ML20033A666

Sar:Tech/Ops Model 858 Type B(U) Package

ML20033A666
Person / Time
Site:	07109154
Issue date:	10/29/1981
From:	TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML20033A665	List: ML20033A664 ML20033A666
References
19858, NUDOCS 8111270002
Download: ML20033A666 (72)

Text

,

Tech /Op3 Radation Products Dwision (x,

40 North Avenue e

i Burbngton Massachusetts 01803 Telephone (617) 272-2000 29 October 1981 Mr. Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. MacDonald:

We request issuance of a USNRC Certificate of Compliance of Radioactive Materials Package for Tech / Ops, Inc. Model 858 Type B Package. We are enclosing eight copies of the Safety Analysis Report for the Model 858 for your review.

In accordance with 10CFR170.31, Item 11E, we are also enclosing a check for $200 for the application fee.

We are applying to the U.S. Department of Transportation for an International Atomic (O

Energy Agency Certificate of Competent Authority for Type B(U) packaging under the 1973 Revised Edition of IAEA Safety Series No. 6.

We ask that this package be reviewed for conformance to these requirements also.

We trust that this application satisfies your requirements for issuance of this certificate.

If we can provide any additional information, please contact us.

Sincerrht

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Ohn J 49 ro III Tec nical Director

/

v JJM/fb Enclosures oV 19S58 8111270002 811029 PDR ADOCK 07109154 C

PDR

Tech / Ops Radiat on Products Omson m

40 North Avenue

,j Burkngton, Massachusetts 01803 Telephone (617) 272-2000 29 October 1981 Mr. Richard R. Rawl, Chief Radioactive Materials Branch Office of Hazardous Materials Regulation Materials Transportation Bureau Research ani Special Programs Administration U.S. Department of Transportation 400 7th Street NW Washington, DC 20590

Dear Mr. Rawl:

We regt.est issuance of an International Atomic Energy Agency Certificate of Competent Authority for Type B(U) packaging under the 1973 Revised Edition of IAEA Safety Series No. 6 for Tech / Ops Model 858 Type B package.

We are enclosing a copy of the Safety Analysis Report for this package. We have filed a similar application with the U.S. Nuclear Regulatory Commission requesting issuance of a USNRC Certificate of Compliance for this package.

'le trust this application provides the information necessary for your review. If we can provide any additional information, please contact us, ince 1-

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Tech / Ops u.

,ac Radation Products Dwson O

Burtngton, Massachusetts 01803 40 North Avenue Telephone (617) 272 2000 SAFETY A!iALYSIS REPORT TECil/0PS MODEL 858 TYPE B(U) PACKAGE F

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V 1.0 General Information 1.1 Introduction The Tech / Ops Model 858 is designed for use as a gamma ray projector and shipping container for Type B quantities of radioactive material in special form. The Model 858 is similar to Tech / Ops Model 680 (USA /9035/B(U)) and Tech / Ops Model 676 (USA /9029/B(U)).

The Model 858 conforms to the criteria for Type B packaging in accordance with 10CFR71 and satisfies the criteria for Type B(U) packaging in accordance with IAEA Safety Series No. 6,1973. The source to be used in conjunction with the Model 858 is Tech / Ops sealed source assembly Model No. A424-14. The Model 858 will contain a maximum of 110 curies of cobalt-60 as special form.

1.2 Package Description 1.2.1 Packaging The Model 858 is 14.62in (371mm) high, 21 inches (533mm) long and 12 inches (305mm). wide. The gross weight of the package is 502 pounds (228kg).

The radioactive source assembly is stored in a zircalloy or titanium "S" tube in the geometric center of the package.

The "S" tube is cast inside a depleted uranium shield assembly. The weight of the uranium shield is 327 pounds 149kg.

The shield is enclosed in a shell f abricated of % inch (6.35m) thick hot rolled cteel. The shield is fixed in position within the shell by the retaining bar assembly and the collimator positioning tube. Tie void space between the shield and the shell is filled with a castable rigid polyurethane foam. Steel-uranium interfaces are separated with 0.010 inch (0.254mm) thick copper separators.

Attached to the sides of the container are 0.50 inch 12.7mm thick hot rolled steel side frames which are welded to the shell using a % inch fillet weld.

Mounted at each end of the "S" tube are positioning devices. The source assembly is locked in position by means of the control cable connector and additionally secured by means of a shipping plug. A protective shipping plate (% inch thick steel) is mounted over the control cable connector assembly.

Tamperproof seals are provided during shipment of these sources.

Assembly joints which are not leak-tight and two one inch diameter pour holes provide passageways for the escape of any gas generated from decomposition of the potting foam in the event the projector is I

involved in a fire accident. The outer packaging is designed to avoid the co11cetion and retention of water. The package is painted and p

finished to provide for easy decontamination. The radioactive material is scaled inside a source capsule, which is the containment vessel of the package.

REVISION O 29 Oct 1981 1-1

~

The Model 858 is sin.ilar to the Model 676 which has been approved for use as a Type B package under USNRC Certificate of Compliance No. 9029 and is also similar to the Model 680 which has been previously approved for use as a Type B package under USNRC Certificate of Compliance No.

9035.

1.2.2 Operational Features The source assembly is secured ia the proper position by the control cable connector and lock assembly. This assembly requires a key for operation, and thus provides positive closure. A % inch (6.35mm) thick steel shipping plate is used to protect the assembly during shipment. Additionally, the source assembly is secured by means of a shipping plug inserted in the opposite end of the "S" tube.

1.2.3 Contents of Packaging The Model 858 is designed for a capacity of up to 110 curies of cobalt-60 as Tech / Ops Source Assembly A424-14. The source assembly is in special form as prescribed in 10CFR71 and IAEA Safety Series No. 6, 1973.

O REVISION O 29 Oct 1981 (O

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1.3 APPENDIX l

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.--y 7, - 2Vk RADOCTIVE SOURCE ASSY.. + \\ E Tm -lthT FETAINiNG B R (REF 1 Miri-BOTH SCE5 \\\\ TOP PLATE 4 ,y;JUSTlhG SCPEW(REF) s ( f/2 TW WsT ROLLED STEEL) \\ ) N \\ \\ V1 9 t / / /\\ /\\ / r 15 c / / r / / n B e 'Q j-20 HEX HP EfX$/JETY Wif q',-Q 7_ N/ N my i N p (x N Vy y s N $7 EEL) (4j f '\\ I' [,. y_ _ _ _;Lh j ^G) p my - ~ ,~--" '4_L , Q 3 [ x, _+ - .- ( SWIPPING PLUG AS5V - % T\\ '\\ \\ \\ ~ - LOCK ASSEME1Y-REF. / N y,. x s b 'N N N x x / ~%N _ - SHIPPtT6 PLATE (PEF) \\ iA. ,/ 'N / j / p y\\ \\ s COLLI \\tATOR PO51Tionir0 TUBE N ~ '/ / , 'N h N \\ w / N ~ l'y 1 '/ \\ k 'x - S TUBE-A67 0.D n.385 f.D. ( HOT ROLLED STEEL'< _SEE DETAIL C - SHT 3 N ~ [ j \\{ s. N L s s ,/ / N - $WELL N. ( t/4 TW HOT POLLED STEEL) } p q._ { g, /.Qhx '. ~ 's N 'x. s NN ,j. N [ ff // f / ./ /. / ~ \\/ \\ /I RIGlD POLYURETWAr4E RMM /

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/ s SWlELD (DEPLETED URAN!UM) / N *) s S_ECTION A._A / \\g, /gg79 S.DE5 = _ _ _ _ _ _ i 3 V SLEEVE (ZlRCALLOY OR TITArruM) cCPFER Rir6(1)) COFFER 0$K(2 - E*DT7DM PLATE CmT inTo SactD ( V2 THX HOT PCLLE9 7 TEEL) (.olo w) .~ NOTED E "'** L W.I."**' ODEL 898 REECTOR < 6., - - >,,m,,,, DESCRIPTIVE ASSEMBLY 1 .x s g -w l.a !m a 85690 lo. m C m. x l "[ ' ~ ~ ~ ' 3-, ; yy -SE PAR /YTOR (.Of 0 THK COPPER) / LEVEUhG PLATE / (1/8 THK COD ROLtID TC_EL) BOTTOM PLMF-FEJ / ' ) l o a \\/ s . _. - - s.~. c. - x ,1 h CONNECTOR PLATE 90L5CE ICENT. [ABEL

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(I/T2 Att;M) FAWED U /4 THK HOTRollED STEEL Iy)TI s q N' WITH 2

