ML20235U701

Nonproprietary Rev 0 to Consolidated PAS-2 SAR Authorizing Shipment of Radioactive Matl

ML20235U701
Person / Time
Site:	07109181
Issue date:	02/28/1989
From:	NUCLEAR PACKAGING, INC.
To:
Shared Package
ML20235U696	List: ML20235U693 ML20235U701
References
NUDOCS 8903090340
Download: ML20235U701 (126)

Text

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N: Pao PAS-2 System Consolidated SAR Rev. O, February 28, 1989 t

NON-PROPRIETARY CONSOLIDATED SAFE'IT ANALYSIS REPORT NRC CERTIFICATE OF COMPLIANCE 4

AUTHORIZING SHIPMENT OF RADI0 ACTIVE MATERIAL IN THE NUPAC PAS-2 PACKAGING g.

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Februa ry 1989 a.

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Prepared by:

Nuclear Packaging, Inc.

1010 South 336th Street Federal Way, WA 98003 I

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1 NnPas PAS-2 Syst em Consolidat ed SAR Rev. O, Februsry 28, 1989 l

TABLE OF CONTENTS I

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M 1.0 GENERAL INFORMATION 1-1 1.1 Introduction.

1-1 1.2 Package Des cription 1-1 1.2.1 Pac ke gin g 1-1 1.2.2 Operational Fea tures 1-5 1.2.3 Contents of Packaging 1-8 1.3 Appendiz - NuPac PAS-2 General Arrangement Drawings 1-10 2.0 STRUCTURAL EVALUATION 2-1 2.1 St ructucal Design 2-1 (mh i

2.1.1 Discussion 2-1 s-i 2.1.2 Design Criteris 2-1 1

2.2 Weight s and Center of Gravity 2-2 2.3 Mechanical Proper ties of Materials 2-2 2.4 General St andards f or.A' 1 Fackage s 2-3 1

2.4.1 Minimum Package Size 2-4 2.4.2 Tamper-indica ting Feature 2-4 2.4.3 Positive Closure

?.-4 2.4,4 Chemical and Galvanic Reactions 2-4 4

L 2.5 Lif ting and Tiedown Sevices for alJ Packages 2-6 i

2.5.1 Lifting Devices 2-5 2.5.2 Tiedowns 2-10 f

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2.6 - Nocaal. Conditions of Transport 2-10 1

2i6.1-Heat.

'2-10 2.6.2 Cold 2-11

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2.6.3 '. Reduced Ext ernal ~ Pres sure'.

2-16. ~

2.6.4 Incre ased Exte rnal' Pres sure '

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2. 6.,5 Vibration 2-18 2.6.6 Water. Spray 2-18' 2.6.7 Pree Drop 2-38 2.6,4. : Co rne r Dro p 2-19 2.6.9 Ccapression 2-19 246.10 Penetration 2-19' 2.6.11 Conclu si on 2 <

3 2.7-Hypo ther t i ca Ace 4Ers t. Cs udi t ion s 2-20 nj

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2.7.1

$ce Drop Event.

2-21 2a7.2 IN rcure 2 2 7.1 The rmal Analy:.s 2-27 2.7.4 Imme raion - Fix s Ale ' t eri al 2-27 2.7.5 Imr$,sica

.*'t Paerigos 2-27 2.7.6 Sa ima?y of Darage 2-29 2.8 Speci al Fcem 2-29 2.9 Fuel Rods 2-29 2.10 Appe ndi x 2-30 2.10.1 Moved to St' tion 1.3 2-30 2.10.2 Incorporated into Section 1.3 2-31 L-2.10.3 Drop Test Result s 2-32 2.10.4 Manuf acturer's Data Sheets 2-38 i-2 I

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l NnPas PAS-2 Sys t em Con s olid a t ed S AR Rev. O, Februa ry 28, 1989 j

,r~'s TABLE OF CONTENTS I'

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3.0 ITERMAL EVALUATION 3-1 3.1 Discussion 3-1 3.2 Summary of Ibermal Properties of Materials 3-3 3.3 Technical Specifications of Components 3-4 3.4 Thermal Evaluation f or Normal Conditions of Transport 3-5 3.4.1 Thermal Model 3-6 3.4.2 Maximum Tempera tures 3-14 3.4.3 Minimum Temperatures 3-17 3.4.4 11azimum Int ernal Pres sures 3-18 3.4.5 Thermal Stresses 3-18 3.4.6 Evalua tion of Package Perf ormance f or Normal 3-18 Conditions of Transport (D

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3.5 Hypothetical Accident Thermal Evaluation 3-18 3.5.1 Thermal !!odel 3-19 3.5.2 Package Conditions and Environment 3-19 3.5.3 Package tempera ture s 3-25 3.5.4 Maxi mum Internal Pres sures 3-25 l

3.5.5 Maximum Thermal Stres ses 3-25 3.5.6 Evaluation of Package Perf ormance for Hypothetical 3-29 Ac ci den t Thermal Conditions 4.0 CONTAINMENT 4-1 1

4.1 Cont a i nmen t Boundar i e s 4-1 l

4.1.1 Containment Vessels 4-1 4.1.2 Con t a i nmen t Pene t ra t ion s 4-1

,f'~^g 4.1.3 Se al s and Welds 4-2 l

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4.1.4 Clo s ur e 4-2 1

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NnP;s PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989

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4.2 Requirement s for Normal Conditions of Tr ansport 4-2 4.2.1 Release of Radioactive Material 4-2 4.2.2 Press uriza tion of Containment Vessel 4-2 4.2.3 Containment Criterion 4-3 4.3 Con t ainme n t Requirement s f or the Hypo the tical Accident 4-3 Conditions 4.3.1 Fission Gas Products 4-4 4.3.2 Rele ase of Content s 4-5 4.3.3 Containment Crit erion 4-5 l

5.0 SHIELDING 5-1 g^s

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6.0 CRITICALITY EVALUATION

6-1 7.0 OPERATING PROCEDURE 7-1 7.1 Operational Requirement s (unles s otherwise noted) 7-1 7.2 Opera tional Narra tive 7-4 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8-1 8.1 Ac cept ance Test s 8-1 8.2 Maintenance Program 8-1 8.3 Appendiz - Discus sion of Gamma Scan Procedure 8-5 9.0 QUALITY ASSURANCE 9-1 l

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NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 CONSOLIDATED SAFETY ANALYSIS REFORT

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NRC CERTIFICATE OF COMPLIANCE ~

s AUTHORIZING SHIPMENT OF RADI0 ACTIVE MATERIAL IN THE NUPAC PAS-2 PACEAGING 1.0 GENERAL INFORMATION 1.1 Introduction The NuPac PAS-2 packaging has been developed by Nuclear Packaging, Inc. as a saf e means of transporting Type B quantities of radioactive liquids from commercial reactor cool ant systems to chemical analysis facilities off-site.

These liquid co olant samples would be taken subsequent to a reactor accident, and would be used to help determine the condition of the reactor core.

Thus, the chemical and isotopic breakdown of the samples would be somewhat varied.

Authorization is sought for shipment by cargo vessel, motor vehicle, rail, and p

cargo aircraf t.

1.2 Packare Description 1.2.1 Packarine 1.2.1.1 General Description The NuPac PAS-2 packaging consist s of a shielded sample cask designed to interface with a post ac ciden t sampling system (PAS S), an optional s e co nda ry containment vessel t o provide redundant cont ainment, and inner and out er overpack systems s ur rounding the sample cask to provide insulating and shock i

absorbing capabilities.

The inner overpack consists of a foam-lined standard 1

1 17H 55 gallon drum. The overpac k sys t em is de signed t o protec t the sample cask f rom the ef f ect s of normal transport and hypothetical accident condi-tions.

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NcPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 m

1.2.1.2

!!at eri al s d Cons truc tion. Dimensions-And. Fabricating s

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Methodi I

General Arrangement Drawings of the NuPac PAS-2 packaging sys tem are included in Ap pe ndix 1.3.

They show overall dimensions of the out er overpack, the f oam-lined 55 gallon drum inner ov erpack, the sample shield and the sample vial.

The outer overpack is f abricated of ductile low carbon galvanized steel in the out e r sh el l, and high impact f ibe rgl as s in the inner sh el l.

The volume be-tween the inner and outer shells of the outer overpack is filled with thermal and shock insulating material con sis t ing of rigid polyurethane foam having a density of approximately three pounds per cubic foot.

The out er overpack has a 32 inch diameter and is 48 inches in height.

l The insul ating ma terial is poured into the cavity be tween the two shells and allowed t o expand, comple t ely f il ling the void.

Here it bonds to the shells creating a unitized construction for the packaging.

Mechanical pro pe r tie s of I

b these mst erials are further described in Section 2.0, below.

The inner overpack consists of a standard 55 gallen drum (DOT 17H) lined with dense (ten pounds per cubic foot) rigid polyurethane foam cut to f i t' be tween either the optional secondary containment or the sample shield vessel and the inside of the 55 gallon drum.

The optional secondary cont ainment vessel provides a redundant l ev el of con-t ainmen t for the NuPac PAS-2 package.

It is f abricated from ASTM 516 grade 70 steel or ASTM 240 304 s tainl es s, which have excellent low t emperature proper-ties. The vessel consists of a rolled 3/8 in. plate body with a 3/8 in plate welded across the bottome and closed with a close fitting 0-ring seal between the body and the lid.

The lid is provided with a test port for use in testing l

the seal integrity of the secondary containment vessel.

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1 NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 l

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The sample shiel d con sis t s of s t e el inne r and out e r shell s with the cavity between the shells filled with lead. The cask closure is ef fected by a lead-

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fill ed s t e el pl ug.

This clos ur e is se aled by a double 0-ring seal on the bot t om of the plug or an optional seal pl a te.

There are f our penetrations through the cask walls; an inlet and outlet port f or int erf acing with the PASS and valve actuator pe netrations t o allow the use r t o ope rat e the inlet and 3

outlet valves from out side the radiation shield.

All radioactive material is contained within a short section of tubing between the inlet and outlet v al v e s.

Thi s tubing, toge ther with the val ve plugs on each end, is the sample vial, f orming the ;,rimary containment boundary of the NuPac PAS-2 package.

Th e c av i ty of th e s ampl e sh i e l d, which is packed with a mixture of lead shot and v ermiculi t e t o provide addit ional shielding and absorb any leakage occuring f rom f ailure of the sample vial, forms a second level of containment. The vial holds approximately 50 milliliters of coolant.

p 1.2.1.3 h tninment Vessel N._Y The NuPac PAS-2 packaging is designed to provide two levels of containment for it s int ended payload.

Th e sample vial acts as th e prima ry cont ainmen t bou nd-ary and the inner cavity of the s ampl e shield f orm a second l eak-tight con-t ainmen t bounda ry.

Op t ional l y, thi s inner cavity se r v e s as a pressure tight confinement boundary and an optional s e cond ary containment ves sel outside the sample shield provides a Icak-tight con t al men t bou nda ry.

IIigh quality double 0-ring bore seals are provided around the valve ope ra t ors and vial plugs to se al of f these penet ra tions, and a double 0-ring f ace se al provides closure at the shield plug in the t op of the s ampl e shield. A test port is provided through the upper vi al plug t o f acilit at e t es ting the shield cav ity.

The optional secondary cont ainment ves sel is also fit t ed with a t es t port designed t o verify it s l e ak-t i ght n es s.

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NuPac PAS-2:Systsm Consolidated SAR Rev.

O', Februa ry 28, 1989' Mc 1.2.1.4

' Neutron Absorbers 6 )(

q There are no sources of-neutron ommissions and' theref ore, there are no ma-7 terials used as neutron absorbers or moderators in the NuPac PAS-2 packaging.

1.2.1.5 'Packane Weight Gross weight of ~ the package-i s approxima tely 2400 pounds, if the optional recondary containment ves sel-is used, or 2100 pounds if - the package is rot so equipped.

L 1.2.1.6 Receptacles There are no recept acles on the out side of the NuPac PAS-2 packaging.. Test port recept acl es are located in the lid of the optional se conda ry - cont ainment vessel as well as in the lower valve port plug. The sample shield containment boundary is pene trated by the two valve port plugs, the two valve operators, f

and the shield plug in the top of the shield. The sample vial has two re-ceptacles, which are plugged in transit with naval brass plugs extending through the side of the sample shield.

1.2.1.7 Tiedowns Tiedowns are not a structural part of the package. The outer overpack lif ting.

lugs are not required f or tiedown and theref ore are covered at all times. 'The

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package is secured to a dedicated use pallet by means of a frame placed over but not attached to the NuPac PAS-2 package assembly.

1.2.1.8 Liftine Devsces Lif ting devices are present in various parts of the NuPac PAS-2 packaging.

The outer overpack is equipped with f our lif ting lugs which have been quali-

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l' find f or lif ting the inner and outer overpacks, and the optional secondary containment. Since these lugs are not to be used to lif t the weight of the sample shield, they will be covered during use by two fender washers held to-ge ther by a small bolt.

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i NuPac PAS-2 Sys tem Consolidated SAR Rev. O, Februa ry 28, 1989 n

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The optional seconda ry containment vessel is equipped with a lifting bail on it s lid f or handling the lid only. Finally, the sample shield closure plug is

' fit t ed with a second lifting ball, used to lift both the plug and the loaded shield through the plug closure bolts.

Ref e r t o Se ction 2.5.1 f or a de tailed structural analysis of this device.

1.2.1.9 Pressure Relief System There are no pressure relief valves in the NuPac PAS-2 packaging.

1.2.1.10 Heat Dissipation The NuPac PAS-2 package will safely transport 3 watt s of internal heat.

j 1.2.1.11 Coolants

,o The NuPac PAS-2 pactaging does not invol ve the use of cool ant s.

1.2.1.12 Protrusions There are no outer or inner protrusions on the NuPac PAS-2 packaging.

1.2.1.13 Shieldine Shielding on the NuPac PAS-2 cask is provided by the 6 in. thick lead-filled sample shield, as well as lead sho t and specially fitted lead pieces inside the sampl e shield.

1.2.2 Operational Features The NuPa c PAS-2 packa ging inv ol v es nume rou s f e a tur es impor t ant t o th e s af e opera t ion and transport of radioactive material.

Figure 1.2.2 shows a schem-atic drawing of the system showing all containment systems, se al s and contain-me n t pe ne t ra t io n s in the packaging system. Note that the shield is penetrated p) s\\_s in four places:

twice for the valve operators and twice for the sample vial l

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NuPac PAS-2 System Consolidated SAR' Rev. O, Februa ry 28, 1989 port plugs.

Close-toleranced bore se al s are used in each of these pene t r a-

'Nd tions to retain any spillage from the sample vial safely within the shield.

1 The optional secondary cont ainment vessel envelopes the shield and also pre-v e nt s r el e as e of the paylo ad t o the e nv ironme nt.

The ves sel lid is sealed with a bore-seal 0-ring.

This lid is equipped with a t es t port such that both the lid bore seal as well as the t es t port seal may be t es ted bef ore the package is allowed to be sh ip ped.

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NuPac PAS-2 System Consolidated SAR Rev. O, February ' 28,1989

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-V TEST PORT-OUTER OVERPACK I,NNER OVERPACK

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.NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry - 28, 1989:

t Surrounding the sample shield' and optional secondaryc containment are' two foam-D<

filled shells which are designed to ' mitigate the effects of the hypothetical ac cident ' event s.

The inner 'shell is simply a standard DOT 17H 55 gallon drum with spe cial'1y. cut' f oam be tween the drum and the sample shield or optional.-

' secondary cont ainment.v es s el.

The outer shell is a f o am-f il l ed steel and

, fiberglass structure.

1.2.3. Cont ent s d Packa nin n -

The NuPac PAS-2'syst em is designed.t o transport: a 50 cc sample of react or

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cool ant t aken f rom the pos t accident s ampling sys tem.

Maximum activity of this. sampl e is es t,4ma t ed t o be 5 c urie s /c c or 25 0 curie s t ot al.

Relative concentrations of isotopes'present a r e gi v e n in Tab l e 1.2.3-1.

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ALL WELDNG PROCEDURES AND PERSONNEL SHALL BE OUALFED N ACCORDANCE WstW:

i ASME CDDE, SECTIOM IK.

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2.

