------------------------------i
---- -- --------------------------------------------- y mac cons sie u.s. NUCLEAR REGULATORY COMMISSION I
*=> CERTIFICATE OF COMPLIANCE I seCrnT8 FOR RADIOACTIVE MATERIALS PACKAGES I 1 e CERTIFICATE NUMBER b REVISION NUMBER s. PACKAGE IDENTIFICAllON NUMDER g PAGE NUMBER a TOTAL NUMBER PAGES i
6697 9 USA /6697/B( ) 1 3 I e.eacA a I
- a. rni. e.riiicai. is issued io certify inst ine packaging and contenis descnn.d .n item s beio . meets ine appiecebie safety standards set forta in Titi. io. cod.
of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Matenal." I l
- b. This certifmate does not reheve the consignor from comphance with any requiremeryt of the regulations of the U S. Department of Transportation or other I sppi.cabio reouistory .g.nc.es. inciuding the government of ar.y country tnrougn or into which the packso wiii be transported.
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, oN TNc sAsis or A sAerTv AuAtvsis,argT,or,1,Nggggs;Ggoa A,regt e,A,rg, g i
i U.S. Department of Energy General Electric Company Application l EH-33 i dated November 29, 1979, as supplemented. 8 Washington, DC 20585 71-6697 l
, , , , , , i
- 4. CONDITIONS Th6e cattifmate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as appicable and the conditions specified below.
s. I I (a) Packaging l l (1) Model No.: GE.8500 I I (2) Description I i l The packaging is a steel, uranium shielded shipping cask surrounded by I a laminated plywood protective Jacket. I I The shielded cask is an upright circular cylinder, consisting of an inner I shell, 2-7/8 inches ID x-6-1/8 inches.high, made of 1/8-inch thick ' stainless steel which is surrounded by 1-13/16 inches of depleted uranium l and enclosed in a 7-inch OD x 10-1/2-inch high x 1/8-inch thick stainless I steel outer shell, i i Closure is by means of six. 3/8-inch diameter bolts and a 1/8-inch thick I Neoprene rubber gasket between body and lid. The shielded cask is positioned in a two-piece protective jacket of solid plywocd laminations l a which is bolted to a rectangular pallet made of aluminum. The protective I jacket is 15-1/4 inches OD x 20-1/2 inches high and together with the i pallet, weighs 80 pounds. The cavity of the shielded cask contains a I leak tight, steel inner container. The gross weight of the loaded package I is approximately 285 pounds. I (3) Drawings ; 1 The package is constructed in accordance with the following General I Electric Company Drawing Nos.: 277E696, Rev. 6; 277E712, Rev. 6; I 174F482, Rev. 5; 289E795, Rev. 3; 195F169, Rev. 2; 289E796, Rev. 5; 161F443, Rev. 5; or 135C5982, Rev. 4; or 106D3830, Rev. 8 with 153C4613, l p Rev. 1. p i I I I I I 158 l
.__------------------ 1, l
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. _ - . - ~ _ _ . - ~ ~__ - - -
mene---================================mmm==========_q ' N CONDITIONS (continued) i I Page 2 - Certificate No. 6697 - Revision No. 9 - Docket No. 71-6697 ! . T I I
- 5. (b) Contents i I
(1) Type and form of material l , I Byproduct material as a liquid or solid within an inner I container shown in General Electric Drawing Nos. 161F443, Rev. 5; I , or 135C5982, Rev. 4; or 106D3830, Rev. 8, used with the liner shown I in 153C4613, Rev. 1. l l (2) Maximum quantity of material per package l I Greater than a Type A; quantity of byproduct material as a solid with I the decay heat 31oad not exceeding,50 watts. I 3 a -
^
i Byproduct' material as a liquid is limited to 100 ci of Mo-Tc. g S y
- 6. Liquids must be,.further packaged in a leak tight polyethylene bottle within l the inner container. Each polyethylene bottle must be.' sealed and tested in I accordance with Attachment D of General Electric's~1etter dated November 29, 1 1979,orAppendixA:inftheSeptember3,1991," supplement. I at ,
; J- (;
7. l ' Prior to each shipment,'the packags ' lid Neoprene gasket inust be inspected. The I gasket must be replaced with a new Neoprene-gasket if inspection shows any I defect or every twelve.(12) months,1whichever occurs first. In each shipment, I a new Viton 0-ring must.be used to seal the' inner container. I
;r '
- .pykT~ '
- 8.
The inner ' container, must be pretestedito ensure leak tighthess prior to l r e each use in accordance with Attachment D of General Electric's letter dated l November 29 1979,'or: Appendig B?in the-September 3,1991, supplement. l
- 9. The radiation' dose rate must not e'ceed x 1,000 millirem per hour, at a distance of 3 feet:from the surface;of'the depleted" uranium cask, when the l g
wooden protective'-jacket is not in place. , p l
/ I
- 10. In addition to the requirements of Subpart G;of 10 CFR Part 71: 1 I
~
(a) Each package must be mainiained in' accordance with the Maintenance Program j i in the October 4, 1990, and September 3, 1991, supplements; and g I (b) Each package shall be prepared for shipment and operated in accordance I ; with the Operating Procedures in the October 4,1990, and September 3, I i 1991, supplements. l l
- 11. The package authorized by this certificate is hereby approved for use under g the general license provisions of 10 CFR 571.12. I i
- 12. Expiration date: September 30, 1996.
l i I I I I I I !' 159 i l
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CONOtTIONS (contonved) lll l
'll l
q Page 3 - Certificate No. 6697 - Revision No. 9 - Docket No. 71-6697 n' l, P REFERENCES I h I l General Electric Company application dated November 29, 1979. j i i . I General Electric letter dated February 21, 1985. I I I I DOE supplements dated: February 27, 1985; January 31 and October 4, 1990; and I September 3, 1991. l l l 1 i FOR THE U.S. NUCLEAR REGULATORY COMMISSION Ig i I I I I d'p .v % I l D- fxM b Charles'E.(MacDonald, Chief Transportation Branch l l I d(']g Division of Safeguards i I -sl' > and Transportation, NMSS I i y'}}