• 4-40 SCREWS y

fQ M' x ir 3. x 4 x x \\ g' 'g y l LOCK A$$Y / N T \\ x; .. '.N L, 'p (SEE C66025 Skr5 A(5) i J'{ ' ' N x a%2w Gf g. m Ns ri x\\ --( / / / _1 ~ x lx fy -Surac anE sq' \\ I/4 THK CCAD POLLED STEEi. Q.. x YT g' x N>NNN NI N-t x - s 0 + o 'l / / 'N M3/3 24 hex HDECLT / ( & LOCKWASHER (6) vErmrca.i/ ~ _.. / (STEEL) SEAL WIRED POURlhG HOLE l' D'A (2) SEE VIEW D (7HT 5) $hI f J ANNTG LJBEL (0 L-NAMtHATE (7) (.C% CCtD FDLLED STEEL) (.02OHK MtD STEEL) WELDED IN PLACE STEEL RIVETED B-B _SECTION. _. _. _ NOTED ~. '

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hCDEL Efa8 PROJECTCR =.rs =.. _ DESCRIPTNE ASSEMBLY

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1 C 65690 l0 4 s ~. - a = va ~ ~ ~. l-o R l Of L TB C L EM J E 0-Q O Fj 9 PM 8 _. R 5 Q-E 8 2V TI 8 P - I lf-L R E C l D 9 %. I M O E ~M D .f /, 2 N x r m. m u s 6 e ~ eS ~ -Q - ~ N 8 ~ r. y 3 \\ 10 N g N' a, \\ 7 \\ \\ il p ~ = 1 3l 2 DG 3-A r TA S D B L D L 7 E 2 3 lH S 2 5 l ,l l T 7 1 6 9. = ) DP V 8 O o T ~ s i

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ig[ og % 11 _a a r t [ /2 pr /gBOTTOM PLME-ftEF E g 8 p I 3 2 / g r 1 1 / j lv / / rCLEAT(4) WELDED 10 $ HELL / g y 77 f]4 THY COLD ROLLED STEEL f V / if g: r l e ADJUSTING SCREW (2) { ' ' ' l l

• I/2-13 THFEACED RCO, STEEL I

I/2-13 JAM NUT (lo) gi i I 3E ' l b l LL RETAINING BAR(2) / f/4 THK COLD RXLED STEEL k i 1 y y COPPER TUBE D l ', .010 NALL TillCKre55 (} / l SHIM (?) 010THX COPFER IN) I i .k Sl d _1_C 'AM NUT) \\ } CA r/ / / /V // / '~ i AoJusTinG Nui(7) f I 3/4 HEX COLD ROLLED 9 TEEL 1 C) VIEW D ROTATED 180* { SCALE:l/l l S t? Io ~ n ? Lj l 0 E (RANIUM SHIELD U \\ l Y il gE3 REF) m 0 q) f I - h J I 8 g, 527 r / / / - n: L /\\

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/ ~ s 8 y f[ f. g I t. ai / 2 3 i s t ) g_ ' dl E\\' l / COPPER = RIT67 4 DISK r '(REF) (J~ pq+N N x( t /> Igxxx / / SHIPPING PLUS A55Y- ' g (REF) 51 e / r s ,/ \\ v gV - s, / / / / L' N b O' SHELL(REF) DETAll C gV '~ SCALE: t/I J-9 h I s5n ses & ~ ,a END PLATC.- REF. -MODIFIED LOCK (CORBIN # O2290) LOCK RETAINE^ 10-2 E HD (304 STAIN. STL) \\ CAP SCREW (2) \\ WiTH LOCTITE / f j' }'g 3 \\ \\' $ELEC10R RtroG Y .\\ COVER .\\ "ffy% L f (304 STA!N.STL) y on wrt,.mx SELECTm BCOY /b \\ e, , ! d' (BIRYLUUM COCPER) / 4- @ D / + 4 g/ / [ _ _I =[El[ "" '/ / COMPRESSai SPRING l /// (MLSC WlRE) y 3- (!/l, / / q j h h SEE SHE S } } cp,/ 3 B

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g Y / y / 40-52 50C.HD CAP SCR" V C 's"y cAuYa$ h- ]M MQ) [ / s-(STAJit.STt.) 4 ~ WITH LOCTITE / s / / / L AIN E ANTI-ROTATE LUGS ( ) / 2 (304 GTAIN. STL) j & cxmSvion spara SaECU RNG LOCKING RNW1ECOOLWS) C (3C4 STAN. STL) WITH COMFRE55lON SPPrG LOCK ASSEMBLY SECTION C-C @lSC WRE)(2 ~~ -ygy,A,, NOTED 4 % IEL 660 GAMMA RAY PFDJECTCR ~ {4,y *~ y' - SHIPRNG CONTAINER ,N DESCRIPTIVE ASSEMBLY [,.

• i Tl 66027 l A'

Crs mM~ C"I g ig A = 7 ggg l REF i = 8 i LCCKING PIN (PEF) I t SCORCE ASSEMBLY / // f ' ^ d" s \\" [ ('2:k~'//?' A / .'f % '/ / } i [ t ,._j 4 =. _. .x,5 p _g;1;!;(Q // a o <a j bq \\' J,/ gafa mm A N stegyg &'^ ~ ->g' hgg use "% ' '!x. v ~ 'Q, y({;-g,c_ t /y LOCKED PCFam0N } i ~., - 2jREF ~ s 1 /,' 7 'l 'f k h h f' ' ' ' $( sec SEFARATE VIEWS ^ 7-L... /%_ _t ' 'u / SELECTOR RING (RER) %3, ~ N,1 0. p SELECTOR BODY (REF.) en yNtocco rwmcn I SECTION B-B '"~ 1 noTED E = ~ U(EEL 660 6AMMA RM PRG)ECTOR ~ 7 *,,,, f'My'x-SHIPP!NG CONTAINER DESCRIPTIVE ASSEMBLY' ' - ' 7 ( E. lUI~~66025 lA

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2. Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally the Model 858 consists of five components: a source capsule, shield assembly, outer shell, side frames a:d lock assembly. The source capsule is the primary containment vessel. It meets the requirements for special form radioactive material as outlined in 10CFR71 (see Section 2.8). The shield is 327 pounds (149kg) of depleted uranium. The shield assembly fulfills two functions. it provides shielding for the radioactive material and, together with the positioning mechanisms insures proper positioning of the source. The shield assembly is supported on one end with retaining bars whie.h are forced together by means of hex nuts threaded on adjusting screws. The-adjusting screws and retaining bars are secured with jam nuts. The shield is supported on the opposite end by the collimator positioning tube. The entire shield assembly is potted in a castable rigid poly-urethane' foam and encased in a ! inch (6.35mm) thick hot rolled steel. shell. Steel-uranium interf aces are separated.with copper. Attached to the shell are side frames made of 0.50 inch (12.7mm) thick stol which are welded to the shell. The key operated lock assembly oad control cabic connector secure the source in the shielded position. A % inch (6.35mm) thick steel shipping cover plate is installed to protect the lock from damage. Positive proof of source position is O evidenced by the use of seal wire on this shipping cover plate. 2.1.2 Design Criteria The Model 858 is designed to comply with the requirements of 10CFR71 4 and IAEA Safety Series No. 6,1973. The device is simple in design, such that there are no design criteria which cannot be evaluated by straight-forward application of the appropriate section of 10CFR;i or i L4EA Safety Series No. 6,1973. 2.2 Weights and Centers of Gravity The Model 858 projector weighs 502 pounds (228kg). The shield assembly contains 327 poands (149kg) of depleted uranium. The center of gravity is located approximately at the geometric center 4 of the package. 2.3 Mechanical Properties of Materials j The Model 858 gamma ray projector shell is made of hot rolled steel. This 2 material has a yield strength of 40,000 pounds per square inch (276MN/m ), (

Reference:

Machinery's Handbook, 20th Edition, 1976, p. 452).

REVISION O O

29 Oct 1981 2-1

2.4 General Standards for All Packages 2.4.1

. Chemical and Galvanic Reactions-The materials used in the construction of the Model 858 gamma ray projector are uranium met d, steel, beryllium copper, bronze, copper, and zircalloy'or titanium. There will be no significant chemical or galvanic action between any of these components.

The possibility of the formation of the eutectic alloy of iron uranium at temperatures below the melting temperatures of the individual metals was considered. The iron uranium eutectic ~ alloy temperature is approxi-mately 1337'F (725 ).

However, vacuum conditions and extreme cleanliness 0

of the surfaces are necessary to produce.the alloy at this low temperature.

Due to the conditions under which the shields are mounted, sufficient contact for this effect does not exist.

In support of this conclusion, the fellowing test results are presented.-

A thermal test of a sample of bare depleted uranium metal was performed by Nuclear Metals, Inc. The test indicated that the uraaium sample oxidized such that the radial dimension'was reduced by 1/32 inch. A subsequent' test was performed in which a sample of bare, depleted uranium metal was.placed on a steci plate and subjected-to the. thermal test conditions. The test showed no alloying or melting characteristics ~in the sample, and the degree of oxidation was the same as evidenced in the first test. A copy of the test report appears in Section 2.10.

Although the likelihood of the formation of an iron-uranium cutectic alloy is remote, copper separators are used at steel-uranium interfaces.

2.4.2' Positive Closure The Model 858 source cannot be exposed without opening a key-operated lock. Access to the lock requires the removal of the shipping cover plate. Additionally, this shipping cover plate is seal wired and provided with a tamperproof seal.