ALL WELDS SHALL BE VISUALLY NSPECTED PER AWS D1.1, PARA S.16.1 ADO ANS8 8 31.1. j SECTON 138.4.2.-

%EAD. PER FEDERAL SPECFCATON OO-L-171e, GR A OR C.

h' (FNS>t PANT ALL EXPOSED. UNPANTED CARBON ST

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3-5 MLS OFT) HIGH QUAUTY EPOXY PfuMER & ONE COAT (3-6 MLS DFT) More OUALify ~

EPOXY PANT. APPLY N ACCORDANCE WrTH MA14JFACTURERS MSTRUCTIONS. EXCEPT'0IS SHALL 9E: ALL O RNQ OLANDS & ADJACENT SEALNG SURFACES: SAMPLE SHE.LD CA"fTY -

AND OUTER OVERPAir SHELL (GALVANIZED STEELL COAT O-RNG OL ANDS & ADJACENT' SURFACES WITH HOH OUALITY VACUUM GRE ASE PRIOR TO FNAL ASSEMSLY.

% CAVITY VOID SHALL BE FLLED WITH A BLEND OF LE AD SHOT (NO. $-8) & VERM ABSORBFhiT. (FNE ENOUGH TO PAS $ THRU A 12 STRAND / WCH WIRE MESA.tt VERialc1HE SHALL BE OF SUFFICENT QUANTITY TO ASSOMS A MINIMUM OF 100 C.C. OF L(AfD..

(APPROX 350-376eo).

'6 TORQUE SPECFCATIONS:

A) SAMPLE SHIELD CLOSURE 80LTS.1/fdSUNC-2A:16 FT/LDS.

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8) HOf5T RNG CAP SCREWS. 3/8-18UNC 2 A: SOFT /LBS.

C) SECONDARY CONTANMENT CLOSURE SOLTS. 6/16-18UNC 2A: ISFT/LSS.

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7. THE SAMPLE vlAL.(SH 4 OF 4)14 HALL DE HYDROST ATIC ALLY PRESSURE TESTEDt375 PS(,

. FOR 6 MMUTES PER NUPAC PROCEDURE LT-10. NO VesLE EVIDENCE OF PERMA

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DEFORMATION SHALL APPEAR.

8.

THE SAMPLE VlAL & OPTIDNAL SECONDARY CONTANMENT VESSEL (F USED) Sv4ALL BE LEAK TESTED ANNUALLY TO 1 s 104 STANDARD CU60C CENTNETERS/SECOND PER '

CACK NUPAC PROCEDURE LT-12.

KAM.

kACKAGE WEl(PIT:

TACirAONG. NC -

SAMPLE SHELD 1800 LDS.

R=107 600 SNP %

SECONDARY CONTANER: 286 LDS.

NNER OVERPACK: 126 LBS.

ACK-SEE SHECT 2 OUTER OVERPACK: 180 LBS.

2400 LSS. TOTAL 3CONDA'.Y Cf MT ANMENT TO TRANSIT. THESE OUTER OVERPACK LFTNG LUGS SHALL BE PLUGGE.D WffH A BOLT & FEN 3ER WASHERS TO PREVENT ATTEMPTED USE AS LFTING OR TE DOWN D SHEET 2 FL1 DETALS-STATIDNS FOR THE ENTRE PACKAGE.

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11. SAMPLE !$ HELD BMALL SE GAMMA SCANNED PER NUPAC PROCEDURE G8 881.

3.D (SECONDARY CONTAMER). 48.0 rep 8 FOR DETALS. k

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NuPac PAS-2 System Consolidated SAR Rev. 0, Februa ry 28, 1989 2.0 STRUCTURAL EVALUATION 7

This Section identifies and des cribes the principle structural design of the packaging, components, and systems import ant to safe ty and to compliance with the performance requirement s of 10 CFR 71.

2.1 Structurni Desian 2.1.1 Discussion The principle structural membe rs and systems in the NuPac PAS-2 packaging are:

(1) the prima ry cont ainmen t vessel, the sample vial described in Section 1.2.1; (2) the sample shield; (3) the optional secondary cont ainment ves sel; (4) the inner overpack; and (5) the out er ove rpack.

The above components are identified on the drawing as noted in Appe ndix 1.3.

They work t oge th er t o satisfy the package st andards set f orth in Subpart C of 10 CFR 71.

A detailed discussion of the structural design of these components is provided below.

,~U 2.1.2 Desien Criteria The pr ima ry function of the inner and outer overpacks is to protect the s e co nda ry cont a i nmen t, sample shield and vial from the hypothetical ac ciden t conditions. Since the sampl e shield is very robus t, the NuPac PAS 2 packaging has been designed t o reduce the severity of the hypo the tical accident to limit s which will not af fect the structural integrity of the optional second-a ry con t ainme n t ves sel, the sample shield, or the sample vial.

In orde r t o demons t rat e the packa ging's ability t o survive the regul a tory transport and ac ciden t co nd it io n s, a combination of full scale tests and engineering analyses has been pe rf ormed. Full scale drop t es t s have been L

perf ormed t o verify the impact at tenuating capability of the package. The NuPac PAS-2 Packaging design is based on the succes sf ul N-55 design, Docke t l

No. 9070.

l Impact energies are absorbed in several ways.

The polyurethane foam inside

.s the outer overpack and the 55 gallon drum inner overpack deforms at a fairly 2-1

__ _________ a

NuPac PAS-2 System Consolidated SAR

. Rev. 0, Februa ry - 28, 1989 U

i const ant stres s on impact and has been used succes sfully in many currently

'n.

Licensed Type B packages as the primary energy absorption medium. Additional-ly,. the ste el shell of the outer overpack as well as the steel drum shell of the -inner overpack also deform plastica 11y on impact. - ' Ful l scale drop tes ts were perf ormed t o ' demons trat e the ef f ectivenes s of this system.

2.2 Weinhts M Center d Gravity The weight of the NuPac PAS-2. packaging ~with the optional seconda ry cont ain '~

ment vessel' is approximately 2400 pounds.

The out er overpack weight is

' approximat ely 180 pounds; the inner overpack weight is approximat ely 120 pou nde; the optional secondary containment-ves sel weighs 300 pounds, and.the skmple shield and vial as sembly weighs approximat ely 1800' pounds.

Th e cent er of gravity ' for the as sembled package. is located at the approximate geometric' cent e r of gr av i ty.

A reference poin t for locating the center 'of gravity is shown. on the General Arrangement Drawing.

(Appe ndix 1.3) 2.3 Mechanical Pronerties d Materials Mechanical properties of the'various materials used in the NuPac PAS-2 pack-aging are shown in Table 2.3-1 below:

l O

2-2

L-NuPao PAS-2 Systsa Consolidated SAR.

~

Rsv. O, February. 28,.1989..

L 4

TABLE 2.3 EECHANICAL PROPERTIES.QE MATERIALS.-

1 ULTIMATE YIELD' STRENGTH STRENGTH E-1-

6 (X10 pgi)

MATERIAL ILSI),,

.3 311 l'

' LOW CARBON HOT ROLLED STEEL 63 46 29 ASTM A516 GR. 70 ASTM A513

.70 38 29 i~

III STAINLESS STEELS (304,316) 80 35 26 3 PCF FOAM 50 PSI 1,700-PSI 10 PCF FOAM 375 PSI 10,000 PSI.

(1) Values shown are typical of stainles s ste els used in the NuPac PAS-2 pack-aging.

Note that all structural stainless used in the NuPac PAS-2 are t ested to 150% of design load without visible def ormation.

2.4' General S t and a rd s & All, Pa ck a n e s Th i s section demonstrat es that the general standarns specified in 10 CFR 71.43 for all packages are met.

2-3

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry. 28, 1939 2.4.1 flinimum Packare h The smallest overall dimension of the NuPac PAS-2 packaging is well in excess of the minimum 10 cm specified in 10 CFR 71.4.3(a).

2.4.2 Tamner-indicatine Feature The NuPac PAS-2 packaging design includes tamper-indicating seals, as shown on the General Arrangement Drawings in Appendix 1.3.

2.4.3 Positive Closure Positive closure of primary is effected by a valve operator cover plate which holds the v al v es closed during sh ipme n t.

Addi t io nal ly, the val ve ports are plugged with face-sealed 0-ring seals installed during transit.

The valve p or t plug pene trations as well as the valve operator penetrations are sealed with double 0-ring bore seals while the shield ping is secured by 4,1/2 inch O

bolt s and se aled with a double 0-ring f a ce-se al.

The opt innal secondary cont ainme nt vessel lid is fastened by eight, 5/16 in, bolts.

An 0-ring bore se al pr eve nt s leakage from this vessel. The outer overpack is equipped with suitable locks and tamper indicating seals to prevent inadv e r t ent and unde-t ect ed ope ning.

2.4.4 Cherical Juut Galvanic Renetions The mat erial s from which the packaging is f abricated (s teel, lead, fiberglass, and polyure thane foam) along with the conte:lt s of the package will not cause significant c h em ic a l, gal vanic, or other reaction in air, nitrogen, or water l

l e nvi ro nmen t s.

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2-4

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l NnPac PAS-2. System Consolidated SAR Rev. O, Fsbrunar 28, 1989 l.. f" t

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2.5 Li f t i n e, gad, Ti e d ow n De v i c e s 1.2I. ALL P a c k n e e s l

2.5.1 Liftine Devices The outer overpack is equipped with four lifting lugs capable of lifting the en tir e system except when the sample shield is in s t al l ed in the inner over-pack. Thes e lugs will be rendered inoperable during transit by use of two.

fla t washers held to the lug with a 1/4 in. bolt to act as a cover.

The NuPac PAS-2 packaging, without the 1800 pound sample shield, weighs 600 pounds.

Per the requirement s of 10 CFR 71.4 5(a), any lif ting at tachment that is a structural part of the package must be designed with a minimum saf ety factor of three agains t yielding when used to lif t the package in the intended manner.

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2-5 i

NuPac PAS-2'Systan Consolidated SAR-Rsv. 0, February 28, 1989-i 2.5.1.1 Lun~Shenront jk.

Assuming only two of f our lugs are ef fective, the load considered'to act on each lug is:

P = 3(600/2) = 900 lbs-Using the standard 40 Shearout Equa tion, the. load to yield a lug is:-

0

[ed - (d/2)(cos 40 )]

P, = 2F,y t

.Where:

F,7 = 21,600' psi (from Section 2.3 where F

= 0.6F )

sy y

t = 0.125 in (minimum) ed = 0.375 in

~d

= 0.3 75 ' in The n :

P, = 2(21,600)(0.125)[0.375 - (0.375/2)(cos 40 )] = 1,250 lbs The lug shearout Margin of Safety is:

M.S. = (P,/P) - 1 = (1,250/900) - 1 = + 0.39 2.5.1.2 Rivet Canacity l

The 3/16 inch riv ets carry a combined loading due t o a bending moment and a l

she a r.

The tensile force in each rivet is f ound by summing moment s about the assumed pivot point 'A':

2P,(0.3 75) + 2P (1.75) - P(0.625) =0 b

2-6

... = - - -

.3 N,M lNuPec PAS-2 ' System Consolidated SAR.

_ Rev. 0,. February 28, 1989l Where:

P, = (0.3 75/1.75 )Pb2 Then:

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2P [(0.375)2/1.75} + 2P (1.75)

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'Pb = 153-lbs.

0.625"

~

1.75" The shear load in'each rivet' is found.by a vertical force balance:

,I P - 4V = 0 p,

V = P/4 = 900/4 = 225'Ibs Calculat e the vector sum of ' the maximum rivet tensile force and shear force:

P, = [ P2 + y 3 5 = [(153)2 +- (225)2j0.5 = 272.1bs 20 Per drawing X-60-200D, flagnote 5 (Appendix 1.3), the rivets have t ension and

. shear strengths of 1,100 and 1,450 pounds, respectively, thus the rive t-Margin of Safety is:

M.S. = (1,100/P,) - 1 = (1,100/272) - 1 = + 3.04 2.5.1.3 Latch Canacity The four (4) CAMLOC 37L33-1-1AA l atches each have a manuf acturers specified ultimate strength of 4,500 pounds and a working strength' of 3,000 lb (Appendiz 2.10.1 ).

By inspection, the latch margin of saf ety will exce ed the lug-l capacity.

l O

2-7

NuPac PAS-2' System Consolidated SAR Rev. O, February 28, 1989

v.

2.5.1.4 Diluut Liftine Devices

\\.

The Carr Lane hoist ring welded to the optional secondary containment vessel lid is rated f or 2,000 lbs. (se e Figure 2.5.1-1), but is only used to lift.the secondary containment vessel lid.

This lid weighs only 130 lb's.,

so there is a large Margin of Safe ty.-

The lid is placarded to prevent lifting it while attached to the vessel body.

The-top of the sample shield is fitted with a 2500. lb..Carr Lane hoist ring

( se e Fi g ur e 2.4.3-1).

The sample shield weighs approximat ely 1800 lbs. and the rated load of the ring is one f ourth of it s ultimate strength.

Since the yield point of mild steel is. typically 62 percent of the citimate strength, the yield load on the ring can be given as:

(.62) (4)(2500) = 6,200 lbs.

10 CFR 71 requires that lif ting fixtures be capable of lifting three times the package weight without exceeding the fixture's yield point. _Theref ore, the margin of safety of the hoist ring is:

6200 M.S. = 3(1800) - 1 = + 1.5 O

2-8

NuPac PAS-2 Systco Consolidated SAR Rsv. O, February 28, 1989 FIGURE 2.5.1-1

,o t

)

V SWlVEL HO ST RINGS FEATURING 3 LOAD CAPACITIES 1000,1500 AND 5000 POUNDS WITH A DESIGN SAFETY FACTOR OF 4 TIMES THE RATED LOAD CAPACITY

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P i

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5 34 5

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grp g/ye MANUFACTURING CO.

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O 2-9

]

L NuPac PAS-2 System Consolidated SAR

'Rev. ' 0, Februa ry 28, 1989 The four shield plug attachment bolts, made to SAE J429 grade 2 specifications or better, must react the weight of the shield body whenever the shield

]

as sembly is lif ted by the hoist ring.

These 1/2 inch - bolts- (13 UNC ' threads) have a stress area for tension given as.1416 in.2 and a yield point given as 36,000 p si.

The total allowable load through the four bolts is then:

.i

(.1416)(4)(36,000) = 20,390 pound s l

The margin of safe ty is then (using the total shield. weight):

M.S. = 20.390 - 1 = + 2.77 3(1800) 2.5.2

_Tledowns The NuPac PAS-2 packaging does not employ tiedowns as a structural part uof. the package.

2.6 Normal Conditions gd; Transnort O

The NuPac PAS-2 Packaging has been designed and constructed, and the cont ent s are so limited (as des cribed in Section 1.2.3 above) that the perf ormance r equir ement s s pe cified in 10 CFR 71.43 and 10 CFR 71.51 will be me t when the package is subjected to the normal conditions of transport specified in 10 CFR -

71.71.

Th e abili ty of the NuPac PAS-2 Packaging to satisfactorily withstand the normal conditions of transport has been assessed and described below:

2.6.1 BtLL A detailed thermal analysis can be found in Section 3.4 where the package was exposed t o direct sunlight and 100 F s till air.

The ste ady st at e analysis 0

conservatively assumed a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day maximum solar heat l o ad.

The maximum inner overpack t empera ture was f ound to be l es s than 240*F.

Such t temperatures will have no detrimental ef fect s on the package.

O 2-10

]

NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 2.6.2

_G.gli O

The two major concerns rel ating to the s tructural perf ormance are brit tl e fracture and the pos sible fre ezing of the sample liquid.

Brit tl e fracture is examined according to the recommendations of NUREG/CR-1815 UCRL-53013.

Of the thre e maj or cont ainmen t component s, only the seconda ry cont ainment vessel and the sample shield are optionally f abricated f rom brittle-fracture-sensitive ferritic steel.

Th e sample vial is made from austenitic stainless s teel, and thus is of no concern f or brittle fracture at the t emperature in question.

Both the optional s e co nda ry con t ainmen t vessel and the sample shield shells may be fabricated from ASTM A516 grade 70 (or austenitic stain-les s ste el as an option) which has a nil-ductility transition a t

-10 F, according to Table NC-2311(a)-1 of Section III, Division 1, Subsection NC of the ASME Boiler and Pressure Ves sel Code.

Brittle fracture, being a dynamic-ally induced problem, is of concern at t temperatures not less than -20 F, since according to Reg. Guide 7.8 the initial t empe ra t ure of the cask during any of the normal loads is given to be this value.

According to NUREG/CR-1815, the lowest al l owabl e se rvice t empera ture (LST) for a given steel is given by the equation:

LST = TNDT + A 1

l Where T is the nil ductility transition t empe rature and A is f ound f rom NDT Figure 7 of the NUREG/CR-1815, shown here as Figure 2.6.2-1.

Since the th ic k-es t pl ate in the design is the 2.38 inch thick Se condary Containment Ves sel 0

lid, A for the lid can be f ound from the Figure to be -10 F, allowing f or the 70 F shift allowed f or steels with yield stresses less than 60 ksi in impact 0

limit ed situa t ion s.

Therefore:

LST = -10 + (-10) = -2 0 F Therefore, the NuPac PAS-2 packaging meet s brittle fracture requirements over the range of t empera tures required by the applicable regulatory guides.

O 2-11

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - -

' - ~ ~ ~ ~

~~

~

'~

L.

ll

'/

.NuPac'; PAS-2' System Consolidated SAR'

' Rsv a 0, Februa ry 28, 1989

~

! ';j-X -.y A/

),

' 2.5 l

l I

I i 70"F for oY < 60 ksi I

6 I

I

'TN O T = LST-A '

30*F Thin section rules apply 2.0 Kigg/oyd s3 1.5 p=d6 X e

s.

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1.0 0.5--

I f

g

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I 3

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I O

-40 : 10 0

20 40 60 80 100 0. l 1 2 2,38 3-4 A('F)

. Thickness (in.)

DESIGN CHART FOR CATEGORY II FRACTURE CRITICAL C0f.!PONEhTS FIGURE 2.6.2-1 2-12

NuPac PAS-2 System Consolidated SAR Rev. O, Februsry 28, 1989

(

The second concern relating to structural performance at l ow t empera tur es is the ef fect of freez ing of the sampl e.

The intended use of the NuPac PAS-2 packaging (to transport reactor coolant samples to a qualified laboratory for analysis) demands that the sample be tightly sealed within the sample vial.

0 Since the inte rnal hea t of the coolant is no t large enough to cause a 72 F temperature gradient be tween the sampl e and the out side of the cask, the sample will fre eze if it s packaging is exposed to a steady state ambient 0

temperature of -40 F.

How e v e r, the f ollowing characteris tics of the packaging j

and it s intended use mitigate the consequences of this si tua tion:

1.

The package would be used only in response to an emergency situation at a commercial reactor s it e.

Such situations would not oc c ur frequently in the life of a plant.

2.

The package would be shipped on a priority basis whenever used, due to the time value of the contents.

Therefore, should the package i

be unprotected f rom the environment during shipment, the foam-filled

,m i

overpacks will insulate and ret ain the s tored heat held in the shield mas s for a con sider abl e period af t er exposure to cold. Cal-0 cul ations show that the exposure to -40 F would have to continue for nearly 5 days before s olidi f i ca tion of the sample would c omme n ce.

This is in excess of the time the sample would normally be exposed.

l NUREG-073 7 r equires the sample to be t est ed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of the a c cide nt.

3.

Should f ailure of the sample vial occur, all contaminated materials would remain fully contained within the sample shi e l d and absorbed by the vermiculit e.

Because there is enough vermiculite in the sample shield cavity to absorb twice as much liquid as the vial can hold, no free liquid would be available.

There would therefore be no rele ase of cont amina tion t o the e nvironment.

l 4.

All materials needed in the construction of all the components of the NuPac PAS-2 packaging have been shown t o be brit tle frac ture r"~g Q

resistent according to the requirement s proposed f or Ca tegory II 2-13

NuPec PAS-2 Systen Consolidated SAR

' Rav. ' 0, Februtry ' 28',i 1989 applications -in NUREG/CR-1815, :UCRL-53013. < Theref ore,- neither the.

in U.-

optional ' secondary containment, ' the sampl e shleid nor the overpacks 0

would exhibit. reduced capabilities at -20 F, the lower t empera ture

' limit of operational loads.

.5.

The 3-way Whitey ball val vos are rated by the manuf acturer (s'en 0

Ap pe ndix 2.10.4) t o t empera t ur e s a s l ow a s '-2 0 F.'

Th e 'de si gn' h as -

been tested by the manuf acturer'. to'.be. ~ unaf fect ed by fr eez ing. water within the val ve.

6.-

The 316 stainless steel used in the design of the sample vial.-is highly ductile, allowing as much as 55 percent deformation before rupture.

Should the' NuPac PAS-2 be. subjected to sub-freezing t temperatures f or ' ext ended periods, the sample within the vial would freeze.

The resulting expansion of the.sampl e would. proce ed in a predictable manner which would not viol ate cont a inme n t.

O Freezing of the sample would require the sample vial to expand and deform to ac c ommoda t e th e lower den si ty of ice.

This. v ol ume change can be calculated f rom the dif ferenco between the sample density when loaded and the minimum density of the sample af ter s solidification.

Although the temperature of the sample when loaded into the paczage is expec-0 t ed to exceed 300 F, the density of the sample sh al l be t aken as the density 0

of water at 200 F.

This density is given in the CRC Handbook of Chemistry and 3

Physics, 53rd Editilon, as.962 grams per em, and the density of ice is given 3

a s.917 gr am s pe r em.

The volume changes by the factor

.dfl.= 1.05

.917 O

2-14

'NuPac PAS-2 Systam Consolidated SAR Rev, 0, February 28, 1989 or a 5 percent incre ase in v olume. As the sample' fre ezes,.the water in the narrow passageways in the vial will freeze first, due to the high surface-to-volume ratio of these f it tings.

Some of the water in these-pas sageways will be forced back into the 1 inch pipe as the passages freeze, since the one-inch pipe is the most flexible part' of the system under internal pressure loadings.

v e s s e l's exhibit hoop stresses twice as large as l'ongi-Cylindrical pressure tudinal s tres ses.

As a result, the expanding sample will cause hoop stresses E

in the 1-inch pipe to reach yield well before the pipe-elongates.

Assuming, then, that th e 5 percent volume change is entirely accommodated by.

an increase in cross sectional di ame ter of the 1-inch pipe, the hoop s train can be calculated:

V = sd.2g 4

1.050 = n(1.025d)2n

.CT 4

Q)

Theref or e, the di ame t e r incr eas e s 2.5 pe rce nt.

Since the hoop s train is by definition, the change in the circumference of the pipe, and the circumference is linearly dependant on the diameter, t he hoop s t rain is al s o 2.5 pe rce nt.

The r ef or e, the s train Margin of Safe ty is:

M.S. = 1 -1 = +21.0

.025 It is unlikely that the loaded NuPac PAS-2 would ev er be subj ect ed to sub-fre ezing t empera tures f or a period long enough to induce the yielding de-s cribed abov e.

Should f reezing occur, however, there is ampl e elonga tion available in the material to prevent rupture through twenty fre eze-thaw cy-cles.

O 2-15 L

l

{

NuPac PAS-2 System Consolida ted SAR Rev. O, Februa ry 28, 1989 2.6.3 Reduced External Pressure

. ;3 4

pO The sample vial, the cavity of the sample shield, and the optional s eco nda ry con t a inme n t v es s el ar e de signed t o be pr es s ure tight.

Se als on th e P AS-2 outer overpack as well as the lid closure on the inner overpack are designed t o minimize the en trance of exte rnal environment al element s such as r ain, I

dust, etc. The valves are rated at 250 psig at a temperature of 450 F.

The components of the vial as s embl y a r e r a t e d pe r ANSI B.31.1 to 1000 psi or greater. The sampl e vial is tes ted to an internal pres sure of 375 pai to verify its integrity after fabrication; therefore, a 3.5 psia e xt e rnal pres-sure (equivalent t o an 11.2 psig internal pres sure) does not present a h az a rd.

The optional seconda ry containment vessel, as well as the sample shield, are tested to 1 atmosphere pressure and demonstrated to be leak tight.

Therefore, a 3+5 p sia exte rnal pressure on either the seconda ry cont ainment or sample shield is not more severe than the f abrica tion verification or annual main-tenance tests performed on them.

2.6.4 Increased External Pressure OV An external pressure of 20 psia will also have little ef fect on the NuPac PAS-2 pac kaging. First, as s ume tha t the out e r overpsck's dus t se al is pres sure tight.

A s s um in g that the double wall construction act s as a s tres s skin design forcing the two shel l s t o work toge ther. Sides react pr es s ure s in hoop compression while the thicker skin ends act in pl at e bending.

Stres ses produced in the circular ends due to exte rnal pressure loads will be carried in the f orm of pl ate bending with the out side sheet is in compres sion ar.d the inne r she e t is in ten sion.

Foam compression strengths in excess of 50 psi are present at all points.

The maximun bending moment in a circul ar uniformly loadeel plat e is given in Timo shenko, Theory s.1 fl a t e s Anst She l l s.

p a g e 61, a t :

)!r " Nt =3+ q2 16 A

i i

v 2-16

t-I'

~i NuPsc PAS-2 Systas Consolidated SAR

. Rav, 0, February 28, 1989'.

q om.

. fy -

Where:

Poisson's Ra tio

.3' j.

0 = ext ernal pres sure, (20-14.7 = 5.3 psig).

A = radius of plat e - (16 in. )

-l Then:

M,=

3 +u (5.3)(16)2 = 280 in-ibs.

16

.in.

Consider an element in the circular container end, subjected to 25 psi exter-.

nal pressure:

I

/

C7" 2

LO FIGURE 2.6.4-1 The moment of inertia I for a sandwich structure, using the transfer formula is equal to:

2 I

=

I,, + 2Ad no i

Where:

I,, is negligible A is Area per unit width of laminae d is distance from th e cent e rline a

l For a 5-1/2 in, foam thickness, i

I

= 2 (.04 8) (2-1/4)2 =.485 in4 on 2-17

a NuPa c. PAS-2. Sys t sa ' Cons olida ted :S AR '

Rev. 0, February 28 1989 1

' Str es s : in' the ~ st e el shells will be equal to:

1

, ; ?v -

l-

.g.,g,, ( 2 80 )( 2 1/ 4 ) _ 1,299, psi-J I -' .485 l If the' allowable stress f or the steel is taken at 46,000 psi (reference. Tab 1'e, 2.3-1) the n: -l M.S.'= 46.000 - 1 = + Large 1,299- -L Therefore, the oute'r 'overpack is capable of reacting the 20 psia external pr es s ur e. Since the Secondary Containment Vessel, the Sample _ Shield, and the Sample Vial are al l subjected to external pressures in excess of 5.3 p sig ' during routine'- maintenance, it is clear that these pres sures will have no ef fect on 'the packaging's ability to meet the r equir ement s of 10 CFR 71. i 2.6.5 Vibration Shock and vibration normally incident to transport are considered to have negligible ef f ect s on the NuPac PAS-2 Packaging. 2.6.6 Vlater Sprav Since the package exterior is constructed of steel,.this test is not required. 2.6.7 Free R 42. The four foot drop r eq ui reme nt is not applicable in light of the more strin-gent 30 foo t drop r equirement of Appendix B of 10 CFR 71. Refer to Section 2.7, b e l ow e O 2-lh'

NnPac PAS-2 System Consolidated SAR ( Rev. O, February 28, 1989 .2.6.8 Corner Eggg This r eq ui rement is not applicable since the NuPac PAS-2 Packaging is f abric-ated of steel. 2.6.9 Compression 10 CFR 71 requires that packages under 10,000 pounds gross. weight be capable of supporting a compres sive load equal to the greater of 5 times the package's loaded weight or 2 psi unif ormly applied the top and bottom surf a ces of the package in the position which the package is normally transport ed. Since the NuPac PAS-2 is designed to be transported vertically, the surf aces in question are the 32-inch diameter circular ends: n(32)2 = 804.25 in.2 4 Since the package weighs 2400 pounds, the compressive s tres s for a load of 5 g's is: 5(2400) = 14.9 psi 804.25 Since the entire external shell is backed with rigid polyurethane foam with a compres sive strength of approximately 50 psi, the Margin of Safety is: M.S. = 33_ - 1 = 2.35 14.9 2.6.10 Penetration l From previous cont ainer t es t s as well as engineering judgement, it can be concluded that the 13 pound rod would have a negligible effect on a heavy 20 gauge f oam-ba cked s t eel shel l. O 2-19

NuPac PAS-2 System Consolidated SAR ' ksv. ' 0, February 28, 1989 AQ' ,O ' - 2.6.11 Conclusion (A As the result of the abov e as ses sment, it is' concluded that under normal conditions of transport: 1. There will' be no release of radioactive material from the contain-ment v es sel.

(

2. The ef festiveness of' the packaging will not be reduced. s 3. There will be no mixture of ' gases.or vapors in the package which. ' could, through any credible' increase in pres sure or an explosion, r edu ce the ef festiveness of the package. 2.7 'Ilynothetical Accident Conditions The NuPac PAS-2 package has been designed and its contents are so limited that the perf ormance requirement s specified in 10 CFR 71J1s will be me t if the pac kage is subj ect ed t o the hypo the tical ac cident conditions : pe cified in 10 CFR 71.7 3., To demons trat e the s tructural integrity of the package and it s ability to withs t and the hypo the tical ac cident conditions, detailed analyses and full s cal e t es t s were conduct ed. It 'is important to not e that the t echniques, analysis methods, assumptions, and routines employed follow closely those used ' f or other petitions such as: l O ) 2-20 1 ..-_-___-__a

i ' NuPac PAS-2 System Consolidated-SAR Rev. O, February.28, 1989 1. DOT _6400 Super Tiger 2. DOT 6553 Paducah Tiger i 3. DOT 6272 Poly Panther i 4. DOT' 6679 Half Super Tige r 5. DOT 6744 Poly _ Tiger 6. AECB - Resin Flask 7.- - NuPac Model N-55, Certificate of' Compliance #9070 8. T-3 Spent Fue1~ Shipping Cask, Certificate of Compliance No.-9132. 9.- 1-13C(II) Shipping Cask, certificate of Compliance No. 9152. J ?rhese are proven techniques that agree closely with full scale tests as well as o ther publicized st andards such as ORNL-NSIC-68. In all cases,. the ' analy-sis has been proven to be conservative when compared with ful.1 scale testing. 2.7.1 him. J2IQg Event s Ful l s ca l e pro to type drop tests were conducted on the NuPac PAS-2 system to demonstrate the c a sk's s urvi vabili ty of the hypo the tical accident' conditions po s tul at ed in 10 CFR 71.7 3. Nucl ear Packaging, Inc. has considerable experi-ence designing and drop t esting ove rpack sys t ems, hav ing co nduct ed sever al successf ul drop test s since 1977 on the N-55 Package as well as the 1-13C and the Padu cah Ti ge r. The t est pad used was specially designed to simulate as much as practical an unyielding surface, and has been the t arget f or drops of as much as 46,000 pounds (the Paducah Tiger). It is approximat ely 6 feet wide,12 f e e t long, and 8 f eet deeps constructed of concrete,'with a 2 inch thick steel plate inlaid into the top surface. The test pad has not e xhibit ed any discernable deformation from any of the protected and unprotect ed drop t est s conducted on it. 2.21

y NuPac PAS-2 System Consolidated SAR: Rsv. O, February 28, 1989 One NuPac PAS-2 proto type was subjected to 3 drop test s. First, the package was dropped 30 f eet with it s centerline parallel to the surf ace of the test pad. Second, the same package was dropped 40 inches ont o a 16 inch long, 6 inch di ame t er s t e el pos t, pe r 10 CFR 71.7 3(c)(2). Finally, the same 'packa ge. was subject ed t o a second 30 foot' drop with it s centerline oriented perpen-- .dicul ar to the surf ace of the pad, with the t op end of the package impacting the pad. Photographs of the drop t est s can be f ound in Appendix 2.10.3. By examining the results of previous drop tests, the effects of various drop. l orient a tions can be eval uat ed.- The particular drop orientations tested maxim-Aze the potential damage to the optional secondary containment vessel. In a side impact, there is the le as t foam thic kn e s s t o dis sipate the drop energy, causing the highes t accelerations to the package. The 40 inch drop onto the 6 inch diameter post was positioned such that the post would directly impact the surf ace of the package corresponding to the' optional secondary containment (which was included in the test) lid seal. End impact was ef f ected on the top end, again maximizing the potential damage to that critical seal. Acceptance criteria were based on th e ability of bo th the se conda ry cont ainment vessel and the sampl e vial' to pas s a highly sensitive leak tes t bef ore and af ter subjection t o the drop t est s. The sample shield cavity on the proto type was not sealed; however, the result s of the test program indicate that these seals would be complet ely unaf fected by the drop event s. 2.7.1.1 f.id.a. RI.Qg Re sui t s The first drop test perf ormed on the NuPac PAS-2 packaging was the side impact drop from 30 feet. Before and after photographs are shown in Appendix 2.10.3. Permanent deformation of the packaging was measured as follows: O 2-22