2.4.3 Lifting Devices The Model 858 is designed to be lifted by two eyebolts, Armstrong No. 27.

These eyebolts are fastened through the container end plate by 5/8 - 11 nuts. Both the nut and the eyebolt shoulder are welded to the container-endplate by a 3/16 inch fillet weld all around.

The root diameter of a 5/8 - 11 thread is 0.5135 in.

Therefore, the 2

root area is u.207 in. Assuming that the material has a yield point of 40,000 psi, each eyebolt can support '8,280 pounds without exceeding the yield strength of the material. This is more than 16 times the weight of the package. Therefore, the lifting is capable of supporting more than three times the weight of the package as prescribed in 10CFR71.31(c).

REVISION O 29 Oct 1981 2-2

~

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2.4.4 Tiedown Devices v

The tiedown devices on the Model 858 are the eyebolts. As shown in the above analysis, these eyebolts can withstand the load combination of 10CFR71.31 without exceeding the yield strength of the material.

2.5 Standards for Type B and Large Quantity Packages 2.5.1 Load Resistance Considering the package as a simple beam supported on both ends with a uniform load af 5 times the package weight evenly distributed along its length, the maximum strcss can be computed from:

s - r_1, 8Z where:

F: total load (2510 pounds) 1: length of beam (21 inches) 8 Z: section modulus of beam (85.6 in )

(

Reference:

Machinery's Handbook, 21st ed.,1979, p. 404)

Thus, the maximum stress generated in the beam is 77.0 pounds per 2

(~'}

square inch (532kN/m ), which is f ar below the yield strength of 2

's

/

the material, 40,000 psi (276MN/m ).

2.5.2 External Pressure The Model 858 is open to the atmosphere; thus, there will be no differential pressure acting on it.

The collapsing pressure of the source capsules can be found:

P = 86,670 t - 1386 D

where: P: collapsing pressure in pounds per square inch t: wall thickness in inches (0.020 inch)

D: outside diameter in inches (0.25 inch)

(

Reference:

Machinery's Handbook, 21st ed., 1979, p. 440)

The collapsing pressure of the capsules is calculated to be 5550 2

pounds per square inch (38.3MN/m ).

Therefore, the capsule can withstand an external pressure of 25psig.

REVISION O 29 Oct 1981 ps

.w 2-3

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2.6 Normal Conditions of Transport 2.6.1 Heat The thermal evaluation is performed in Chapter 3 of this application.

From this evaluation, it can be concluded that the Model 858 can withstand the normal heat transport conditions.

2.6.2

. Cold The metals used in the manufacture of the Model 858 can all withstand 8

0 temperatures of -40 F (-40 C). The lower operating limit of the polyurethane foam is -100'F (-73'C). Thus, it is concluded that'the Model 858 will withstand the normal transport cold conditions.

2.6.3 Pressure The Model 858 is open to the atmosphere; thus, there will be no differential pressure acting on it.

In Section 3.5.4, the source capsules are demonstrated to be able to withstand an external 2

pressure reduction of 0.5 atmospheres (50.7kN/m ),

2.6.4 Vibration The Model 858 is similar to Tech / Ops Model _680 which has been in use for eleven years. During that time there has never been a

,_/

vibrational fa'h:re reported. Thus, we contend the Model 858 will not undergo a vibrational failure in transport.

2.6.5 Water Spray Test The w.?er spray test was not actually performed on the Model 858.

We contend that the materials used in construction of the Model.858 are all highly water resistant and that exposure to water will not reduce the shielding or affect the structural integrity of the package.

2.6.6 Free Drop The drop analysis performed in hypothetical accident conditions (see i

Section 2.7.1) is sufficient to satisfy the requirements outlined for the normal transport free drop condition in 10CFR71 and IAEA Safety Series No. 6, 1973. On this basis, we conclude that the Model 858 can withstand the free drop without impairment of the shielding or package l

j integrity.

1

[

2.6.7 Corner Drop Not Applicable a

f REVISION 0 29 Oct 1981

()

2-4

m x -

y 2.6.8 Penetration A penetration test of the Model 858 was not actually performed.

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However, the similar Model 684 was subjected to the penetration

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test with no resultant loss of shielding or package integrity (a copy of the test report is enclosed in Section 2.10).

The following analysis demonstrates that the maximum damage exhibited by the Model 858 due to the penetration test is less than that of the Model 684.

The maximum stress observed in a flat rectangular plate supported on all edges due to concentrated central loading is:

In [ L

+ 0.577 J=

0.62F L

(2r 2

3 o

where: F:

total load t : thickness of plate (inches)

L:

length of longest side (inches) r,:

0.325t (inches)

(

Reference:

Machinery's Handbook, 21st ed., 1979, p. 436)

The appropriate dimensions for the Model 858 and Model 684 are:

Model 858 Model 684 I i t

0.25 inch (6.35mm) 0.1875 in. (4.76mm) wi L

21 inch (533mm) 17 in. (432mm) r 0.0813 in. (2.06mm) 0.0609 in. (1.55mm) o The calculated stress for tae Model 858 is 54.0F; for the Model 684, it is 97.3F.

In both cases the load F (40 inch drop of a 13 pound hemisphe-rical billet) and the material of construction (hot rolled steel) are the The maximum stress, and thus the maximum damage, to the flat plate same.

occurs in the Model 684. The shipping plate which protects the lock mechanism is the same in the two models. As the Model 684 successfully withstood the penetration condition, we conclude that the Model 858 will undergo the penetration test with no loss of structural integrity or shielding.

(A copy of the test report for the Modt1 684 is enclosed in Section 2.10).

2.6.9 Compression The gross weight of the Model 858 is 502 pounds (22Skg). The maximam cross-sectional area of the package is 307 square inches (0.20m ).

Thus 2

two pounds per square inch times the cross-sectional area (614 pounds, (279kg) is less than five times the package weight, 2510 pounds (1141kg).

For this analysis, the load will be taken to be 2510 pounds.

REVISION O

[)

29 Oct 1981 v

2-5

[dO The maximum stress generated in a flat rectangular steel plate with all edges fixed and a load distributed uniformly over the surface of the plate can be computed from:

S=

0.5 F 2 _1,+0.623/1j5_

t

\\"I -

where:

S: maximum stress F: total load (2510 pounds) t: thickness of plate (0.25 inches) w: width of plate (14.6 inches) 1:

length of plate (21 inches)

(

Reference:

Machinery's Handbook, 21st ed., 1979, p. 436)

From this relationship, the maximum stress generated in the plate is 2

3807 pounds per square inch (26.3MN/m ).

This figure is greatly belcw the yield strength of the material, 40,000 pounds per square inch 2

(276MN/m ).

Thus, it can be concluded that compression will not adversely affect the package.

2.7 Hypothetical Accident Conditions

]

A2 2.7.1 Free Drop The Model 858 was not actually sebsitted to the 30 foot drop test.

However, the Model 672 was submitted to the drop te.st (thc test report appears in Section 2.10).

The Model 858 has approximately the same weight and is constructed from the same materials as the Model 672.

Model 672 Model 858 Length 24 inches (610mm) 21 inches (533mm)

Width 14 inches (356mm) 14.6 inches (371mm)

Height 12.5 inches (318mm) 12 inches (305mm)

Weight of Shield 401 lbs. (182kg) 327 lbs. (149kg)

Gross Weight of Container 580 lbs. (264kg) 502 lbs. (228kg)

Side Frame Material 1 in (25mm) thick hot 0.5 inch thick (13mm) rollea steel hot rolled steel Shell Material

% inch thick (6.35mm)

% inch thick (6.35:sa) steel hot rolled steel

,O

'ss' REVISION O 29 Oct 1981 2-6

O Based on the satisfactory performance of the Model 672, we conclude k'

that the Model 858 will undergo no loss of shiciding or structural integrity as a result of the 30 foot free drop test.

2.7.2 Puncture The Model 858 was not submitted to the puncture test of 10CFR71.

Ilowever, the similar Model 676 was submitted to the puncture test.

There was no resultant damage to the container, nor reduction in shielding. (A copy of the test report appears in Section 2.10).

The shipping plate used in the Model 858 is the same as that used in the Model 676. The Model 676 puncture test report (included in Section 2.10) shows that the shipping plate withstood the puncture test.

On this basis, we concluda that the Model 858 can successfully withstand the puncture condition of 10CFR71.

2.7.3 Thermal The thermal analysis is presented in Section 3.5.

There it is shown thattheceltingpointofthematerials,exceptthepottingcompound, used in the construction of Model 853 are all greater than 1475 F 0

(800 C).

Thus, it is concluded that the Model 858 satisfactorily meets the S

requirements for the hypothetical accident-thermal evaluation as

)

set forth in 10CFR71..

2.7.4 Water Immersion Not Applicable 2.7.5 Summary of Damage The tests designed to induce mechanical stress (drop, puncture) would cause minor deformation, but no reduction in the safety features of the package. The thermal test will result in no reduction of the saf2ty of the package. It can be concluded that the hypothetical accident conditions have no adverse ef fect on the shiciding ef fectiveness and structural integrity of the package.