NuPcc PAS-2 Systga Consolidated SAR Rsv. O, Februa ry 28, 1989 Reduction to out side diameter of outer (_,) overpack at impact 2.5 in. Reduction of inside diameter of outer overpack at impact .8 in. Reduction of inner overpack foam thickness 1.3 in. TOTAL FOAM DEFORMATION: (2.5 .8 + 1.3) 3.0 in. The circumferential stiffening hoops on the drum were flattened on the impact side, and the fiberglas inner skin on the outer overpack also was cracked in the area of impact. One of the outer overpack lid latches was directly on the point of impact; aft er impact the latch held, but was rendered flush with the side of the package. An 8 inch long crack in the side of the 55 gallon drum also appeared, but since the drum is not a cont ainment boundary, this crack is of no consequence to the safety of the packaging. N] 2.7.1.2 Puncture RI22 Resnits Af t er the side drop f rom 30 f eet, the package was dropped 40 inches onto a 6 inch diamet e r pos t. The package impacted the post on the opposite side of the package than was impacted during the side drop. Before and after photographs are shown in Ap pe ndix 2.10.3. Post impact caused the f ollowing pe rmanent deformations: ! O l 2-23 L-

.q N: Pao' PAS-2 Systco Consolidated SAR Rov. ' 0, Fobrua ry. 28; 1989 Reduction of ' out side diameter of outer () overpack local to impact: 1.0 in. Reduction of inside dian ter of outer overpack: .3 in. - Tot al local def ormation of the outer overpack: .7 in. There was no permanent def ormation t o the foam inside th e d rum. Th e dr um experienced minor def ormation local to impact. This drop al so impacted a la tch, which ; was. severely damaged. In spite of this damage, the latch stil1~ held. The fiberglass inner skin of the outer overpack cracked slight 1r local: to the< impact. 2.7.1.3 ImL Rg,gg Re sul t n The final drop test had the package impacting directly-onto its top surface. This orientation caused the secondary containment vessel lid to react the full impact load from the 1800 pound sample shield. Before and after photographs: are shown in Appendix 2.10.3. Permanent def ormations to the packaging are summarized below: 1l' t .. O 2-24 L

NrPac PAS-2 Systes Consclidcted SAR Rsv. 0,' Febrasry 28, 1989 >,g3 ( *s,,), Reduction of overall length. of outer overpack: .8 in.- Increase of cavity length at top of outer ove rpack: 5.5 in. Total decrease in end thickness of outer overpack: 6.3 in. Deflection of drum cover center: 2.0 in. Reduction in d2ickness of top inner overpack foam: .8 in. Tot al Overall Foam Def ormation (6.3 +.8) 7.1 in. The inner fiberglass liner on the outer overpack experienced a shear / tension f ailure circumferentially where the drum impacted the out e r overpack. Exam-( ination of the damage indicates that the drum cover bulged out agcinst the top of the outer overpack causing a dome-shaped def ormation in the foam. Then the fiberglass failed as described above. Thus, f ailr.re of the fiberglass liner contributed significantly to the energy dis sipation pro per t ie s of the out e r overpack. Interestingly, one of the previously undamaged latches opened on impact, while bo th pr eviou sl y impac t ed la t ch e s continued t o hold firm. Apparen tly, the impact drove the outer overpack base into the lid on one side f ar enough to unhook the pull-down toggle. Examination of the lid lip near the failed latch reveal ed that the f oam in the lid had shat tered either in the end impact or one of the pr evious drop s, allowing f airly free movement between the two halves of the overpack near the failed latch. 2.7.1.4 Conformance As,Accentgggg Criteria Survivability of the containment boundaries and shield is crucial to the () packages co nf ormance to paragraph 71.51 of 10 CFR 71. Careful attention was 2-25

NuPac Pall-2 System Consolidated SAR. Rev. O, February 28, 1989 t given bef o o and after ' the drop t est - to insure that any leaks present in the sys tems af t er the drop t est would be f ound, and would be as a resul t of the cumula tive ef fect s of the drop t est s ra ther than pos sible mishandling.or. ' assembly. A l e ak ra t e from any - l e ak t es t in excess of 1 x 10-7 standard cubic centimeters 'per second would be considered unacceptable. All leak test s, both bef ore and af ter the drop t est s, on both the sample vial and secondary con-t a i nme n t, t e s t ed l e ak ti ght t o be t t e r the 1 X 10~I standard cubic centimeters per.second, the limit of sensitivity of the. mas s' spe ctrometer l eak de tector-used for the - t es t. ~ Neither the shield nor the secondary. containment vessel sustained any per-coptibl e def orma tion. The only indication on either item that any unus ual loading had occured was on the inside of the secondary containment lid, where the shi el d - pl ug clo s ure bolt s s cra t ched the highly polished s urf a ce of the lid. Therefore, it can be concluded ~ that shielding will be unaf fected by the ef f ects of a 30 foot drop or 40 inch drop onto a 6 inch diameter' post. As stated above, the prototype used in the drop tes t was not equipped with a test port for testing th e s asipl e shield. cont ainment boundary bef ore the drop t es t program. Howev er, this containment boundary t es ted to be tt er than 1 x 10-7 standard cubic centimeters per second af ter the drop' test. Because there was clearly no damage to the sample shield from any of the drop t ests there is no reason that the con t a inme n t bounda ry would be affected by'any of the regul atory dror: in any way. 2.7.2 Puncture The effects of a 40 inch drop onto a 6 inch diameter steel post are documented in Section 2.7.1 above. Pro to type testing showed no damage to any containment boundaries f rom this ev ent. O 2-26

NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989' 2.7.3 Thermal Analvais O-i Thermal evaluations for the NuPac PAS-2 Packaging have been conducted for both normal transport and hypothetical thermal accident conditions. These evalua-tions are presented in Section 3.0 of this report. 2.7.4 T==arnion _ Fissile Material This section is not applicable, since the NuPac PAS-2 package will not contain fissile materials. 2.7.5 T==,rsion _ All.Packanes An external gauge pressure of 21 psi will not significantly af fect the NuPac PAS-2 packaging, since it is designed to handle much higher internal pr es sur es. However, in Section 2.6.4, - the outer overpack was analyzed for an internal pressure of 5.3 psig, and a stress of 1299 psi was calculated for the s teel shell. The stress under 21 psig will be: (21/5.3) x 1299 = 5147 psi The margin of saf ety is then: (46,000/5147) - 1 = +Large For the Se conda ry Cont ainment Ve s sel, the 3/8 inch end plate would be the critical struc ture. From Timeshenko: 2 M = 3 + u QA 16 Where: O 2-27

tr-N: Pac PAS-2 Sy' stem, Consolidated SARL Rav.10, Februsry' 28, 1989L g = Poisson's' ratio = 0.3-Q = Pressure.= 21 psi A = Plate' Radius = 9 inches So, - 2 ~ M =- (3.3 /16)(21) (9 ) =. 351. Ib.-in./in. . Now~, 3/12 = 0.3 75 /12 = 0.0044 in.4/in. 3 I.=t Mc/I = (351) (0.5) (.3 75) /0.0044 = 15,970 p si. The Secondary Containment Vessel could be made from carbon or stainless steel. The minimum yield material is the stainless, with a yield strongth of.36,000 psi. The Margin of Safety is then: MS = (30,000/15,970) - 1 = +0.88 There are no structures in t he Sampl e shield pres sure boundary which would develop stresses in excess of 15,970 psi under an external pressure loading of 21' psi. Since none of the accident events result in either of these pres sure = boundaries to be damaged in any way, no further analysis is required. However, it can be easily seen that the high pres sure Sample Vial is fully capable of resis ting a 21 psi external pressure. l l l l O 2-28

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 O- .tg 2.7.6 Sa===rv si Damage From the above analyses and tests, it can be seen that there will be no significant damage to any of the NuPac PAS-2 containment systems or radiation shields from the hypothetical accident event sequence se t out in 10 CFR 71. Damage would, in fact, be limited to the inner and outer overpacks, and there would be no reason to require any rework or remanuf acture of any other part of the packaging syst ems af ter such an event, should it actually occur. 2.8 Snecial fsIn Not applicable, since no special form is claimed. 2.9 1231 Egla, Not applicable, since no fuel rods would be packaged in the NuPac PAS-2. O l 2-29

I l NaPac PAS-2 Systen Consolidated SAR - Rev. O, Februsry 28, 1989 s 2.10 Annendir l 2.10.1 Moved h Section u O O 2-30

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 2.10.2 Incorporated h Section. M O { O O 2-31

1: L N'uPac' PAS-2 Sys tem Consolidat ed SAR. - Rev. 0, Februsry 28, 1989 l: 7 2.10.3' h.D.n.T.na.1. Re sul t s k ' The following pages present a pictorial record of the drop tests performed on ~ the NuPac PAS-2 package. The phot ogr aphs are numbered, and explanations 'appe ar bel ow: Photorrach h 1.:. The NuPac PAS-2 package, just prior to drop tes t s. Pho t o r rach h h, Th e NuPa c PAS-2 pac ka ge, subs equent t o the final 30 foot drop, impacting on the package top end. Photographs 1 and 2 provide a good before and after comparison for the cumulative ef fects of the three drops on t h e packaging. Photorranh h h Just prior to first 30 foot drop. Photenrnnh h 3,.1, Package shown approximat ely one foot above ground on re-bound af ter initial impact. sd Photorranh h L' Measurement of damage from the side drop. 'Undeformed diameter is 31-3/8 in ch e s, phot o shows 2-1/2 inch def ormation a t bo t t om e nd. Photorraoh h 11, Impact zone of side drop. Note newly recessed latch. Photocranh h L. Puncture impact height verification. Photocranh A J.; Ext e rnal damage from puncture impact. Not e popped rivet s. Photocranh h 3.1 NuPac PAS-2 rigged for final 30 foot d ro p. See pho t ogr aph No. ' 2 f or resul t ant damage. i 2-32

,NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989, Ph'otocranh h 121 Ext erior of 55 gallon drum af ter t est s. flh it e a re a s j%V) ~ due to abrasion with out er overpack fibe rglas s liner. Note horizontal are crack in cent er - of picture. Photo 2ranh h 111 Inner overpack damage af ter drop. Note cracks and crushed foam on far side. Blue streaks result s from glue, sed to glue foam pie ce s toge ther. ~ Photorranh h 22,1 Damage. to inside of outer overpack from end' drop. Note fiberglass separation on far side. Photonranh h lli Inside of optional Secondary Containment Ves sel Lid. Not e s cratches from shield plug closure bolt s. O 1 2-33

I NnPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 0 ~ ~ ^ -._.4.,._' y [ ~~". JERIEE . :k. E z< y , r, i -.;3 gM.M v e

ndently of eacn other. ( g ,3 ,e

• Spring loaded seats assure positive sealing at low prev

.4 sure and cunng pressure and temperature cychng.

• Pressure loaded seats assure a rehable leak-tight seal at each seat, regardless of flow direchon.

.am e Brow.outproof stem provides maAimum safety.

• BallJs blow outproof from the bottom. top and sides even

"" ~ if the down stream er't. screw as accidentally removed.

• Chalce of seat meterials allows use m the widest range of pressures and temperatures.
• Choice of reptsceable SWAGELOK Tube Fitting or pipe end connecflons provides added system versatihty.
• On.off and 3.Way swstching models meet a vanety of system requirements.

hh[,,4.L ' f f,

• !'t

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• Heary duty handle stops extend operstmo hfe.
• Wettedparts and frlm are corrosion resistant.

5

• Direcflonaf handle orovides visual stem positron er $catioi

( e Handles available m optsonal colors: blue, green. orange.

1. ao red and yellow.

e Panel mounting,s standard for ease of instaHation. o

• Air actuated models have either double acting of spring b "'....

return actuators for use an remote or hazardous systems. I

• UOhr werght compact design allows use en systems with

'7 space hmrtations.

• Sealservice kris simphfy field repair if reovered MATERIALS g

4 Body. End Connection. Stem. Trunnion Mounted Ball. Seat e e Camer, Camer Guide Seat Springs, Pano6 Nul-316S$ i ~ OR6ngs-Viton Back up Rings, End Connection Seal-T7 E Stem Beedng-Filled TFE in 2 Way, vespel in 1 War Stop Pin-316SS WHITEY CO. Handie-Stack Phenonc sta sisMoP #0a0

• MiGNta af o Hf #GNf 3. ONio dand3 Handle Insert-Brass. navat

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YOUR LOC AL SALES & SERVICE RE?RESENTATIVE: m- ' '11. 9 l "ar h 2-39 NuPac PAS-2 System Consolidated'SAR Rev.. O, Fe nruary 28, 1989 3.0 THERMAL EVALUATION i% This section identifies' and describes the principal thermal engineering design ' as pect s of :the NuPac PAS-2 packaging import ant to safe ty and compliance with the-performance requirements of 10 CFR 71. 3.1 ' Discussion-f

The NuPac PAS-2 packaging is designed with a. totally passive thermal system.

The principal physical characteristics of this thermal system consist of a fully enclosing overpack surrounding a DOT Specification 17H or 17C, SS ~ gallon' 4 drum, enclosing more impact absorbing (and thermal insulating) f oam, which in turn encases the thermally mas sive sampl e shield and se conda ry c o n t ainme nt. The outer overpack is f abricat ed of 20 gauge (0.0359 inch thick) gal vanized sh ee t s t e el out er sh ell, a 0.125 inch thick fibe rgl as s' inner sh ell, and' ap-proxima t ely three pound per cubic foot cl o sed-cel l polyure th ane foam in be-l tween. The payload consists of a reactor coolant sample, estimated to contain' p approximat ely,3 wat t s of decay hea t. .The details of the payload are described l i n S e c t i o n 1.2.3.' i Three heat transf er analyses were run f or each of the three cl ossifications of payload utilizing the computer thermal network analyzer program THAN: i ) (1) A normal condition s t eady-s t ate analysi s a t an ambient t emperature of 0 100 F with insolation, l, (2) An accident condition steady-state analysis at an ambient temperature of l 100 F without ins olation, and l I (3) An accident condition transient analysis at an ambient t emperature of 1,475 F f or thir ty minut e s f ollowed by exposure t o 100 F ambient air .) with suf ficient t ime f or t empe ratures throughout the package to maximize. j 1 The NuPac PAS-2 packaging is analyzed for 3.0 thermal watt s. Maximum tempera-tures at various l oca tions within the NuPac PAS-2 packaging are presented in O Tabi c 3.1-1. Details of the thermal analyses are presented in Section 3.0 3-1 NuPa c PAS-2 Sys t em Cons olida t ed S AR Rev. O, February 28, 1989 1 i l t N) TABLE 3.1-1 Maximum Temperature (OF) i Outer Outer 0/P Inner Analysis Type 0/P Shell Inner Shell 0/P Shell Payload Normal Condition 153.8 161.5 161.9 180.8 Steady-state Accident Condition 100.2 108.0 108.5 127.5 St e ady-s t a t e Accident condition 1,471.8 135.3 117.41 136.31 Tr an sien t r-1. Rising at a rat e les s than 0.03 F/ hour. ( O 3-2 NuPac PAS-21Systs:m Consolidated SAR Rev. O, February 28, 1989' 3.2 Sn==arv of Thermal Pronerties of Materials q L The NuPa c PAS-2 packa ging is f abrica ted primarily of carbon and s t ainl es s steel, lead, fibergl as s, and polyure thane foam. Void spaces are assumed to be filled with air. ~ The f ollowing t able document s the thermal properties util-ized in the analysis models and the source from which they were obtained: Pro per ty - Carbon Ste eli Foam