2.8 Special Form The Model 858 gamma ray projector is designed for use with Tech / Ops source assembly A424-14. This source assembly has been previously certified as special form radioactive material.

(IAEA Certificate of Competent Authority No. USA /0165/S, see Section 2.10).

We contend that this certificate is suf ficient evidence that the requirements for special form radioactive materials, as established in IAEA Safety Series No. 6,1973 are satisfied.

O 2.9 Fuel Rods N,I Not Applicable REVISION 0 29 Oct 1981 2-7

O 2.10 APPENDIX Nuclear Metals, Inc., Test Report: Iron Uranium Alloying Test Report: Penetration Test, Model 684 Test Report: Drop and Puncture Tests, Model 672 Test Report: Puncture Test, Model 676 Descriptive Assembly Drawings, Source Assembly IAEA Certificate of Competent Authority No. USA /0165/S O

REVISION O 29 Oct 1981 0

2-8

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- ca s w.si.atte CO,ger:0 uAs%4csaustits o 743 28 January 1974 Technical Operations, Inc.

Radiation Products Division South Avenue Burlington,flassachusetts 01803 Attention:

f1r. J. Lima L

Gen tlenien :

in responw to a request by Joe f.ima of Tech Ops, a simulated fire te' t was perfonned on sanples of bare depleted uranium in contact with mild i

i steel, the object being to determine what, if any, alloying or meltinq l

l would occur under these condi tions.

TEST DATA:

h A 3/4-incl. diameter x 5/8-inch lonq bare droleted uranium specimen was set on a 1-inch diameter x 1/8-inch thici mild steel plate, placed in a (n) thin wall ceranic crucible.

A mild steel cover plate was used on top of the crucible to act as a partial air seal.

The crucible was loaded in a preheated 1,lS0"f resistance heated furnace, held for 35 minutes, then removed and allowed to air cool under a ventilated hood.

i i

1

-Fi. llLT S :

T'o react ion was evidenced between the two metals.

Both separated readily and showed no alloying or ueltinn characteristics.

0xidation of the uranium was about the sar,s degree as that reported to Joe Lima on an earlier experiment.

The tes t was performed by ritil on 25 January 1974.

Very truly yours,

.$cca

/

(' John G. Powers Project Engineer 7

,m

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v g_ 9 REVISION O-29 ocr 1981

__.-__------.,---.---,,.-n_

I o

TEST REIORT ROIATIO:.' PRODUCTS DIVISION FY:

Jchn J. Munro fII DATE:

5 September 1979 S! TBJECP: Pode1634 Ter.etration Teat On 5 September 1979 a penetration test was perferced on a Technical Operations Medel 68b Shipping Contairer i. acccrdance with 10CFR71 Appendix A.8 and I A?.A Safety Series 'Io. 6,1973, raragraphs 714a and Tlkb.

The hemispherical end of a vertical steel cylir. der 1.25 inch in diameter weighirg 14 pounds was dropped frem the height of 43 inches onto the geometric center of the bottom surface of the Mcdel 68h. There was no defermation and no damage which vculd affect the shieldit.g or structural i utegri cy of the package.

A second test was conducted using the same cyli. der.

It was dropped from the height of h0 inch-s onto the shippir:g pInte. There was r.o deformation and no damage which would affect the shielding er structural integrity of the packaie.

Docut: entry photographs are enclosed.

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TEST REPORT OESC R I P T I Ott:

Model 672 - 30' Drop DATE M.irch 18,1970 The first drop test landed on the right rear corner of the side plate and was bent in 1-1/2" and forward 1/2". No other daintige was sustained.

The second drop test landed on the left side of the side plate breaking 2/3 of the weld and was bent in 1".

The Source Tube remained straight and the front nut turned freely.

The puncture test (11" drop on to a G" dia, steel billet) left a slight mark on the skin.

C0t4CLU510ti:

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i BY ltichard Evans WITtJESSED BY Fred llauser k

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DESCRIPTION:

DATE 9 necember 197h li 1

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Puncture Test of Model 676 Container Connector J

A Model 676 GaI=a Ray Projector with Shipping Plate instelled was dropped from a height of 40 inches onto a six inch diameter, eight inch high steel Billet es shown in Figure 1 e. The Container impacted on the Shipping Plate sa shown in Figure 1 b.

4 i

CONCLUSION:

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resulted. There was no reduction of shielding effectiveness nor lose of Radioactive Material.

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I AEA Ch.RTIFICATE OF COMPETENT AUTiiOKITY 9

I

s. r e a n vo.

EP"_C.I.D.1 Form Radi cac t_ive f a t eri al Encapsul a t ion certificate Number USA /0165/S (Revision 0) i This cer t i f ies t hat the encapsulated sour (es, as described, when loaded with the authorized r adioact ive contents, have been denonstrated to meet j

j the regula t ory r"quirewats for special forn radioactive r'aterial as I

2

{

prescribed in IAEA anJ USA Fegulations f or the transport of radioactive j

r.e4 t c ri a l s.

I Sou- -- r_c e-De_s c ! i n t i o.n.a n d Ea d.i.. oa c t. i ve.Co n_t_e n. t_r - Th e sources described I.

ly this cert ificat e consist of the following Technical Operations, Inc.,

j 4

l nodels whi ch a re velded capsulc, const ructed of either 304 or 304L l

a s t a i ni e r.s e, t e e l to the l ist ed c:,psul e designs (see Appendix A) and which t h.m the list ed quanti t ies of Coha' c 60 in wet allic fo.c:

f contain not more l

(

l

.. Cuties).

0d 01 c.m nle S t v._i c_

A t t i v i t.y A624-2 60011, 60001 22 I

A424-3 60011, 60001 22 A424-4 60011, t0000 55 A424-5 600]!, 60001 6

j 1

A424-7 60012, 60002 165 l

A424-8 60011, 60000 110 A424-10 60011, 60004 6

j A424-ll 60011, 60004 55 i

l Au24-12 60011, 60004 110 i

A424-13 00012, 60002 330 i

A424-14 60011, 60004 110 l

A424-15 60011, 60004 11 A424-16 60011, 60000 55 i

A4 24-17 60011, 60000 55 A424-18 00011, 60000 33 A424-19 60001, f,0004 0.11 A453-1 60011, 60000 110 A453-2 60012, 60002 165 A453-5 60012, 60002 550 l

A452 6 I0013, 6D003 1100 A453-1 t0011, 60000 110 A453 8 60011, 60000 55 A453-9 60011, 60000 55

(

A453-10 60011, 60000 55 l

F i

O 2-2s REVISIO O 19 ocr i9&t 1

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I l

l Certificate Non.be r US/ '016 5/S, gesision 0 page 2 l

l r

II.

This certificate, unless rrneved, expires on Sept aber 30, 1982.

This certificate is it.soed in accordance with paragraph 803 of the l

IAEA Fegulations and in nesponse t o t he.luly 26, 1979, petition by

[

Technien1 Operations, Inc., Burlington, Ma tr.achuse t t s, and in j

censideration of the associated *information therein.

I I

l Certified by-NN?,,

M 2.N h

(Date)

R. R. i< a wl l

Pe!ignated U.S. Cc:petent Authority f or t he int ernational Transport at ion of Radioactive Mat eriait, Office of Hazardous Materials Retulotioa Mat erials Tr anspo. t at ion T.urcau l

U.S. Depar t ment of Transportation l

1" Safety Series No. 6, Fegulations for the Safe Transport of Eadioactive l

Revised Edi t ion" publi shed by t he International Materials, 197.5

/.tomic Energy Agency (1/.EA), Vi enna, Aust r i a.

Title 49, Code of Federal Ecgulations, art 170 -178, tis A.

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i f

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f.

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BEVISION O 7M Ctr1f31 I

0 2 - 26 j

[

S

%g 4

9

'M mm h w

3.0 Thermal Evaluation J

3.1 Discussion The Model 858 is a completely passive Lnermal device and has no mechanical cooling system nor relief valves. All cooling of the package is through free convection and radiation. The heat source is 110 curies of cobalt-60. The corresponding decay heat is 1.84 watts.

32.

Sutrnary of Thermal Properties of Materials The melting points of the materials used in the construction of the Model 858 are:

Steel 2453 F (1345 C) 8 8

Uranium 2070 F (ll33'C) 8 Copper 1940 F (1060'C) 8 Titanium 3300'F (1820'C)

Bronze 1840 F (1005'C) 8 Beryllium Copper 1600 F

( 870'C) 8 Zircalloy 3350 F (1845 C) 0 Thepolyurethanefoamhasaminimumoperatingrangeof-100'F

(-73 C) to 200 F (93 C).

It will decompose at the fire test 0

8 0

temperature (800 C).

Decomposition will result in gaseous D

byproducts which will burn in air.

d 3.3 Technical Specification of Components No Applicable 3.4 Normal Conditions of Transport 3.4.1 Thermal Model The heat source in the Model 858 is a maximum of 110 curies of cobalt-60. Cobalt-60 decays with a total energy liberation of 2.82 MeV per disintegration or 16.7 milliwatts per curie.