• Fiberglass 8 Inner 0/P

' Assembly

• Co nduc t i v i ty 26.0

~ 0.0142 0.25 N/A (BIV/hr-ft OF) Emissivity 0.8 N/A 0.8 0.8 d Density 490 3 155 N/A (1b/ft3) Specific Heat 0.113 0.30 0.28 0.30 (BTU /lb JF) 1. Holman, Heat Transfer. Table A-2 2. Product brochure for LAST-A-FOAM, General Plas tics Manuf acturing Company, Ta c oma, - W a sh in gt o n 3. Materials Selector, 9/75 4. Assumed 0 At temperatures above 400 F, the polyurethane f oam begins to decompose form-ing a char and gas. Gases are vented from th e overpack through two low melting point plastic plugs. The char is a porous material that blocks the j radi an t he a t. For analysis, the foam char may be represented by an equivalent air gap without radi ant heat t ransf er (i.e., air conduction only). Since the thermal co ndu c t iv i ty of air varies significantly wi th t empera ture, b/ the following table is used in the thermal analyses for all air gaps: 3-3 r__ - - .NuPac PAS-2.Systen Consolidated SAR Rev. O, February 28,-1989. l's j'.D Air' Temperature Air Conductivity * [' (OF) (BTU /hr-f t-F) l 'O 0.0133 32 0.0140 100 0.0154 l 200 0.0174 300 0.0193 400 0.0212 500 0.0231 600 0.0250 700 0.0268 800 0.0286 900 0.0303 1,000 0.0319 1,500 .0.0400' q 2,000 0.0471 V 1. Kreith, Prineinles of Heat Transfer, 3rd Edition, Table A-3 3.3 Technien1 Specifications of Comnonents The materials used within the NnPac PAS-2 packaging which are considered to be t empera t ure sensitive are th e ne o pre ne dust seal and the pol yur e th ane foam. 0 0 The neopreno seal has an allowable temperature range of -40 F to 250 F per Page A3-35 of the Parker 0-Rine Handbook. ORD $700, 1982. The polyurethane 0 foam will char at temperatures above 400 F. 'The Viton 0-rings in the pack-0 0 aging are specified for the range from -65 F t o +400 F (600 for short periods). Other package materials are steel and fiberglass which have melting points of 0 0 0 2,600 F and 1,35 0 F, r es pe c ti v ely. Le ad mel t s a t 621 F, and vermiculit e 0 melts at 2200 F. r 3-4 l NuPac PAS-2 Systam Consolidated SAR' Rev, 0, ' Februa ry 28, 1989 3.4 Thermal Evaluation for Normal Condit %ns of Trensno n 'V i 1 This section presents the thermal analyses for the NuPac PAS-2 packaging f or normal conditions of tr ans p or t per the r equi r ement s of 10 CFR 71.71(c)(1). A 0 100 F ambient temperature with the following insolation values was used for heat input t o th e exterior of the package. Tot al Ins olation fer. a 12-Hour 2 Form and Location of Surf ace Period.(g cal /cm ) Flat surfaces trans port ed horizont ally - Base Wone. - Other Surf aces 230 Flat surfaces not transported horizontally 200 Curved Surfaces 400 3.4.1 Thermal Model 0 3.4.1.1 Analvtical Model Figure 3.4-1 illustrates the thermal model utilized for the normal conditions heat transfer analysis. Due to the simplicity of the package, the out side and inside surf aces of the package are modeled as just one node each. Additional-l y, the model as s umes axi al s ymme t ry. Heat transfer mechanisms, for the undamaged overpack, are represented by 16 thermal resistors connecting the 13 nodes in an appropriate manner. An additional hand analysis is performed to estimate the t emperature at the semple vial from the t emperature at the out-side surface of the inne r overpack (node N13). l Thermal Capacitances: 1 Thermal capacit ances are t abul ated f ollowing a brief weight s analysis to determine overpack mas s distribution. Th e design weight for the out er over-pack is 180 pounds. \\ 3-5 i NuPac PAS-2 System Consolidated SAR Rsv. O, Fsbrua ry 28, 1989 Figure 3.4-1 \\ RJ THERMAL !!ODEL Ambient N1 R1 R2 N2 Side B T Outer Shell 7 -7 ottom 7 op y R4 R8 R12 Edge Closure ON3 oN4 ON5 e3 p V R5 R9 R13 7 Mid-Wall R3 ON6 ON7 ON8 R6 R10 R14 oN9 ON10 oN11 R7 R11 R15 N12 1 inner Shell / 4 R16 Payload oN13 I) x.y 3-6 l w__________ l NLPac PAS-2 Syster, consolidated SAR Rev. O, Februa ry 28, 1989 i pri ' Al though r ho. package maximum gros s weight is 2400 pounds (Section 2.2), the 2, analysis ;,n >ervatively as sumes that the package weighs caly $00 pouads more than th e out e r ove rpack. This assumption will not affect st e ady St at e ra-suits, but the transient analyses will tend to produce cesservatively higher predicted t temperatures due t o the lower overall thermal mas s. Ext ernal Steel Shell Weight (Mode 2): W = n[(32)(48) + (32)2/2](0.0359)[490/(12)3] = 65.4 lbs Top Foam Weight (Nodes 5, 8, and 11): W = (n/4)[(32)2(7.5)][3/(12)3] = 10.5 lbs Bottom Foam Weight (Nodes 4, 7, and 10): W = (n/4)[(31.3 75)2(6)][3/ (12)3] 8.1 lbs = Side Foam Weight (Nodes 3, 6, and 9): W = (r/4)(((32)2 - (25)2)(14) + [(31.375)2 - (24)2](21.5))[3/(12)3] = 19.6 lbs Inner Fiberglas s Shell (Node 12): W = n[(24)(35.5) + (24)2/2 + (2)(5.5)(28)](0.125)[155/ (12)3] = 51.2 lbs The total calculated weight is: W = 65.4 + 10.5 + 8.1 + 19.6 + 51.2 154.8 lbs Os = 3-7 i NuPac PAS-2 System Consolidated SAR Rev. O, Februsry 28, 1989 Ratio the calculated total weight to the assumed total weight a s f oll ows : -~ Q.) Calculated A~' Final Component Nodes Weight Weight Weight Outer Shell 2 65.4 10.7 76.1 Foam - Top 5,8,11 10.5 1.7 12.2 3ottom 4,7,10 8.1 1.3 9.4 Sides 3,6,9 19.6 3.2 22.8 Inner Shell 12 51.2 8.3 59.5 154.8 + 25.2 180.0 = Th e c apacit ance for each node in the outer overpack is summariz ed in the f ollowing table: ,m ( I </ Weight Specific Heat Capacitance 0 Node 11a t e ri al (1b) (BTU /lb-F) (BTU / F) 2 Steel 76.1 0.113 8.599 3 Foam 7.6 0.30 2.280 4 Foam 3.1 0.30 0.940 5 Foam 4.1 0.30 1.220 6 Foam 7.6 0.30 2.280 7 Foam 3.1 0.30 0.940 8 Foam 4.1 0.30 1.220 9 Foam 7.6 0.30 2.280 10 Foam 3.1 0.30 0.940 11 Foam 4.1 0.30 1.220 12 Fiberglass 59.5 0.28 16.66 bv 3-8 k i NuPec PAS-2 System Consolidated SAR ' Rev. O, Fsbrusry 28, 1989. Assume a composite specific' heat of .3 0 B TU/ l b F, and a weight of-500 . pounds.. The thermal capacit ance-of Node 13, the payload, is (500)(0.30)'= l-T 15 0.0 BTU /0F, -Radiation Heat Transf er (21 and R16)' 'The general' form f or. radiation resistor coefficient coupling of nodes 'i' to '.j' is ' t aken from. Equation 5-56 of Ereith: l k ) = oFgj g A i Where: o = 0.1714(10)~8 BTU /hr-ft _oR4 2 (Stefan-Boltzman constant) F (A - U.A, all external surfaces) ij = eg g j Fij = 1/[(1/e1 - 1) + 1 + (A /A )(1/c) - 1)] (concentric cylinders) g j Resistor R : g Resistor R1 provides ' the radiant portion of thermal coupling to the external environment from the package outer surf ace. For this geometry: Ag = n[(32)(48) + 2(16)2]/(12)2 = 44.68 f t2 j== (ambient) A i = 0.8 (per 10 CFR 71) c j = 0.9 (per 10 CFR 71) e

Then, 4

1 = [0.1714 (10)-8](0.8) (44.6 8) = 6.126 6(10)-8 BTU /hr OR R 3-9 1 NuPac PAS-2 Systen Consolidated SAR Rev. O, February 28, 1989 f ~' k Resistor R 3 16 l Resistor R16 Provides the primary radiant heat transf er between the inner shell of the outer overpack and the outer surface of the inner overpack. The-basic dimensions of the 55 gallon drum are assumed to be 22 inches diameter and 35 inches long. g = n[(22)(35) + 2(22/2)2]/(12)2 = 22.078 ft2 A A) = nl(24)(35.5) + 2(24/2)2]/ (12)2 = 24.871 f t2 1 * 'j = 0.8 8

Then, 16 = [0.1714(10)-8)(22.078)/[(1/0.8 - 1) + 1 R

+ (22.078/24.871)(1/0.8 - 1)] 4 = 2.5709(10)-8 BTU /hr OR Convective Heat Transfer (R ): 2 Resistor R; provides conv ective coupling between the outer surf ace of the out er overpack end the ambient. Assuming laminar flow of air, the film coef-ficients for convective heat t ransf er may be determined by utilizing equations from McAdams. Heat Transmission. 3rd Edition: For a horizontal plate with the heated surf ace facing upward (Equation 7-8d): cH = 0.27(AT/L)0.25 BTU /hr-f t _op 2 h ). 1 i. For a vertical cylinder (Equation 7-Sb): 1 h,y = 0.29( AT/L)0.25 BTU /hr-f t _op 2 O Assuming convective heat transfer over all but th e bo t t om s urf a ce ; i 3-10 E_______________________________._______________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _. _ _ _ _ _ _ - _ _ _ = _ - - _ - _ _ _ _ 1 NuPac PAS-2 Systea Cons olidated.SAR - Rev.. O, February. 28, 1989' 2 H = n(32/2)2 (12)2 = 5.585 f t / '. A y = n(32)(48) /(12)2 = 33.510 f t2 A 'Then, the composit e film 'coef ficient may be f ound as: h, = (((5.5 85)(0.27)/(32/12)0.25) [(33.510)(0.29)/ (4 8/12)0.25])/ (5.5 85 + 33.510) + (O'.20595)AT.25 O = l l The above form is - utilized. directly f or input into the comput er code THAN.. l Conductive Heat Transfer (R4-R15) The basic heat transfer mode between the inner and outer shells 'of the outer 3 . overpack is v'in conduction through the 3 lb/f t polyurethane foam. From 2 Se c t ion -3.2,. the f oam conduc tiv ity ut iliz e'd i s 0.014 2 BTU /hr-f t.oF. It is 0 assumed that the foam chars at a t emperature of 400 F. At '.this t empera ture, each foam conduction resistor will be replaced by an air conduction resistor of equiv alen t ge ome t ry. Radial conduction through a cylinder is given as: gj = in(rg/rj)/2n d R Axial conduction through a flat plate is given as: Rij = t/kA Where: r3 = outer radius, ft rj = inner radius, f t 2 k = f oam conductivity, BTU /hr-f t OF O 3-11 i luPac PAS-2 Systs:a Consolidated SAR Rsv. O, Fabruary 28, 1989_ j l l fm L = cylinder length, it \\ ) m; i t = plate thickness, ft 2 A = plate area, ft i ( Outer Overpack Sides (R4-R): 7 Heat transf er through the outer overpack sides is via radial foam conduction. The ef fective cy linde r length is given as 35.5 inches (2.958 f t). The table below summarizes the resistor values f or resistors R4-R-7 Resistor Nodes Radius Resistor Value Numbe r Out e r Inner ri rj ( F-hr/ BTU) 4 2 3 16.00 15.13 0.21357 (_,- 5 3 6 15.13 14.25 0.22631 6 6 9 14.25 13.38 0.24065 7 9 12 13.38 12.50 0.25694 Outer Overpack Bottom (R8-R11) Heat t ransf er through the outer overpack bottom is via axial foam conduction. The effective plate th ic kn es s is given as 6.0 / 4 inches (0.125 0 f t ). The resistor value for resistors Rg-Ryy is calculated as: l R8 = Psg = R10 = Ryy = 0.1250/ (0.0142)[n(24/2)2 (12)2) / = 2.8020 F-hr/ BTU l l I Outer Overpack Top (R12 - R15 h t { ( 3-12 l NuPac PAS-2 Systea C:ns olidstad SAR-Rsv. O, Februa ry 28, 1989 p Heat transf er through the out er ov erpack t op is via axial f oam conduction, bl The effective plate thickness is given as 7.5 / 4 inches (0.156 3 f t )..The is calculated as: resistor value f or resistors R12 - R15 R12 = R13 = R14 = R15 = 0.1563/(0.0142)[n(25/2)2 (12)2) / 0 = 3.2279 F-hr/B W Edge Closure (R ): 1 3 Th e e dge closure is of 0.125 inch thick molded fiborgiass for both the top and bo t t om h al v e s of the overpack. Th e me an conduction path length is approxi-mately 5.5 inches. For purposes of this analysis, assume axi al heat conduc-tion as the mode of heat transfer. 3 = t/kA = (5.5/12)/(0.25)(2(0.125)n[(24 + 32)/2]/(12)2) R = 12.005 0F-hr/B W iD) v' External Heat Lcading: 2 The insol ation onto the top of the outer overpack is given as 800 g cal /cm (2,950 BW/f t2) per 12 hours: = (2,7ed)[n(32/2)2 (12)2] = 16,476 BTU /12 hours / qtop Likewise, th e insolation onto the curved side of the outer overpack is given 3 (1,475 BTU /f t ) per 12 hours: 2 as 400 g cal /cm qside = (1,475)[(32)(48)/ (12)2] = 15,733 BTU /12 hours Therefore, the t otal ext ernal heat load per hour is: q, = (qtop + G sido) /12 = (16.47 6 + 15 3733) /12 = 2,684 BTU /hr l'\\ b 3-13 \\ p I NuPsc PAS-2 ' Syst em Consolidated SAR Rev.! 0, February 28, 1989: ~ r Internal Ht,at Loading: ( . qg = (3.0 watt s)(3.412 BTU /hr-watt) = 10.23 BTU /hr 3.4.1.2 Test Model ' Not applicabl e as no thermal tes ting f or normal. conditions of 't ransport,is. performed for the. NuPac PAS-2 packaging. 3.4.2 Maximum Tamneratures The maximum normal conditions of t ransport s teady-stat e nodal t temperatures, as directly output by THAN, are present ed below: $TEADY STATE PROBLEM TOTAL NUMBER OF NEWTON ITERATIONS s 7 NUMBER OF TEMPERATURE DEPENDENT INTERPOLAT30NS a 3 NO. OF NEHTON ITERATIONS FOR FINAL bPDt.1E a 1 CLASS 2 - TEMPERATURE, T ID DEGREES F ID DEOREES F ID DEGREt$ F ID DEGREES F 1 100.0000000 2 153.7563123 3 155.5263666 6 155.698710s 5 155.69s710s 6 157.4019639 7 157.6411093 8 157.6411093 9 159.3964306 10 159.5s35077 11 159.5s35077 12 161.5259062 13 161.9404477 The temperature at the center of the package may be conservatively estimated by assuming that the temperature at Node N13 is the sink temperature for heat flowing through two cylindrical resistors in series, and ignoring end eff ects. It may be further as sumed that the inner overpack foam fills the space between the inner overpack shell and the out side surface of the sample sh i el d. The high relative conductivity of lead and steel when compared to the polyure-thans result s in a relatively small thermal gradient be tween prima ry cont ain-mont and the inner overpack foam. From Equation 2-7 of Kreith, Princinles si 3-14 NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, fl989 1 Ihad; Transfer. First Edition, page 26, the gradient through the inner overpack ~\\m foam or:the sample shield.can be calculated by the following: AT = a ln(d d of ;). 2nkl L l Where: q = heat load = 3 watts = 10.2' BTU /hr> d L= out side diamete r' = 16.5 inches ( s ample. sliield) o

= 22.0 inches (inner overpack) di = in side di ame t e r = 3.75 inch e s ( sample shield).

16.5 inches (assumed f or inner overpack) = Lr length - 21' inches = 1.75 feet (sample shield, and assaned f or inner overpack) k' = thermal conductivity of le ad = 19 BTU Hr-ft OF of foam = 0.0142 BTU Hr-f t-F .O So, AT,, = 10.2 ln(16.5/3.75) =.073 F 2n (19) (1. 75) AT, = 10.2 ln(22.0/16.5) = 18.8 F 0 g 2n ( 0.014 2) (1.'75 ) In the steady state, then, it can be as sumed that the t emperature of the sample shield is es senti ally const ant. The t empera ture of the sample vial within the packaging, then is estimated to be less than: 0 12 161.9 + 18.b + 0.1 = 180.3 For air transport, 49 CFR 175.703 r equi res that the surf ace t emperature during 0 0 transport be les s enan 50 C (122 F). The NuPac PAS-2 packaging may cont ain up p to 3 watts of internal decay heat: ( i 4 3-15 J l \\ NuPac PAS-2 Syst en Consolidated SAR Rev. O, Februa ry 28, 1989 ) n (3 watts)(3.41 BTU /Hr/ watt) 10.2 3 BTU / Hr. t = (v): I Since transpor t within an aircraf t would eliminat e insola tion loads, this decay heat represents the total heat to be dissipated during transport. 0 If the ambient t empera ture is as sumed t o be 100 F, the surf ace temperature required t o dis sipat e 3 wat t s via convection and radiation, heat transfer may be calculated as f ollows: Convective heat transf er can be calculated by the f ollowing f ormula developed by McAdams and reported in Heat Transfer by Holman: q = hA(T, - T.) Where: = C(T, - T.)1/3 h .19 f or vertical cylindrical surf aces. C = C/ C .22 f or horizont al plunor surf a ces = A = Heated area for convective heat transf er. surf a ce t empera ture T = s T. = ambie nt t empe rature = 100 F q = heat flow Radiant heat transfer can be czpressed at q = cAE(T,4 - T 4) Where .1718 x 10-8 BTU /Hr-f t.2 oR4 o= (St e f an-Bolt zman const ant ) E =.8 (emissivity per 10 CFR 71) f' N Using the above expres sions, the total heat transfer, away from the surface of the NuPac PAS-2, may be calculated: 3-16 i i a NuPac PAS-2 ' Sys t on Cons olida t e d SAR : Rev. O, Februa ry 28, 1989. fm qt =.19A,(T, - T.)4/3 +.22 A'g(T, - T ) O + o(A,'+ A )E(T,4 'T,4) t Where-2 A, = Cylindrical side ' area = 'n( 32)(48) 33.5 ft =

144 2

2 A = Top surface are a = 21121 = 5.58 ft t 4(144) s 9; qt total heat flow,10.23 BTU /Hr f or the steady state. N = ' Solving the abov e expression f or T,, the surf ace t emperature,'as suming the 0 ambient t empera ture, Tg equals 100.0 F or 559.69 R, yields as surf ace 't emper-0 a t ur e of 100.24 F. This trivial incre ase in t emperature is not surprising considering the very low internal decay heat. , N It can be concluded that the surface t empera ture of the NnPac PAS-2 packaging 0 will not exceed 100.3 F during normal air. transport. 3.4.3 Mini =n= Temperatures 0 The NuPac PAS-2 packaging could be exposed to t empe ratures as low as -40 F. . Th e con t a in ed co ol an t sample would fre eze within the primary cont ainment should the package reach equilibrium under such conditions. Howev er, the la rge thermal capa cit ance of the shield and seconda ry cont ainment v es sel, coupled with the thermal resistance of the inner and outer overpacks means that the sample will not freeze f or many hours af ter the package is subjected to this environment. See Section 2.6.2 f or a dis cussion of the package per-0 formance'at an ambient t empera t ur e of -40 F. O 3-17 l NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 3.4.4 Maximum Internal Pressures The maximum internal pr es sure within primary containment (the sample vial)is 0 250 psi, corresponding to the partial pressure of water at 400 F, The sample vi al will not be subje ct ed to pres sures or t temperatures great er than these v al ue s. 3.4.5 Thermal Stresses Because the internal heat load in the NuPac PAS-2 sample vial is so low (only 3 watts), and the the rmal conductivity of steel and lead is so high relative to the foam in the inner and outer overpacks, thermal gradients developed in the vial, the sh i el d, or the s e conda ry con t ainment vessel are in si gnif ican t 0 (l e s s t h an.1 F). The calculations given Lbove predict a thermal gradient in the outer overpack of 161.5 - 15 3.8 = 7.7 degrees, and 18.8 de gre e s f or the more conservative These gradients, although suf ficient to cause minor thermal stresses in is o-G tropic me t al s t ru c t ur e s, would not indu ce si gnif ic ant stresses for the com-bination foam, fibe rgl as s and me t al inner and out er ov erpacks. The high flexibility of the foam will prevent significant stresses from developing. The primary cont ainment will be kept at a uniform temperature, and thus will not develop thermal stresses. 3.4.6 Evaluation of Packace Performance for Normal Conditions of Transnort It can be readily seen by the calculations presented above that the NuPac PAS-2 packaging will meet all the thermal requirements of the normal conditions of transport. 3.5 Hvoothetical Accident Thermal Evaluation This section pr e sc nt s th e the rmal analyses of the NuPac PAS-2 packaging for the hypothetical a cci dent fire condition specified in 10 CFR 71.73(c)(3). The initial t empera ture distribution in the package prior to the fire is t aken as 9 0 that corresponding to the 100 F steady state condition of Section 3.4, with-3-18 l I NuPac PAS-2 System Consolidated SAR' Rev. O, February 28,'1989 out ins ola tion, in ac cordance with 10 CFR 71.7 3(b). To det ermine the ef fect p 0 of the fire, the package is exposed to a 1,475 F fire f or a period of thirty 0 minutes at which time the thermal boundary is returned to a 100 F ambient air condition as specified in 10 CFR 71.7 3(c)(3). The transient analysis is continued f or a time suf ficient t o det ermine the maximum vslues. f or al l t em-peratures within the package. Those nodes not achiev ing a maximum' t emperature within a period of ten hours f ollowing the end of the fire have be e n s o no t ed. 3.5.1 Thermal Model 3.5.1.1 Annivtieni Model The analytical model used to evaluate the hypothetical accident condition was nearly identical to tha t des cribed in Section 3.4.1.1. Minor model modifica-tions were incorporated to account for accident condition damage as discussed in Sec tion 2.7. The ap pl i ca t io n of this damage to the thermal.model is c o v e r e d i n S e c t ion 3.5.2. N 3.5.1.2 Test Model Not applicable as no thermal testing f or accident conditions is perf ormed f or the NuPac PAS-2 packaging. 3.5.2 Packnee Conditions and Environment For conse rva tism, the ef fects of three (3) suc ces sive impact s on the overpack l l will be collectively imposed upon the thermal model and utilized f or the l~ hypothetical fire transient analysis. Each impact effect is represented as a single ' damage' resistor in parallel with the other elements of the thermal model, connecting between Nodes 2 and 12, as shown in Figure 3.5-1. l l 3-19 m - NuPac PAS-2 Syst em Consolidated SAR ' Rev. 0, Februa ry 28, 1989. i Top ; and Bot t om Corner Lnpact Damage (Rig:and'R19): Consider the f ollowing illustration to determine the ef fects of overpack l damage upon the - thermal analyses:

---

4

+ f- - r. I i IN b t _ __ h Q c a d- = l s n e { v '/ ( O Ab O 3-20

(. . NuPac PAS-2 Syst em Consolidat ed SAR - Rev. O, Februsry 28, 1989-Figure 3.5-1 Fire Accident Thermal Model Ambient N1 R1 R2 7 ottom Top B N2 eSid e j R4 R8 R12 Edge Closure-4tN3 R17 O jss jR9 ls13 Mid-Wall R3 4DN6 apN7 R18 t>N 8 R19 R6 R10 R14 t>N9 t>N10 <>N11 R7 R11 R15 inner Shell J N12 R16 Payload 6N13 0 3-21

+- 'NuPac PAS-2 System Consolidated SAR-Rav. 0, February 28,.1989: yg. The procedure f or de't ermining _ the ' damage' resist ors 'is as f ollows: l} 1)' : Calculate the end area

2). Calculat e the wedge volume-

3). Calculate the equivalent thickness reduction, volume /aren

'4) Calc ula t e the' foam' conduction resistor f or the -thinner section The end area Lis. the area of a circle,- ori 2 A = nr Where: . r = ef fective end radius f or the thermal. analysis The volume of an ungula may be f ound from the f ollowing expression: 3 V = c[(2e /3) - bA ]/a b C'D a=d-f c = ah/d b=r-a e = [a(2r - a)]0.5 2 Ab = r [a _(sin a)(cos a)] -1(b/r) a = cos .If R is the resistance of the undamaged section, R is the resistance of the d t -: damaged section, and R, is the equivalent resistance using the Parallel Resis-l tor Law, then: l n Rd = 1/[(1/R ) + (1/R,)] = (R R,)/(R g g g + R,) 3-22 t_. ______-__-__-__-_____--__D

?- LNuPac' PAS-2 Sys'tes Consolidated SAR' Rsv. O, February ' 28,1989f Rearranging, ls R, =~(k R )/(Rt -R), R from Section~3.4.1.1' gd d g (11.2080 f or bot t om, 12.9116 for top)' 'Where: Rd " t - At Rt"t At = V/A

Then, R /R = p = ( t - At) /t d t Substituting, 2

R, = R p/(Rt a g - E S) = R /(1 - ) Parameter Bottom Resistor (R18) Top Resistor (Ryg) .O-r 12.0 12.5 d 12.0 16.0 b 4.5 8.0 f 3.6875 3.50 a 8.3125 12.50 b 3.6875 0.0 c 3.1172 6.25 e 11.4194 12.50 A 452.39 490.87 0 0 a 72.104 90.00 A 139.108 245.437 b V-179.92 651.04 t 6.00 7.50 At 0.3977 1.3263 p 0.9337 0.8232 f R, R18 = 157.84 Ryg = 6 0.118 l 3-23

l NuPac PAS-2 Syst em: Cons olidated ' SAR Rev. O, Februa ry 28, 1989 i .D -Side Impact Damage.(Ry7): As same any:. localized of fect of the side latch is negligible and utilize the same techniques as above to determine resistor R17 ~ The irapact zone is assumed 'to have a length equal to the cylindrical overpack. The width of the impact zone is the leng th of the circ ula r s e gment;f ormed.- The volume of the circular segment is: 2 'V~= r 1[2p~- (sin 2p)]/2 'Jh e r e : -r = 16.0'in 1 = 4 8.0 in P p = cos-1[(r - 6)/r] O i 5 = 0.75 in The n, p = co s-1[ (16.0 - 0.75 ) /16.0] = 17.610 V- = (16.0)2(48.0) { (2np/180) - [ sin -2(17.61 )])/2 = 233.49 in3 0 Th e t o t al surface area of the overpack cylinder is: 2 A = 2nr1 = 2n(16.0)(48.0) = 4,825.5 in The. effective change in thickness, At, is: At = V/A = 23 3.49/4,825.5 = 0.0484 in Assuming the damage ef f ect s only the first ring of insulating foam (R ), the 4 total thic kn e s s, t, is 0.875 inches. The reduction coefficient, p, is: I 3-24 l

NuPac PAS-2 Systra Consolidated SAR Rev. O, February 28, 1989-t l 1) p = (t - At)/t = (0.875 - 0.0484) /0.875 = 0.9447 1

and, R17=R[ /(1 - p)] = 0.21357[0.9447/(1 - 0.9447)]

4 2 = 3.6485 STU/hr-f t _op 3.5.3 Packace Temperatures The maximum nodal temperatures for the hypothetical fire accident, as directly output by THAN, are presented in Table 3.5 -1, and Figures 3.5-2 and 3.5-3. The maximum temperature at the center of the sample shield can be conserva-tively es timat ed by applying the same thermal gradient calculat ed f or the normal condition. The actual gradient will be less that this value, since the thermally mas sive sample shield will not roact as quickly as the model pre-dicts, and the externally applied heat loads will actually serve to reduce the (] gradient. Under these as s ump t ion s, the maximum t empera ture of the sample vial r i U and payload under hypothetical accident conditions is 117.4 + 18.8 + 0.1 = 0 136.3 F. Likewise, the t empera ture of the vial at the start of the accident 0 is 108.6 + 18.8 + 0.1 = 127.5 F. 3.f.4 Maximum Internal Pressures 0 The maximum normal condition payload temperature of 180.8 F represents the h i gh e s t temperature exper ienced by the NuPa c PAS-2 pac ka ging. Since the hypothetical fire temperatures are l e s s than the normal condition t empera-tures, th e hypo th e t i c al ac cide n t condition is not the con t rol ling case. For t he NuPa c PAS-2 packa ging, the maximum t empe rature of the sampl e vial, 250 psi, occurs as a normal condition, at th e tine of loading. 3.5.5 Maximum Thermal Stresses Thermal stresses induced during the hypothetical accident condition are in- ,q signif icant f or the same re asons the normal condition thermal stresses are not j significant. See Se c t ion 3.4.5 f or a compl e t e expl ana tion. 3-25 - --- a

77, c 4 l} } 1 [ ^ NuPac PAS--2 Systsm Cons olida ted SAR Re6'0,' February 28,'1989 , [ f) ' A,_ . TABLE 3~.5 Hypothetical Fire Accident Temperature Time History ' Time (hr) . Node 1 Node 2 Node 6' Node 12 Node 13 '====================================================== 0.000 1475.000-100.240 -103.880 108.010 108.550 0.100 1475.000 1466.855z 148.006 109.028 108.556~ 0.200- 1475.000 1469.326 248.475 110.200 108.575-0.300 1475.000. 1470.592. -354.185 111.668 108.611 0.400 1475.000 1471.308 448.757 .113.616-108.C68 0.500- 1475.000 1471.758 528.989 116.104. 108.753-0.600 100.000 1267.719 579.687- '118.223 108.864 0.700 100.000 197.198 580.150 120.582 108.998 0.800 100.000 170.749 554.319 123.250 109.163 0.900 100.000' 156.010- '518.060 125.966 109.361 1.000 100.000 146.226 479.653 128.494 109.593 1.100-100.000" 139.147-442.790 130.674 109.856-1.200 100.000 133.765-408.860 132.424 110.144-1.300., 100.000 129.532 378.208-133.726 110.453 1.400 100.000 126.112-350.739 134.601 110.776 1.500-100.000-123.289 326.199 135.093 111.106 1.600- -100.000-120.914 304.292 135.259 111.438 1.700 100.000 118.886 284.731 ~135.156 111.768 1.800 100.000 117.131 267.249 134.838 112.092 1;900 100.000 115.597 251.611 134.355 112.407 - [\\ 2.000 100.000 114.246 237.608 133.748 112.710 2.200 100.000 111.976 213.795 '132.302 113.278 2.400 100.000 110.155 194.589 130.717 113.789 2.600 100.000 108.676 179.047 129.129 114.243 2.800 100.000 107.464 166.429 127.620 114.641 3.000 100.000 106.464 156.159 126.234 114.988 3.200 100.000 105.637 147.779 124.989 115.290 3.400-100.000 104.948 140.926 123.890 115.551 3.600 100.000 104.373 135.311 122.930 115.777 3.800 100.000 103.892 130.703 122.099 115.972 4.000 100.000 103.487 126.915 121.386 116.141 4.200 100.000 103.145' 123.796 120.776 116.288 4.400 100.000 102.855 121.225 120.257 116.415 4.600 100.000 102.609 119.102 119.815 116.526 4.800 100.000 102.399 117.348 119.441 116.622 5.000 100.000 102.219 115.896 119.125 116.707 5.200 100.000 102.064 114.693 118.856 116.782 5.400 100.000 101.930 113.695 118.629 116.848 5.600 100.000 101.814 112.866 118.436 116.906 5.800 100.000 101.713 112.176 118.272 116,959 6.000 100.000 101.624 111.601 118.133 117.005 6.200 100.000 101.545 111.122 118.013 117.047 6.400 100.000 101.476 110.720 117.910 117.085 6.600 100.000 101.414 110.384 117.822 117.120 6.800 100.000 101.359 110.102 117.745 117.151 7.000 100.000 101.309 109.864 117.677 117.179 7.500 100.000 101.204 109.418 117.542 117.241 l 8.000 100.000 101.121 109.119 117.438 117.290 0 8.500 100.000 101.052 108.913 117.354 117.330 9.000 100.000 100.995 108.765 117.284 117.363 9.500 100.000 100,946 108.656 117.221 117.389 10.000 100.000 100.903 108.571 117.165 117.410 3-26 1

l i

NuPac PAS-2 Sys ten Consolidated SAR Rsv. O, Februsry 28, 1989 e s-FIGURE 3.5-2

.lN.)'