Assum-ing that all of the decay energy is transformed into heat, the heat generation rate for the 110 curies of cobalt-60 would be 1.84 watts.

To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 Edition for Type B(U) packaging, an analysis is presented in Section 3.6.1.

The thermal model employed is described in that section.

To demonstrate compliance with the requirements of peragraph 240 of IAEA Safety Series No. 6, 1973 Edition for Type B(U) packaging, an analysis is presented in Section 3.6.2.

The thermal model employed is described in that section.

REVISION O 29 Oct 1981 i

3-1 i

o\\

3.4.2 Maximum Temperatures

/V The maximum temperatures encountered under normal conditions of transport will have no adverse effect on the structural integrity or shiciding. As presented in Section 3.6, the maximum temperature in the shade would be less than 41'C and the maximum temperature -

when insclated would be less than 63'C.

3.4.3 Minimum Temperatures The minimum normal oparating temperature of the !bdel 858 is -40*C

(-40'F).

This temperature will have no adverse affect on the package.

3.4.4 Maximum Internal Pressures Normal operating conditions generate negligibic internal pressures.

Any pressure generated is significantly below that generated during the hypothetical thermal _ accident, which is shown to result in no loss of shielding nor containment.

3.4.5 Maximum Thermal Stresses The maximum temperatures that occur during normal transport are low enough to insure that thermel gradients will cause no significant thermal stresses.

O)

(,

3.4.6 Evaluation of Package Performance for Normal Conditions of Transport The thermal conditions of normal transport arc insignificant irom a functional viewpoint for the Model 858. The applicable conditions of IAEA Safety Series No. 6, 1973 Edition for Type B(U) packages have been shown to be satisfied by the Model 858.

3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model The Model 858, including the source assembly, is assumed to reach the thermal test temperature of 800"C.

At this temperature the polyurethane foam will have decomposed and the resulting gases will have escaped the package through vent holes and non-leak tight assembly joints.

3.5.2 Package Conditions and Environment The Model 858 underwent no significant damage during the free drop and puncture tests.

the package used in this analysis is considered undamaged.

REVISION O 29 Oct 1981 O

v 3-2

O 3.5.3 Package Temperstores As indicated in Section 3.5.1, the entire package is assumed to reach a temperature of 800'C.

Examination of the melting temperatures of the materials used in the construction of the Model 858 indicates that there will be no damage to the package as a result of this tempera-ture. The possibility of the formation of an iron-uranium eutectic alloy was addressed in Section 2.4.1 where it was concluded that the formation of the alloy uas not a likely eventuality.

3.5.4 Maximum Internal Pressures The Model 858 packaging is open to the atmosphere. Therefore, there will be no pressure buildup within the package. In Section 3.6, an analysis of the source capsules under the thermal test condition demonstrates that the maximum internal gas pressure at 800*C is 54 psi 2

(377kN/m ),

In Section 3.6.3, an analysis is presented which demonstrates that the maximum stress generated in the source capsule (containment) under the thermal test conditions could only be 3% of the yield

,_s

()

strength of the material at the test temperature.

3.5.5 Maximum Thermal Stresses There are no significant thermal stresse; generated during the thermal test.

3.5.6 Evaluation of Package Performance The Model 858 will undergo no loss of structural integrity or shiciding vt.cn subjected to the thermal accident condition. The pressures and temperatures have been demonstrated to be within acceptable limits.

REVISION O

}

29 Oct 1981

)

3-3

l

'O 1

3.6 APPENDIX i

4

{

3.6.1 Model 858 Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 Edition f

l 3.6.2 Model 858 Type B(U) Thermal Analysis: Paragraph 240 of IAEA Gafety Series No. 6, 1973 Edition i

l 3.6.3 Model 858 Type B(U) Source Capsule Thermal Analysis:

Paragraph 238 of IAEA Safety Series No. 6, 1973 Edition i

i k

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I REVISION O I

29 Oct 1981 i

)

3-4 i

j I

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/~'N 3.6.1 Model 858 Type B(U) Thermal Analysis V

Paragraphs 231 and 232 of IAEA Safety Series No. 6,1973 Edition This analysis demonstrates that the maximum surf ace temperature of the Model 858 will not exceed 50*C (122 F) with the package in the 0

shade and at an ambient temperature of 380'C (100'F).

To assure conservatism, the following assumptions are used:

a.

The entire decay heat (2.0 watts) is deposited in the exterior faces of the Model 858.

b.

The interior of the Model 858 is perfectly insulated and heat transfer occurs only from the exterior wall to the atmosphere.

Because each face of the package eclipses a different c.

solid angel, it is assumed that twenty-five percent of the total heat is deposited in the smallest f ace (f ront).

d.

The only heat transfer mechanism is f ree convection.

Using these assumptions, the maximum wall temperature is found f r om:

s/

q = hA(T

-T) w a

_k and h = 1.42 -T

-T w

a

_ L where q : Heat deposited per unit tice in the face of interest (0.50 watts) h:

Free convective heat transfer coefficient for air in watts /m2 o c A: Area of the face of interest (0.113m )

2 T: Maximum temperature of the wall of the package.

T: Ambient temperature (38 C) a L: Height of the face of interest (0.371m)

From this relationship, the maximum temperature of the wall is 40.0'C (104.1 F). This satisfies the requirement of paragraphs 8

231 and 232 of IAEA Safety Series No. 6,1973 Edition.

(' T

's_sl REVISION 0 29 Oct 1981 3-5

,m t

fT

\\_s/

3.6.2 Model 858 Type B(U) Thermal Ans. lysis Paragraph 240 of IAEA Safety Series No. 6, 1973 Edition This analysis demonstrates that the maximum surf ace temperatures of the Model 858 will not exceed 82'C (180'F) when the package is in an ambient temperature of 38'C (100'F) and insolated in accordance with paragraph 240 of IAEA Safety Series No. 6, 1973 Edition.

The calculational model consists of taking a steady state heat balance over the surface of the package. The following assumptions are used.

a.

The package is insolated at the rate of /75 w/m2 2

(800 cal /cm - 12h) on the top surface, 194 w/m2 2

(200 cal /cm - 12h) on the sides and no insolation on the bottom.

b.

The decay heat load is added to the insolation heat

load, c.

The solar absorptivity is assumed to be 0.9.

The solar emissivity is assumed to be 0.8.

(S d.

The package is assumed to undergo free convection from

\\_,)

the top and sides and undergo radiation from the top, sides and bottom. The inside f aces are considered insulated so there is no conduction into the package.

The f aces are considered to be suf ficiently thin that no temperature gradients exist.

The package is approximated as a rectangular solid c.

of 0.37m length, 0.37m high and 0.30m wide.

The maximum surface temperature is established from a steady state heat balance relationship.

aq; + qd # 9 "r

c where a : Absorptivity (0.9) q.: Solar Heat Load (182.2 watts) 1 q: Decay Heat Load (2.0 uatts) g L

q : Convective Heat Transfer q: Radiative Heat Transfer AU REVISION O 29 Oct 1981 3-6

1 i

l l

1 L

1 1

j The convective heat transfer is:

?

l i

,(hA) top + (bA)

(T

-T) q

=

sides _

c w

a

]

where h: Convective lleat Transfer coefficient A: Area of the surface of interest

[

)

T: Temperature of the wall j

T" Ambient Temperature a

i The heat transfer due to radiation is:

I

{

q = ocA (T " - T *)

r w

a 1

_8 2 0 4 where c: Stephan Boltzman Constant (5.67 x 10 w/m - K c: Emissivity (0.8) i

)

Iteration of this relationship demonstrates that the vall temperature

{

is 62.2"C which satisfies the requirement of paragraph 240 of IAEA Safety Series No. 6,1973 Edition.

1 j G 1

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REVISION O 29 Oct 1981 l

l i

1 3-7 I

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(s/)

3.6.3 Model q}C Source Caps.u_les - Theraal Analysis m

Paragraph 238 of IAEA Safety Series No. 6, 1973 Edition This analysis is intended to demonstrate that Tech / Ops source capsules which are of 0.25 inch (5.35mm) diameter, seal welded to a minimum penetration of 0.020 inch (0.51mm), made of Type 304 or 304L stainless steel, and licensed as special form containers under IAEA Safety Series No. 6, 1973, also meet the requirements of paragraph 238, IAEA Safety Series No. 6,1973, i.e., containment under specified thermal test cond it ions.

The actual cantainment vessel for the radioactive material is the velded source capsule. These capsules are all 0.25 inches (6.35mm) in diameter and less than 1 inch (25.4mm) in length.

The internal volume of the source capsules contains only cobalt-60 metal (as a solid) and cir. It is assumed at the time of loading that the entrapped air in the capsule is at standard temperature 8

and pressure (20 C, 0.101 Meganewtons per square meter). We contend that this is a conservative assumption because, during the welding process the internal air is heated, causing some of the air mass to escape before the capsule is scaled. When the welded capsule returns to ambient temperature, the internal pressure is somewhat reduced.