C O

De -D D w .. = e T 1 6 O E 'M 2 .-C D Q 7 e w o D O p ? 1 k 8., J E h e s, .9 e = + 6 c-g k 5 5 E g = s 9 53 t N 4 2 Q =., 2 o c y O D ~ 'ei e O O 9 o. I 1 i i i i i i i i i i i i o o o O O O O 'O O O O O O O O O O 9 N N N N O. O. 9 I '. 9 N N 9 9 9 9 O O O O O O O O O O (spuesnoq1) ( (3-see.rzap) s.rnan.radtnel 3-27 1

n - _ _,____ _. - - _ _ _ -. NnPac PAS-2 Systen Consolidated SAR Rev. 0;. February 28,11989'. FIGURE 3.'S - . (.- %. C' o, O D 5' e x k N X-d- o C. 9 o e~ .c q. 5: d i ai e @ N i:.% 8 e eb - 9* o b 9 &6 o. ~ d e O = o-m n s o ~ s i n u o O O O O O O o o o o o o to C 4 n N (j-899JIOp) OJn1BJedu191 3-28

c. 1 11-1 l -NuPae' PAS-2, System Consolidated SAR Rev. O, -- Fobrua ry 28, 1989 J 1 i' l-l 3.5.6 Evaluation of Packane Performance for lV. Hvnothetien1 Accident Thermal Conditions l l It can be readily seen-by: the calculations presented above that the NuPac.' PAS-j

2. packaging will meet all: the ' thermal requirements of the hypothetical 'acci-den t conditions.

t l I' Y 3-29 i

L NsPac PAS-2 Systes Consolidated - SAR Rev.' 0, February 28, 1989 1 f 5 l - (, 4.0 CONTAINMENT l 1 i 4.1 Containment Boundaries 4.1.1 Containment Vessels l' 1 The NuPac PAS-2 ' packaging provides two levels of leak-tight containment in two l conf igura t ion s. In bo th configura tions, the _ primary. cont ainment ' is provided by the stainles s steel sample vial, which is' leak tes ted to a leak rate less than-1x70-7 st anda rd cubic ceritime t e rs pe r second (scc /sec). Leak tight secondary containment (also tes ted to a leak rate les s than 1x10-7 scc /sec) is provided by the. sample. shield cavity in one configuration and by the optional secondary containment vessel in the other configuration. In this second configuration. the sample shield cavity is t ested to a leak rate les s than 10-3 sec/sec and is therefore pres sure-tight 4.1.2 Containment Penetrations There are four penetrations into the sample shield cavity other than the shield closure plug: two valve operators and two vial plugs. All pene trations are long naval brass shaf ts bore-sealed within stainless steel sleeves. The upper vial plug is fitted with ~ a test port for le ak and pr es s ure testing the shield cavity. The test port is se al ed with a Parker St at-0-Se al 0-ring, or eq uiv alen t. The optional secondary containment vessel is also penetrated by a test port in the lid; again, se al ed with a St a t-0-Se al or equiv alen t. The lid seals to the secondary containment ves sel body with an 0-ring bore seal, and is secured by eight S/16-inch bolt s. ck 4-1 ) l

i NuPac PAS-2 Systea Consolidated SAE ' Rev. O, February 28, 1989 4.1.3 Seals and Welds i Seals af fecting containment are as described above. All containment welds are i test ed 'non-destructively 'and leak t ested to verify their integrity. 4.1.4 Closure Closure on the optional secondary containment ves sel is ef fect ed by eight 5/16-inch bolt s tightened to 18 f t-lb. t orque.. The shield closure. plug on the sample shield is held in place with four 1/2-inch bolt s tightened to 75 f t-I b s. The sample vial plugs employ pipe threads f or closure, therefore, th e s e plugs shall be hand-tight for transit. 4.2 Econirements 191 Normal Conditions d Transnort 4.2.1 Release d Radioactive Material The result s of analysis performed in Chapters 2 and 3 indicate that there will .() be no release of radioactive materials under any of the normal conditions of t ran spor t. 4.2.2 Pressurization d Containment Vessel The sample vial is t es t ed t o 150lb of the highest pressure anticipat ed under any r.ormal or accident conditions. There are no vapors or gases formed which could mix explosively within the sample vial. 1 4-2

1 NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 Should a leak develop in the sample vial, the payload could be f orced ont O unde r pres sure and could f lash t o s t eam. However, the exces sively large thermal mas s provided by the shfeld and the large surface area for heat exchange provided by the l e ad shot within the shield cavity ensure that the t empera ture of th e st e am will no t exce ed the equilibium t empera ture of the l 0 packa ge, or 237 F. Th e ab s ol ut e pres sure of sa turat ed s t e am a t this t emp-erature is les s than 25 psia, or only.70 atmospheres gage. The sample shield cavity is l e ak tested at one atmosphere, so a sample vial rupture at maximum design t emperature and pressure would not exceed the pressure required to test for l e ak tightness. i 4.2.3 Containment Criterion The NuPac PAS-2 packa ging sys tem will be subjected to assembly verification leak tests of the sample shield and the s e conda ry cont ainmen t vessel if present. Thes e t ests chall be performed per the requirement s of Chapt er 7. In addit ion, the Sample Shield, the Se conda ry Cont ainmen t V es s el, and the O Sample vial sh al l be subj e c t ed to Fabrication Verification and Maintenance Leak Test s per the requirement s of Chapte r 8. These tests shall verify that bo th prima ry and s e condary cont ainment bounda rie s a re l e ak-t ight t o be t t er than 10-7 SCC /sec. 4.3 Containmagt, Reanirements 1,gr ihr Ilvoothetical Accident Conditions Drop t es ts and thermal analyses presented in Chapt ers 2 and 3 indica t e that th e con t ainmen t boundaries will suf fer no damage from the hypothetical acci-dent conditions. Therefore, all contents shall be compl e tel y cont ained throughout the en tire hypothe tical ac ciden t s ce na r io. O 4-3

_ _ _ - _ _ _ =_. _ _ _ _ _ - _ - _ _ - _ -. _ - .NuPac P' S-2' System Consolidated EAR ' Rev. O, February 28,,1989" A O-4.3.1 Flasion Ag1 Products The quantity of fission gases in the primary containment vessel, available for rolease is in si gnific ant. i O O l 4-4

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 4.3.2 Release d Contents Decause no damage is incurred to the containment s tructures f rom the hypo-thetical accident scenario, there will be no release of radioactive materials to the environment during or af ter this s ce nario. 4.3.3 Containment criterion See Section 4.2.3 above. 4.4 Sgg.gifi Reanirements I The NuPac PAS-2 packaging utilizes two con t ainmen t boundar ie s that are leak-tight, as dis cussed abov e. None of the normal or hypothetical accident co ndi t ion s af fect th e ability of these bounda r ie s to perf orm as designed and tested prior to shipment. O O 4-5

i NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 5.0 SHIELDING The payload f or which the NuPac PAS-2 is designed is given in Table 5.0-1. Th e s e isotopes can be grouped int o groups according to g amma emission energy levels. The resulting grouping with their concentrations are given below: MAXIMUM ENERGY CONCERTRATIQH (Mev.) (C1/cc) l 0.4 1.6 0.8 1.3 1.3 1.2 1.7 .45 2.2 .25 2.5 .2 As3uming an ef f ective shield thickness of approximately 6.3 inches of lead and 9 assuming the source to be a line source 6 inches in length, a dose contribu-tion from each of the energy groups above can be calculated. The resul ting sum is 9.5 mR/hr a t 6 feet from the surface of the package. The dose rate calculated includes several areas of con se r va t i sm. First, the lead shot was not included in the shielding calcul ations, nor was the small amount of self sh i el ding provided by the wat er in the vi al. Se cond, many of the isotopes given in Table 5.0-1 hav e relatively short half-lives, on the order of one hour or les s resulting in a shipping payload of les s activity than the initially collected payload. Third, in classifying the isotopes into energy g roup s, th e gamma energy level was rounded upward to the next hi gh e s t energy group, thus increasing the calculated payload activity. These calc ula tion s wer e me an t only t o verify the adequacy of the design. Prior to any shipment, dose readings will be taken to verify that the packa ge neets transport limit s given in 49 CFR 173. O 5-1

NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 TABLE 5.0-1 O NUPAC PAS-2 MAXIMUM PAYLOAD CONCENTRATIONS (CURIES /CC) Nuclide Nuclide Nuclide BR-84 4.5 9 E-0 2 RU-106 2.64 E-04 IE-135 1.4 8E-01 BR-85 6.4 3E-02 TE-129M 3.4 4E-0 4 CS-135 3.6 9E-10 ER-85M 1.27E-01 TE-129 1.05 E-0 3 CS-136 5.72E-06 ER-85 2.08E-03 TC-99M 7.2 9E-0 4 XE-137 5.78E-01 ER-87

2. 39 E-01 I-129 3.34E-09 CS-137 1.3 3E-0 4 ER-88 3.5 0E-01 I-131

1. 4 4E-01 XE-138 5.75E-01 RB-88 3.53E-03 IE-131M 1.98E-03 CS-138 6.55E-03 ER-8 9 4.54E-03 TE-132 4.27E-03 CS-140 5.81E-03 RB-89 4.69E-03 1-132 2.14E-01 LA-140 6. 2 6E-0 3 SR-89

4. 6 6E-0 3 TE-13 3M 3.443-03 BA-143 5.14E-03 SR-90 2.96E-04 TE-133 3.6 3E-0 3 LA-143 5.81E-03 Y-90 2.96E-04 I-133 3.31E-01 CE-143 5.81E-03 SR-91 5.72E-03 XE-133 6.3 3E-01 PR-143 5.81E-03 Y-91M

3. 3 7E-0 3 CS-134 3.31E-05 CE-144 4.05E-03 Y-91

5. 75 E-0 3 TE-134 6.81E-03 PR-144 4.05E-03 NB-95 6.10E-0 3 I-134 3.85E-01 ZR-95 6.01E-03 MD-99

6. 07 E-0 3 I-135 3.0 3 E-01 RU-103 2.95E-03 XE-135M 1.77E-01 O

O 5-2

NuPac PAS-2 System Consolidated SAR Rev. O, February 28, 1989

6.0 CRITICALITY EVALUATION

The NuPac PAS-2 packaging will not contain significant quantities of fissile cm.terial; theref ore, this section is not applicable. l O i O 6-1

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 7.0 OPERATING PROCEDURE 7.1 Operational Reanirements (unless otherwise noted) 7.1.1 During all as sembly operations, the face se al 0-rings on the f il l tube s (Part No. GF-20-02D-A2) as well as the shield cl o sure plugs shall be wiped clean. Vacuum grease shall be sparingly applied to the 0-ring groov e prior t o mounting the 0-ring. The 0-ring shall then be mounted in the 0-ring groove. I 7.1.2 To prevent accidental or inadvertent spillages, the actuator rod j closure plat e shall be installed at al l times while the system is not in use, and shall also be installed at any time the sys tem is t r an s por t e d. 7.1.3 Flow path through the valve is indica ted by arrows on the valve o pe ra t o rs. To alter the flow path through either valve, ro t at e the 0 o pe rator 180 and continue ro tating until cperator cannot ro tate 9 f ur the r. Then turn operator back to vertical, with arrows pointing the desired direction. See Figures 7.1.3 -1 and 7.1.3-2. O 7-1

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 7.1.4 Th e shield assembly may only be lifted using the hoist ring on the 9 top of the shield. 7.1.5 The loaded packaging shall not be allowed to freeze during the life of the package. If the sample vial is suspected to have frozen while loaded with any aqueous cont ents, the vial shall be replaced I bef ore f urther u se of the packaging. i 7.2 Onerationni Narrative l 1 7.2.1 St orage Procedure l When not in use, the system shall be stored as follows: 7.2.1.1 The PAS-2 cask syst em shal l be stored complet ely as sembled in close proximity to the PAS sample location. All unpainted surf aces of secondary containment vessel sh al l be kept coated with a high quality vacuum grease to prevent oxidation and to G assure a tight se al when in use. The 8 se conda ry cont ainmen t vessel lid bolt s shall not be installed at any time the sample shield assembly does not contain a sample. 7.2.1.2 The sample shield transportation cart, required tools and parts shall be st ored in the same location as the PAS-2 cask. 7.2.2 Filling Procedure 7.2.2.1 Remove the sample shield assembly from the s e c o nd a ry con t ainmen t vessel. 7.2.2.2 The shield assembly shall be positioned on a cart in such a way that the fill port s are positioned conveniently with respect to the PAS sampling ports. 7.2.2.3 The fill tube s (Part No. GF-20-02D-A3) shall be ins t all ed as G pe r s e c t ion 7.1.1. 7-4 K _ _ _ _ _. _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _. _ _ _. _. _ _ _ _ _

j NuPac PAS-2 System Consolidated SAR Rev. O, Februasy 28, 1989 7.2.2.4 Modified eye-bolt s shall be inst alled in the top of the shiel d body. 7.2.2.5 Remove the actuator rod closure plate. 7.2.2.6 Set th e v al ve s u sing th e pro ced ur e in Pa r agr aph 7.1.4 abov e, such that the arrows indicate flow through the sample loop. 7.2.2.7 Position cart and shield assembly so that the pig-tail assemb-lies may be easily attached to the PASS ports. Attach pigtails to the appropriat e f it ting. 7.2.2.8 Run th e cool ant through the sample loop f or a period to be de t ermined s o tha t the inte rnal t empera tures of the vial is very clo se t o the t emperature of the cool ant and a represen-ta tive sample may be t aken. 7.2.2.9 Se t t he val v es, u sing the pro cedure in Pa ragr aph 7.1.4 abov e, out f low valve firs t, so that the arrows indicat e flow through the flush (bypas s) loop. 7.2.2.10 Shut down re a c t or co ol an t f l ow t o the NuPa c PAS-2 Ca sk. 7.2.2.11 Direct non radioactive flush water through the sample vial. Flush f or several minutes. 7.2.2.12 Install actuator rod closure plate. 7.2.2.13 Direct a compressed gas source through the vial. The gas should not be pressurized t h ro u g h the vial to a pressure greater than 250 psi. 7.2.2.14 Allow gas to flow until passages are dry. G 7-5

NnPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 7.2.2.15 Remove pigtail as semblies and fill tubes. De s ure tha t the 8 fill tube 0-rings are on the tubes af ter removal. 7.2.2.16 In s t al l sh i el d c l o s ur e p l u g s pe r Pa r a g r a ph 7.1.1. 7.2.2.17 Transport shield assembly on cart to the partially assembled overpacks. 7.2.2.18 Perform Leak Test LT-16 on the sample shield to verify assembly of the sample sh i e l d. 7.2.2.19 If the optional se conda ry cont ainme nt vessel is used, this se conda ry cont ainment ves s el shall have bee n verified t o be leak-tight t o be t t er than 1x10~7 sec/seo at it s most recent maint enance helium leak test, which shall have be e n performed not more than one year prior to use. If the secondary contain-men t v es s el is no t t o be u sed, skip t o s t ep 7.2.2.19. 7.2.2.20 Place the secondary containment vessel body in the inner over-pack. 7.2.2.21 Place the sample shield in the se conda ry containment vessel. Sec ur e the secondary con t ainmen t vessel lid with it s 8 bolts. Bolt s should be torqued to 18 f t-lb. 7.2.2.22 Perform the applicable part of LT-16 on the se conda ry cont ain-ment ves sel (the section entitled ' Assembly verification l e ak test of the Optional Secondary Containment V es s el'. 7.2.2.23 In s t al l shoring within the inner overpack as requi red to pr e-ven t exces siv e mov emen t of the shield rela tiv e t o the inne r overpack during shipping. O 7-6

NuPac PAS-2 System Consolidated SAR Rev. O, Februa ry 28, 1989 7.2.2.24 Place the top foam piece into the inner overpack. Secure the 9 inner overpack closure devices. NOTE: No shoring is required between the inner and outer ovorpacks. 7.2.2.25 Install the upper portion of the outer overpack and secure. 7.2.3 Emptying Procedure 7.2.3.1 Remove the covers of the outer and inner overpacks, and the se conda ry cont ainmen t vessel cover, if the optional s e co nda ry containment vessel is used. 7.2.3.2 Remove shield assembly and place where vial is t o be emptied. 7.2.3.3 Remove shield closure plugs and install Fill Tubes. See Para-gr a ph 7.1.1 a bo v e. 7.2.3.4 Connect upper fill tube to a source of pres surized gas and G lower fill tube t o a t es ting st orage t ank. Pr es s ur e shall not exceed 250 psi. 7.2.3.5 Af t er removing the val ve ope ra tor cover, turn upper valve operat or t o the sample loop, then se t lower valve operator to the sample loop, thus releasing the sample into the t es ting storage tank. See Paragraph 7.1.3 above. 7.2.3.6 Af ter entire sample has been transf erred into the storage tank, redirect the flow from the lowe r fill tube into the f acility waste water system. l 7.2.3.7 Attach the upper fill tube t o a source of demineralized water. O 7-7

l NuPac. PAS-2 Sys tem Consolidated SAR - Rsv. 0, Fobruary 28, 1989 l, - g [. ~ 'p: 7.2.3.8-Flush,the. sample-loop with water f or sufficient time to remove ' [\\ M, any contamination from the inside. of the system. .7 2.3.9 . Redirect the pressurized gas through the sample ' loop to dry the vial. 7.2.3.10. Rese t the valve. operators to the flushi-loop and reinstall 'the valve operator cover. 7.2.3.11' Redirect the source of. water through the' fill tubes and f lu sh.- for 30 seconds. 7.2.3.12 Again direct _the pres surized gas through the fill tubes until pas sages are dry. 7.2.3.13 Disconnect the fill tubes and remove from the shield assembly. f 7.2.3.14 Reinst all Shield Closure Plugs. Se e Pa r a gr aph 7.1.1. ~ $. 7.2.3.15 Pe rf orm steps - 7.2.2.15 through - 7.2.2'.21, except that l e ak t es t-ing to verify as sembly are not required. \\ 7-8

i 'NuPac PAS-2 Systen Consolidated SAR Rev. 04 February 28, 1989 l t 3 j 1 I 8.0 - ACCEPTANCE TESTS AND. MAINTENANCE PROGRAM U 8.1 Accentance Tests Prior to the firs t use of the packaging, the tests and evaluations called out on the General Arrangement Drawings, (Appendiz 2.10.1 and 2.10.2) shall be performed. Shield integrity shall be verified using the gamma scan procedures described in Appe ndix 8.3.1. Weld integrity on the sample vial shall be demonstrated by subj ecting it to an internal pres sure of 375 psi f or 5 minut es, af t er which the welds sh all be visually inspected for any si gns of def ormation.