As described in Tech / Ops standard source encapsulation procedure, the

()

minimum weld penetration is 0.020 inch (0.51mm). Under conditions of interns 1 pressure, the critical location for failure is this weld.

Since the capsule has an outside diameter of 0.25 inch (6.35mm), this weld has a cross-sectional area of 0.014 square inches (9.30mm ),

2 Under conditions of paragraph 238 of I AEA Safety Series, No. 6, it is assumed that the capsule could reach a temperature of 1475'F (800 C).

8 Using the ideal gas law and requiring the air to occupy a constant volume:

P2 =PT2 I

Il 2

i Initial pressure (0.10lMN/m )

P

=

Ti = Initial tenperature (293 k) 8 T2 = Final temperature (1093 k) 8 The internal gas pressure could reach 0.377MN/m. It is assu=ed that 2

the capsule can be treated at a thin-walled, cylindrical pressure vessel.

REVISION O

' (}

29 Oct 1981 v

l 3-8 1

?

l l

l The maximum longitudinal tensile stress can be calculated by writing a longitudinal force balance through the weld:

I pressure x area

=0 stress x area s

p l

l S n (d

- d.2) - Prd.2 0

2 i

l 0

1 1

~

s u

l where S

= longitudinal stress i

+

I I

d

= outer diameter (6.35cm) l 0

d.

= inner diameter (5.35cm) l 1

i P

= pressure-(0.37710i/m )'

l 2

\\

2 l

Thus, the longitudinal stress is 0.9221ci/m The hoop stress can be found in a similar fashion. Taking a longitudinal cross-section and summing forces:

l I

hoop stress x area - pressure x area

=0 g

2 S lt - Pd.1 = 0 I

h 1

i i

where S = hoop stress 1 = length of cylinder t = thickness of weld (0.51=m) l 2

Thus, the hoop stress is 1.98tC4/m At a tecperature of 1600 F (870'C) the vield strength of type 304 0

D stainless steci is 10,000 psi (69.0ml/m ).

Thus, the pressure I

induced stresses are less than 3% of the yield strength at 800 C.

8 I

l i'

i REVISION O 29 Oct 1981 f

3-9

y

('~)

4.

Containment g

4.1 Containment Soundary 4.1.1 Containment Vessel The containment system for the Model 858 gamma ray projector is the Tech / Ops Model A424-14 source assembly. The source assembly is currently certitied as special form containment for radioactive materials (IAEA Certificate of Competent Authority Number USA /1065/S).

The actual containment vessel is the welded source capsule, either style 60004 or 60011. The capsules are made of Type 304 or 304L stainless steel.

They are seal welded with a minimum veld penetration of 0.020 in. (0.51an). The capsules are rounded cylinders 0.25 inches (6.4tm) in diameter and 0.96 inches (24mm) in length. Capsule style 60011 is a oouble encapsulation, the inner capsule located inside the capsule of the above dimensions. Appropriate design drawings are enclosed in section 1.10.

4.1.2 Containment Penetrations There are no penetrations of containment.

The source capsule is seal welded to provide conformity to special form requirements.

/N 4.1.3 Seals and Welds V

The containment vessel is tungsten inert gas welded by General Electric Co., Vallecitos, California. This is done in accordance with Tech / Ops standard saurce encapsulation procedure (see section 7.4).

l The minimum weld penetration is 0.020 inches (0.51=m).

This has proved acceptabic for approval of this vessel as special form.

4.1.4 Closure Not Applicabic 4.2 Require =ents for Normal Conditions of Transport 4.2.1 Release of Radioactive 15aterial The source assemblies used r et the seguirements of special form radioactive material as delineated in IAEA Safety Series No. 6,1973 and 10CFR71. Thus, there will be no release of radioactive materials under conditions of normal transport.

REVISION O 29 Oct 1931 4-1

/-m.

4.2.3 Coolant contamination Not applicable 4.2.4 Coolant Loss 4.3 Containment Requirements for the Hypothetical Accident Condition 4.3.1 Fission Gas Products 4.3.2 Release of Contents The hypothetical accident conditions as outlined in 10CFR71, Appendix B.

l.,

2., and 3. have been shown (Sectione 2.7.1, 2.7.2 and 3.5 respectively) to result in no loss of package containment.

s i

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ON O zy vet 1981

)

4-2 L

lV) 5.

Shiciding Evaluation 5.1 Discussion and Results The Model 858 is shielded with 327 pounds (149kg) of depicted uranium. The uranium metal is cast around the zircalloy or titanium "S" tube which holds the source. The storage position for the source is at the inflection in the "S" tube.

A radiation profile of Model 858 SN 1 containing 99Ci of Cobalt-60 (see section 5.5) was made. An extrapolation to a capacity of 110Ci yielded the results which are presented in Table 5.1.

From this data, it is concluded that the Model 858 complies with the regulatory standards in 10CFR71 and IAEA Safety Series No. 6, 1973.

TABLE 5.1

SUMMARY

OF MAX 1 MUM DOSE RATES (mR/hr)

Contact At 1 Meter Side Top Bottom Side Top Bottom O

Cam:na 156 122 133 1.8 1.1 1.1 Neutron Not applicable Not Applicabin Total 156 122 133 1.8 1.1 1.1 Hypothetical accident conditions will result in essentially no change in the above radiation intensities.

5.1 Source Specificatiog 5.2.1 Camma Source The gamma source used is encapsulated cobalt-60 in quantities of up to 110 curies.

5.2.2 Neutron Source Not Applicable 5.3 Model Specifications Not Applicabic s,/

REVISION O 29 Oct 1981 5-1

I I

i i! /~N IV i

l j

5.2.2 Neutron Source t

l Not Applicable

[

{

5.3 Model Specifications I

Not Applicabic l

5.4 Shielding Eva'uation I

The Model 858 shielding evaluation was performed on Model 85d Serial l

Number 1, containing 99Ci cf cobalt-60. The radiation profile is l

included in Section 5.5.

Extrapolation of this data to the capacity of 110 curies (Section 5.1) clearly indicates that the Model 858 conforum to regulatory radiation limits. As the hypothetical accident evaluation (Section 2.7) revealed no change in the shiciding arrange-l ment, it is concluded that shiciding af ter the hypothetical accident j

is essentially unchanged. Therefore, the radiation profile indicates the package will be within acceptable limits.

[

t

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8 i

4

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j REVISION O l

29 Oct 1981 i

i I(1:)

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+

i i

i f

i

O 5.5 APPENDIX i

l

- Model 858: Radiation Profile i

E i

i l

1 1

l 1

1 I.

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I f

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l 1

l REVISION O t

20 Oct 1981 j

l i

i 5-3 1

1, l

/

O RADIATION PROFILE Model 858 Scrial Number 1 Source Model Number A424-14 60 Serial Number 1939; 99 Curies Cobalt Location At Surface At 1 Meter From Surface Top 110 1.0 Right Side 130 1.2 Bottom 120 1.0 Left Side 100 1.0 Front 14 0 1.3 Back 130

1.6 NOTES

1.

All intensitics are expressed in units of n:illiroentgens per hour.

2.

Intensities expressed are the maximum intensities on the particular surface.

3.

Measurements were made with an AN/PDR - 27(J) Survey Meter.

REVISION O 29 Oct 1981 6

5-4

l.

i.

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v

}

Criticality Evaluation i

i Not Applicabic l

l 4

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I l

REVISION O 29 Oct 1981 6-1 9

I Y'-

--YY N*E WM-.

=YD r--

.mW--

.~.

f'G)'

7.

Operating Procedures 7.1 Procedures for Loading the Package Section 7.4 describes the procedure for fabricating the special form source encapsulation. Section 7.4 also contains the procedure for loading this source assembly into the package and preparing the package for transport.

7.2 Procedures for Unloading the Package Section 7.4 contains the procedure for unloading the source assembly from the package.

7.3 Preparation of an E=pty Package for Transport Section 7.4 describes the procedure for preparing an empty package for transport.

x (V

REVISION O 29 Oct 1981 f

a

\\v >

f 7-1

1 g

7.4 APPENDIX

- Encapsuletion of Scaled Sources

- Technical Operations Model 858: Procedures of Loading -

Unloading the Package i

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REVISION O

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29 Oct 1981 7-2 i

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[

RADIATION SAFETY MANUAL

\\

Part II In Plant Operations Section 2 ENCAPSULATION OF SEALED SOURCES A.

Personnel Requirements only an individual qualified as a Senior Radiological Technician shall is2 perform the operations associated with the encapsulation of Iridium.

There must be a second qualified radiological technician available in the building when these operations are being performed.

B.

General Requironients 192 The Iridium loading cell shall be used for the encapsulation of solid metallic 182Iridium and the packaging of scaled sources such 378 137 as

Thulium, Cesium and I6' Ytterbium. Solid metallic '0 Cobalt not exceeding one curie may be handled in this cell also.

The maximum amount of 3'2 Iridium to be handled in this cell at any one time shall not exceed 1000 curies. The maximum amount of 137 Cs to be handled in this cell at any one time shall not exceed 100 curies.

This cell is designed to be operated at less than atmospheric pressure.

The exhaust blower provided shall not be turned off except when the cell is in a decontaminated condition.

Sources shall not be stored in this cell overnight or when cell is un-attended. Unencapsulated material shall be returned to the transfer containers and encapsulated sources transferred to approved source containers.

When any of the "through-the-wall" tools such as the welding fixture or transfer pigs are removed, the openings are to be closed with the plugs provided. These tools shall be decontaminated whenever they are removed from the hot cell.

C.

Preparatory Procedure 1.

Check welding fixture, capsule drawer and manipulator fingers f rom cell and survey for contamination. If contamination in excess of 0.001pCi of removable contamination is found, these items must be decontaminated.

[

REVISION O

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29 Oct 1981 7-3

[

x e

i

\\_ /

2.

If the welding fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this dummy capsule by sectioning thru weld. Weld penetration must be not less than 0.020 inch.

If weld is sound and penetration is at least 0.020 inch, the preparation of active capsules may proceed. If not, the condition responsible for an unacceptabic weld must be corrected and the preparatory procedure repeated.

3.

Check pressure differential across first absolute filter, as measured by the manometer on the 1cf t side of the hot cell. This

~

is about % inch of water for a new filter. When this pressure differential rises to about 2 inches of water, the filter must be changed.

D.

Encapsulation Procedure 1.

Prior to use, assemble and visually inspect the two capsule components to determine If weld zone exhibits any misalignment and/or separation. Defective capsules shall be rejected.

2.

Degrease capsule components in the Ultrasonic Bath, using isopropyl alcohol as degreasing agent, for a period of 10 minutes. Dry the capsule components at 100'C for a minimum c~s

(

)

of twenty minutes.

3.

Insert capsule components into hot cell with the posting bar.

4.

Place capsule in weld positioning device.

5.

Move drawer of source transfer container into hot cell.

6.

Place proper amount of activity in capsule. Disposable funnel must be used with pellets and a brass rivet with wafers to prevent contamination of weld zone.

7.

Remove unused radioactive material from the hot cell by withdrawing the drawer of the source transfer container from the cell.

8.

Remove funne) or rivet.

9.

Assembic capsule components.

10.

Weld adhering to the following conditions:

REVISION O 29 Oct 1981 q

(.

7-4 i

m

a.

Electrode spacing.021" to.024" centered on joint 1.002"; use jig for this purpose.

b.

Preflow argon, flush 10 seconds.

c.

Start 15 amps.

d.

Weld 15 amps.

c.

Slope 15-amps.

f.

Post flow 15 seconds 11.

Visually inspect the weld. An acceptable weld must be continuous without cratering, cracks or evidence of. blow out.

If the weld is defective, the capsule must be cleaned and rewelded to acceptable conditions or disposed of as radioactive waste.

12.

Check the capsule in height gauge to be sure that the veld is at the center of the capsule.

13.

Wipe exterior of capsule with flannel patch wetted with EDTA solution or equivalent.

O Count the patch with the scaler counting system. Patch must 14.

show no more than.005pCi of contamination.

If the patch shows more than.005 Ci, the capsule must be cleaned and rewiped. If the rewipe patch still shows more than 0.005pci of contamination, steps 8 through 11 must be repeated.

15.

Vacuum bubble test the capsule. Place the welded capsule in a glass vial containing isopropyl alcohol. Apply a vacuum of 15 in Hg (gauge). Any visual detection of bubbles will indicate a leaking source. If the source is determined to be leaking, place the source in a dry vacuum vial and boil off the residual alcohol.

Roweld the capsule.

16.

Transfer the capsule to the swaging fixture. Insert the wire and connector assembly and swage. Hydraulic pressure should not be less than 1250 nor more than 1500 pounds.

17.

Apply the tensile test to assembly between the capsule and connector by applying proof load of 75 lbs. Extension under the load shall not exceed 0.1 inch. If the extension exceeds 0.1 inch, the source must be disposed of as radioactive waste.

REVISION O 29 Oct 1981 7-5

1-

,w

(

/T 16.

Position the source in the exit port of hot cell Withdraw

~'

(

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all personnel to the control area. Use remote control to insert source in the ion chamber and position the source for et maximum response. Record the meter reading. Com?ute the activity in curies and fill out a temporary source tag.

19.

Using remote control, eject the source from cell i?.to source changer through the tube gauze wipe test fixture. 1:onitor before reentering the hot cell area to be sure that the source is in the source changer. Remove the tube gauze and count with scaler counting system. This assay must show no more than 0.005pCi.

If contamination is in excess of this level, the source is leaking and shall be rejected.

l.

20.

Complete a source loading log (Figure 11.2.1) for the operation.

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s REVISI3k0

/r 29 Oct 1981 i

OO 7-SA

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4

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4 r,

(

Technical Operations G

)'

\\

\\

Model 858,

i

/

Procedures for Loading - Unloading the Package s

Wear personnel monitoring devices during all source changing procedures.

%)

Honitor 2.11 operations with a calibra'ted, operable survey meter.

1 o

Note: 5.\\11 the precautions uced when making radiographic exposures i muet be followed.

\\'

i 1.

Survey the projecter to ciu.ure that the source is in the proper

\\

s positdon.

'L w

.5 p

k

2..Jocate thfi projector and souitcc changer in a restricted area.

Locate the d2 vices so as to avoid shbrp bonds in the guide tube

't

'or control housing.

',c igW

'Y, s

s

'j, The, control cabic housing bend radius should not be less than 36 inches (0.914m), and the guide tube bend radius should not be less

,I N

than 20 inches (0.508m).

', (

.,c 3.

Set the source changer for operation.

~3

. "

• f, 4.

Attach.cne end of a guide tube fitti.tg to the fitting above the

[

empty ' han.bar in the source changer and the other end to the source c

)g changing fix;ure attached to the projector.

(

_s 5.

Attach the Montrol ecble to the projector.

.i N i

1 g Unlock the projectors with the key provided and turn the connec-tor s2)hetor ring fran the LOCK position to the CONNECT position.

i s

when thb rihg is in the CONNECT position, the storage cover will y

disengage f"com the projector.

b.

Slide the control cable collar back and open the jaws of the

' Awivel connector, exposing the male portion of the connector, Engage the male and female portions of the swivel cunnector w

i by depressing the spring loaded locking pin toward the projector with the tnumbnail. Release the locking pin and test that the lhonnectionhasbeenmade.

I

~t Close the jaws of the control cable connector over the swivel l ' -l c.

g type connector.

i l

d.

Slide the control cable collar over the connnector jaws. Hold i-the control cable collar flush against the projector connector and rotate the selector ring from the CONNECT position to the i

OPERATE position.

lO iV REVISION O 29 Oct 1981 7-6 t_

t

,d-/

6.

Crank the source into source changer.

a.

Survey this operation with a survey meter to be sure the source has been transferred from projector to changer.

b.

With a survey meter verify radiation level does not exceed 200 mR/hr at the surfacc of the changer.

7.

Disconnect the control cable from the source assembly. Disconnect the guide tube from the source changer. Secure the cource in the source changer.

d.

IF THE PROJECTOR IS TO REMAIN EMPTY:

a.

Fully retract the control cable. Disengage the control cable from the projector and lock the projector.

b.

Attach the identification plate of the source to the source changer.

c.

Affix a green " empty" tag to projector.

d.

Perform a wipe test of the projector to assure that the contamination level observed is less than 0.001 microcuries per f 'S 100 square centimeters.

\\

%,/

Survey the projector to determine thc proper RADI0 ACTIVE shipping e.

labels to be applied.

f.

Mark the projector: Radioactive "LSA".

Affix the proper shipping labels to the package.

g.

Comp?.:,te the proper shipping papers.

9.

IF THE PROJECTOR IS TO BE RELOADED:

Connect the soarce changer end of the guide tube to the fitting above the new source in the source changer. Connect the drive cable to the new source assembly.

10.

Crank source to full retraction within the projector, a.

Survey this operation with a survey meter to be sure the source has been transferred into the projector.

b.

With a survey meter verif y radiation icyc1 does not exceed 200mR/hr at the surface of the projector.

11.

Disconnect the control cabic and lock the projector.

O r

i REVISION O 29 Oct 1981 7-7

q 7_.s

(

)

12.

Disconnect the source guide tube from the projector and source changer.

13. Affix the identification plate of the new source to the projector and attach the identification plate of the old source to the sourco changer.

14.

Prepare for shipment.

a.

Again survey projector to insure that the radiation level does not exceed 200mR/hr at the surface of the projector.

b.

Survey the radiation Icvel at a distance of three feet from the surface of the projector. This radiation level should not exceed 10mR/hr. The highest radiation level measured at three feet from the container is used to determine the Transport Index in accordance with 49CFR173.389'h).

/^T Y)

REVISION O 29 Oct 1981 v) 7-8

_q

()

Tech [0,gsModel858 Procedure for Shipping Radicactive Material The Model 858 meets the requirements for a Type B shipping container under the regulations of the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and the International Atomic Energy Agency. The container has been assigned USNRC Certificate of Compliance No.

for domestic shipments and IAEA Certificate No. USA /

/B(U)T for international shipments.

The following shipping procedures comply with NRC Regulations 10CFR Part 71 and DOT Regulations 49CFR Parts 171 through 179 regarding the transportation of radioactive materials.

1) Ensere that the source is locked into place in its storage position. To check this, the lock should be in the down position, and the selector ring should be immobile. Secure the cover plate to the container, and seal wire the hex head bolts to provide a tamper proof seal.

2) Perf orm a radioactive contamination wipe test of the outer shipping package. This consists of rubbing filter paper or other absorbent material, using heavy finger pressure, 2

2 over an area of 100cm (16in ) of the package surface. The activity on the filter paper should not exceed 0.001pCi of removable contamination.

O--

N-

3) Survey the package with a survey meter at the surface and at a distance of three feet from the surface to determine the proper radioactive shipping labels to be applied to the package as required by 49CFR Part 172.403. The radistica exposure limits for each shipping label are given in Figure 1, If radiation levels above 200mR/hr at the surf ve or 10mR/hr at three feet from the surface are measured, the container must not be shipped.

4) Properly complete two shipping labels indicating the radioactive isotope, activity and the transport index. The transport index is used only on Yellow II and Yellow III labels and is defined as the maximum radiation icvel in milliroentgens per hour measured at a distance of three feet from the surface of the package. Put these two labels on opposite sides of the container after making sure any previous labels have been removed. The package should be marked wit'a the proper shipping name (Radioactive Material, Special Form, n.o.s.).

If the exposure device is packaged inside an outer container, mark the outside package "INSIDE PACKAGE COMPLIES WITH PRESCRIBED SPECIFICATIONS - TYPE B USA /

/B(U)."

REVISION O

[~')

29 Oct 1981 1

7-9

5.

Complete the shipping papers indicating:

b'

\\-

Proper shipping name (Radioactive Material, Special Form,

~

a.

n.o.s.) and identification number (NA9182).

b.

Name of radionuclide ( Cobalt) c.

Physical or cheuical form (special form) d.

Activity of Source (expressed in curies or millicuries) c.

Category of label applied (i.e., Radioactive Yellow III) f.

Transport Index g.

USNRC Identification Number of DOT Specification Number (USNRC: USA /

/B) h.

For export shipments, IAEA Identification Number

(

IAEA: USA /

/B) i.

Shipper'3 Certification:

"This is to certify that the above named materials rs are prope:1y classified, described, packaged,

(,,)

marked and labeled and are in proper condition tor transport according to the applicsbic regula-tions of the Department or Transportation."

Notes:

1.

For air shipments, the following shipper's certification may be used:

"I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled and are in proper condition for carriage by air according to applicable national gavernmental regulations."

2.

For air shipments, the package must be labeled with a " CARGO AIRCRAFT ONLY" label and the l

shipping papers must state:

l "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARGO-ONLY AIRCRAFT."

(m,)

REVISION O i

29 Oct 1981 7 - 10 i

~

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(

I N/

Shipment of Empty Container (1) Ensure that the source is removed, and the connector assembly is in the LOCK position with the lock plunger in the down position and the key removed. Secure the cover to the outer container with the hex head bolts, and secure the bolts with seal wire.

(2) Mark the outside of the outer shipping package: "RADI0 ACTIVE - MATERIAL -

LSA, n.o.s."

(3)

Perform a radioactive contaminatien wipe tast of the shipping package and ensure that the wipe test does not exceed 0.001 microcuries per 100 square contimeters.

(4 ) Survey the package at the surface and at three feet from the surface to determine the proper radioactive snipping labels to be applied to the package.

a.

If the surface radiation level is less thaa 0.5 milliroentgens per hour and there is no measurable radiatioa level at three feet from the surface, no label is required. Mark the outside of the package with the statement: " Exempt from specification packaging, marking and labeling, and exempt from the provisions of 49CFR173.393 per 49CFR173.391(c). Exempt from the requirements of 49CFR Part 175 per 49CFR175.10(a)(6)."

-~

V Properly complete the shipping papers:

( 1)

Proper shipping name (Radioactive Device n.o.s.) and identification number (UN 2919)

(2)

Name of radionuclide (Depleted Uranium)

(3)

Physical or Chemical Form (Solid Metal)

(4)

Activity (in curies or milliauries)

(5)

The statement " Exempt from specification packaging, marking and labeling, and exempt from the provisions of 49CFR173.393 per 49CFR173.391(c). Exempt from the requirements of 49CFP.

Part 175 per 49CFR175.10(a)(6)."

(6)

Shipper's Certification:

"This is to certify that the abvve named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transport according to the applicable regulations of the Departmen; of Transportation."

m

('~')

REVISION 0 29 Oct 1981 7 - 11

n

/"'s Notes:

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(1) For Air Shipments, the fc11owing shipper's certificction may be used:

"I hereby certify that the contents of this consign-ment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled a.d are in proper condition for carriage by air according to applicable national governmental regulations."

(2) For Air Shipments, the following statement must appear:

"This shipment is within the limitations prescribed for passenger aircraft in accordance with 49CFR175.10(a)(6)."

b.

If the surface radiation level exceeds 0.5 millircontgens per hour, or if there is a measurable radiation Icvel at three feet from the surface, use the criteria of Table 7.4.2 to determine the proper radioactive shipping labels to be applied to the package.

Complete the shipping papers indicating:

7-g (1) Proper Shipping Name (Radioactive Material, LSA, n.o.s.) and

(,)

identification number (UN2912).

(2) Name of radionuclide (Depleted Uranium)

(3) Physical or Chemical Form (Solid Metal)

(4) Activity (In curies or millicuries)

(5) Category of label applied (i.e., Radioactive Yellow II).

(6) Transport Index (7) USNRC Identification Number (USNRC USA /

/B)

(8) For Export Shipments, IAEA Identification Number

(

IAEA USA /

/B)

(9) Shipper's Certification:

"This is to certify that the above named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transport accord-ing to the applicable regulations of the Department of Transportation."

N,]

REVISION O 29 Oct 1981 7 12

~.

9 Notes:

(1)

For Air Shipments, the following shipper's certification :tay be used:

"I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled and are in proper condition f or carriage by air according to applic-able national governmental regulations."

(2)

For Air Shipments, the package must be labeled with a " CARGO AIRCRAFT 0:!LY: label and the shipping papers must state:

"THIS SHIP!ENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARGO-ONLY AIRCRAFT."

O h

REVISION O 29 Oct 1981 7 - 13

p}

S.

Acceptance Tests and Maintenance Program 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are wired properly and that the package is properly marked.

The seal veld of the radioactive source capsule is visually inspected for proper closure.

8.1.2 Structural and Pressure Tests The swage coupling between the source capsule and cable is subjected to a static tensile test with a load of seventy-five pounds. Failure of this test will prevent the source assembly from being used.

8.1.3 Leak Tests The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination. The source capsule is subjected to a vacuum bubble leak test. The capsule is then subjected to a second wipe test for leakage of radioactive contamination.

These tests are described in Secticn 7.4.

Failure of t.ny of these tests will prevent use of this source assembly.

s/

8.1.4 Component Tests The lock assembly of the package is tested to assure that security of the source will be maintained. Failure of this test will prevent use of the package until the lock assembly is corrected and retested.

8.1.5 Tests for Shielding Integrity The radiation levels at the surface of the package and at three feet from the surf ace are measured using a small detector survey instrument (e.g., AN/PDR-27). These radiation levels, wnen extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface, nor ten milliroentgens per hour at three feet from the surface of the package. Failure of this test will prevent use of the package.

8.1.6 Thermal Acceptance Tests Not Applicable REVISION O 29 Oct 1981 r~s -

8-1

.r-g,-

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l

!l

}

4 5

13 V

j 8.2 Maintenance Program j

8.2.1 Structural and Pressure Tests l

l Not Applicable i

8.2.2 Leak Tests As described in Section 8.1.3, the radioactive source assembly is lesk I

tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months.

8.2.3 Subsystem Maintenance 4

i l

The lock assembly is tested as described in Section 8.1.4, prior to f

each use of the package. Additionally, the package is inspected for l

tightness of f asteners, proper seal wires and general condition prior to each use.

8.2.4 Valves, Rupture Discs, and Gaskets Not Applicable 8.2.5 Shielding f 1 Prior to each use, a radiation survey of the package is made to assure that

- t the radiation levels do not exceed 200 milliroentgens per hour at the surface, nor ten milliroentgens per hour at three feet from the surface.

8.2.3 Thermal I

Not Applicable 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this package under the general license privisions of 10CFR71.12(b) are included in Section 7.4.

REVISION O O) 29 Oct 1981 8-2