Then, both the sample vial 'and the sample shield shall be Icak tested to demonstrate a le ak rat e of les s than 10-7 st andard cubic centimeters per second. If the secondary containment vessel is used, the sample shield shall have a verified leak rate less than 10-3 soc /sec, and. the se conda ry cont ainment " v es sel shall be verified to 10-7 scc /sec.

Acceptance tests for the outer overpack are listed below: 1. The entire outer overpack, both inside and out, sh al l be visually inspected and assured that it has not been significantly damaged (no cracks, punctures, hol es, nor broken welds). 2. The exterior stencils must be in place and ledgible. l 3. Toggle clamps and gasket s mus t be present and free of defects. l 8.2 lia.in t en a n c e Prorram General maintenance procedures are as follows: D 8-1

_ = _. .m LNuPac FAS-2.Sys ten Consolidat ed SAR - Rsv. O, Februsry 28, 1989 Painted Surfaces 'YJ j A. Ps"inted surf aces may be wiped clean using standard chemical solutions and' procedures. B. ' Chipped or scratched surf aces shall be repainted as.follows: 'd 1. Remove rust or loose coatings and sand edges.so they fair into sound coating. 2. Apply two coats Mobil Chem 89W9 or suitable equivalent to bare surfaces, f ollowing manuf acturer's recommendations. Unnainted Surfaces A. Unpainted non galvanized carbon steel surf aces shall be coated with a generous coat of high quality vacuum grease. These areas include: O 1. 0-ring glands on the Secondary Containment Vessel lid and body. 2. Secondary Containment test p or t. 3. Valve operator recess on side of sample shield. B. . Vacuum grease shall be removed and replaced yearly. Grease may be re-moved using solvent s recommended by the manuf acturer of the grease. All 0-rings shall be removed prior to the use of any solvents. Fasteners All threaded parts shall be inspected yearly and af ter each use for deformed or stripped threads. Any damaged parts including rivets, sh al l be replaced prior to further use. 8-2

Nurac PAS-2 System Consolidated SAR Rev. O, February 28, 1989 3.rJL1.s. All 0-rings and gasket s shall be repl aced annually except on the outer over-pack. Ad di t ional l y, the silicone flat gasket sealing the shield plug in the sampl e shield shall be repl aced ev ery time the plug is remov ed. Scaling surfaces and 0-ring glands shall be inspected for rust, chip s,

burrs, scratches, etc., at the time of seal replacement.

Immediately f ollowing seal r e pl a c eme n t, the sample shield and secondary cont ainment vessel shall be leak tested to the requirement s of LT-12 (Appe ndix 8.3.2). Lend-Vermig;111t e Filler The lead shot and vermiculite mixture shall be replaced yearly to insure the vermiculit e's absorption capabilities. The f ollowing procedure shall be used: 1. Remove old sho t and v ermiculite by inv erting the shield with the shield closure plug removed. A nylon choker strap is r e c omme nde d. Shield cavity and sample vial must be meticulously cleaned prior to any helium leak testing. Foreign material will render such a test impossible. 2. Measure out 350 to 375 cubic centimeters of comme rci al v ermiculi t e and grind int o a fine powde r. Powder shall be fine enough to pas s through a 12 strand per inch wire s creen. Vermiculit e shall contain l es s than 10% moisture by weight. 3. Mix ground vermiculit e thoroughly with enough lead shot to fill the shield cav ity. 4. Carefully pour the mixture into all spaces within the shield cavity and fill to the upper edge of the c av i ty. 5. Replace shield plug. 8-3

NuPac PAS-2 Systen Consolidated SAR Rsv. 0, Februsry 28,-1989 ] Onter Overnack \\_5 A good sound industrial maintenance program should be f ollowed to' as sure the integrity of the out er overpack. Components such as gaskets, toggle cl amp s, and component s neces sary. f or the saf e and easy operation of the packaging should be given regular inspection and repaired or replaced as necessary. i As a mini mum, gaske t s shall be repl aced with new gaske t s me eting the des-cription on the drawing (See Appendix 1.3) yearly (sooner if visible wear is detected). To ggl e cl amp s mu s t - work f r e e. Lubricate as required and replace if clamps are bent or damaged to the extent that proper la tching would be impaired. Valve Onerators Valve operat ors shall be checked f or free operation immediately following replacement of the lead-vermiculit e filler. Operators shall be turned through 1 their complete range of movement three times to verify free movement. If any a bn ormal resistance to movement exists, or if the operator c anno t be' turned through its entire range, contact the manuf acturer of the sample shield (Nu-clear Packaging, Inc.) f or direction t o correct the malfunction. O 8-4

, NuPac PAS-2 System Consolidated SAR. ' Rev. 0, ' Februa ry 28, 1989 8.3 APPENDII APPENDIX 8.3.1 DISCUSSION.QE GAMMA j. Cati PROCEDURE Lead shielding int egrity shall be confirmed via gamma scanning. There~are two gamma s can t echn'iques. ut ilized. The main dif ference is in the me thod utilized to det ermine acceptance cr it e ri a. Both Gamma Scan Techniques are exactly the same in all other respects and are conducted as f ollows. An Eberline E120 probe or equivalent is used to scan the outer surface of the cask while an Iridium 192 or Cobalt 60 source of sufficient strength is present.in the conter of the cask. The source is firs t pl aced on the bo ttom-of the cask while the surface is scanned around its circumference parallel: to the source. The source is then moved up a pre-determined dis tance and the circumference s canned again. This s eque nce is repeated until the entire cask surface is scanned. O For these t est s, the cask' surf ace is gridded (in this case the grid consist s of 4 inch squares) and a chart is made to reflect the gridded cask surf ace. -Readings are t aken from each grid square by scanning every point in the grid and recording the maximum reading in the corresponding grid on the chart. ' This data then serves as the raw gamma s can result s. All readings are in Mil liroent gens (MR). The readings are evalua t ed by comparing them to predetermined MR values for nominal, or as designed, lead thickness and nominal -10% lead thickness. Th e two different methods utilized to determine acceptance criteria are dis-cus sed bel ow. The Laboratory Calibration Method (NuPac Procedure GS-001) utili.tes t es t blocks of the cask wall made up of lead and ste el she e t s. Th e t e s t b l oc ks simul at e nominal or as de signed and -10% l ead thicknes ses. The s ource is placed behind the t es t bl oc k a t a distance eq ual to the inside radius of the 8-5

NuPa c PAS-2 Sys t e= Cons olida t ed S AR Rsv. O, February 28, 1989 cask. The probe is then placed on the out side of the t es t block and readings ,.3 (_) are taken. This s eque nce is repeat ed on the nominal and -10% t es t blocks and th e da t a is recorded. The res ul t ant values are then a v eraged. A ratio of the values is also de-veloped. Then the average value is multiplied by the ratio. Th e v al ue s o derived is the maxinmm acceptable value for the shielding to be inspected. The Field Calibration Method (NuPac Procedure GS-022) utilizes a specially f abricated t est lid which incorporates a holder f or various lead and steel sho e t th ic knes s e s. This fixture is inst alled onto the cask to be s canned. The test lid is then set up to simulate the nominal lead thickness, the source is placed bel ow the t es t lid in the cask at a distance equal t o the inside radius of the cask. Re adings are then t aken. The t es t lid is then se t up to recreate the -10% lead thicknes s co nfi gura t ion, and readings are again t a ke n. Other readings are then taken in 1/8 inch l e ad thickness increments be tween and beyond the two base readings until f our to eight readings are obtained. (' The data is then plotted on a chart of readings versus lead thickness. The k value f or nominal lead -10% is then utilized as the maximum acceptable reading during the actual gamma scan. O 8-6

Appendix 8.3.2 PMEKREING A Pacific Nuclear Company NUPAC PAS-2 MAINTENANCE HELIUM LEAK TEST PROCEDURE LT-12 Rev. 2 i l February 2, 1984 /7 /' M U4k

• W.

Prepar ' By Date V /C vsn / Engineering / Date ( I Quality Assurance Date ~ Manufacturing / Production Date O N Other Date /, W rh' ex w 8-6a 2-/S -8$ \\ l Document Control / Release Date

I LT-12, Revision 2 February 2, 1984 LA SCOPE This procedure describes the requirements for performing a helium leak test on the NuPac PAS-2 Post Accident Sampling Cask system. M REFERENCE DOCUMENTS 2.1 ANSI N14.5 Leakage Test on Packages for Shipment of Radioactive Materials. 2.2 QP-5 NuPac Quality Procedure, Quality Planning. 2.3 QP-6 NuPac Quality Procedure, Inspection and Verification. 2.4 QP-7 NuPac Quality Procedure Discrepancy Reporting and Control. i NOTE: If this test is performed by an organization other than Nuclear Packaging, Inc., the appropriate equivalent quality procedure dictating quality.

planning, inspection and verification of the performing organization may be utilized in place of QP-5, QP-6 and QP-7 M

REQUIREMENTS 3.1 Leak dgtector shall be capable of detecting a leak of 5 x 10-standard cubic centimeters per second or smaller. M PROCEDURE M Sample Vial Leak Test 4.1.1 Calibrate leak detector,according to manufacturer's recommendations, such that thg leak detector sensitivity is 5 x 10-standard cubic centimeters /second (scc /sec) or better. 4.1.2 Clean the sample vial and the sample shield so that they are free from all foreign materials such as dirt, grease or oils. Remove lead shot and vermiculite from sample shield cavity. l l 4.1.3 Set the valve such that the flow direction through both valves is directed through the F large sampling cavity (a r r o ws pointing l opposite each other). I 4.1.4 Install a plug (GF-20-02D-A3) in one flow port on the vial. j 0-7

LT-12, Revision 2 February 2, 1984 t (m. ,-) 4.1.5 Using appropriate' fittings attach the lea'k ' detector to the other flow port on the~ sample vial.. 4.1.6 Evacuate sample vial cavity for one hour, or until vacuum is sufficient to operate the leak detector. according. to manuf acturer's recommendations. Note any adjustments made to the connecting fittings required to achieve this. 4.1.7 Envelop the. sample vial as assembled in plastic ~and fill the enclosed space with helium taking care to purge all other gases from any pockets or cavities adjacent to the sample vial. 4.1.8 Determine the leak rate of the system using the leak detector manufacturer's recommendations and so note. If leak rate of the systep 'is determined to 4.1.9 be greater than 1 x 10-sec/sec, inspect system for cleanliness and tightness of connecting fittings. Return to step.4.1.6 above. Continue testing until the vial passes the test or it.is apparent that the system cannot be made to be leak-tight to the indicated level. Note the best system leak tightness observed. 4.1.10 Release vacuum and disassemble from leak detector. 4.2 Sample Shield Leak Test 4.2.1 Calibrate leak detector according to the manufacturer's recommendations, such leak detector sensitivity is 5 x 10~8 scc /sec or better. 4.2.2 Clean the sample vial and the sample shield so that they are free from all foreign materials such as dirt,

grease, or oils.

Remove lead shot and vermiculite from the sample shield cavity. C'J 8-8

LT-12, Revision 2 February 2, 1984 '] 4.2.3 Install vial plug (GF-20-02D-A3) in lower / port of sample vial, sealing the lower. port x shield penetration. Install the' testable vial plug (GF-20-0 2D-A13) in the upper port of the sample vial, sealing the upper port shield penetration. Install the sample shleid plug and seal plate and tighten the plug to insure a seal. 4.2.4 Using the test port adapter and appropriate fittings attach the leak detector to the test port fitting on the testable vial plug. 4.2.5 Evacuate sample vial cavity for one hour, or until vacuum is sufficient to operate the leak detector according to the manufacturer's recommendations. Note any adjustments made to the connecting fittings required to achieve this. 4.2.6 Envelop the sample shield in plastic and fill the enclosed space with helium, taking care to purge all other gases from any pockets or cavities adjacent to the sample shield. 4.2.7 Determine the leak rate of the system using (q ' ') the leak detector manufacturer's recommendations and so note. 4.2.8 If the leak rate of the system is determined 10-7 sec/sec, to be greater than 1.0 x inspect sytem for cleanliness and tightness of connecting fittings. Return to step 4.2.5 above. Continue testing until the shield passes the test or it is apparent that the system cannot be made leak tight to the indicated level. Note the best system leak tightness observed. 4.2.9 Using appropriate fittings, flood the sample shield cavity with helium to a pressure of 15-20 psia. 4.2.10 Quickly remove the test port connections and install test port closure bolt with its Stat-0-Seal. Sample shield is now filled with helium. 4.2.11 Re-install the test ports adapter and evacuate so that a vacuum is created on the outside of the Stat-O-Seal and closure bolt. 8-9

LT-12, Revision 2 February 2, 1984 4.2.12-Determine the leak rate of the Stat-0-Seal using the leak detector manufacturer's recommendations. If the leak rate of th 10-9 Stat-O-Seal is greater than 1.0 x sec/sec, inspect the Stat-0-Seal and its sealing surfaces for cleanliness and integrity. Return t o-s t e p 4.2.9 above. Continue-testing until the Stat-0-Seal passes the test or it is apprent that the seal cannot be made leak-tight to the indicated level. Note the best seal leak tightness observed. 4.2.13 Release vacuum and disassemble test port adapter from test port. Reinstall lead shot and vermiculite. l 4.3 Leak Test EgI Optional Secondary Containment Vessel 4.3.1 Install 0-ring on the lid of the secondary containment vessel. Install the lid onto the body of the secondary containment vessel and secure with the proper bolts. ,m () 4.3.2 Install the test port sampling tool in the test port on the lid. Attach to the leak detector using appropriate fittings. Using sampling tool, adjust test port closure bolt such that the stat-o-seal does m seal. 4.3.3 Evacuate the system for one hour or until vacuum is sufficient to operate the leak detector as per manuf acturer's recommenda-tions. Note any adjustments made to the connecting fittings required to achieve this. 4.3.4 Envelope the secondary containment vessel in plastic and fill the enclosed space with helium, taking care to purge all other gases from any pockets or cavities adjacent to the vessel. 4.3.5 Determine the leak rate of the system using the leak detector manu f ac tu re r's recommenda-tions and so note. to be greater than 1 x 10-f tem is determined If the leak rate of the sy 4.3.6 scc /sec, insper. system for cleanliness, tightness, and proper -s[V assembly. Retu r n to s tep 4.3.3, above, and i continue testing until the vessel passes the test or it is apparent that the system cannot be made leak-tight to the indicated level. 8-10

LT-12,--Revision 2' February 2'_'1984 r Note the best leak tightness ' observed.- The 1]m = observed leak rate.shall meet the. acceptance ~ criteria of - paragraph 5.2. 4.3.7 Using the sampling tool-handle, adjust the Test Port Closure Bolt such that.the stat-o-seal is properly seated. 4.3.8 . Release the vacuum to theLsampling tool. 4.3.9 Connect sampling' tool to a helium source, taking care to adequately seal conne'cting fittings'to prevent significant leakage.of airLinto the system. 4.3.10_ Adjust test port closure bolt to allow f ree passage of helium into the Secondary Contain-ment Vessel. 4.3.11 When the internal pressure of the system reaches one atmosphere, again' adjust the Test Port Closure' Bolt so that the stat-o-seal is properly seated. 4.3.12 Disconnect from helium. source and reconnect to the leak detector. d 4.3.13 Perform steps 4.3.3, 4.3.5 and 4.3.6. 4.3.14 Release vacuum and disassemble from leak detector. M ACCEPTANCE CRITERIA 5.1 An inspection report shall be prepared _in accordance with QP-5 and QP-6, describing the system and giving the part names and numbers for each component tested. The brand.name, serial number and calibration date of l the leak tester shall be recorded. Actual leak rates obtained shall also be recorded for each unit tested. 5.2 To be acceptable, the sample vial, the sample shield and the test port closure s a leak rate less than 1.0 x 10-yl shall each exhibit sec/sec. Any leak rate l greater than this shall be recorded, corrected and l atested a maximum of 3 times. Af ter a third failure, a Quality Discrepancy Report / Supplier Disposition l Request (QDR/SDR) shall be prepared for disposition in l accordance with QP-7 O(M 8-11 c_

PREKRGING A Pacific Nuclear Company ASSEMBLY HELIUM SNIFFER TEST FOR THE NUPAC PAS-2 PACKAGING LT-16 REV. 2 O March 9, 1984 f 'l b b A-r' Prepar By -' ~ Date ?/ W ~ ( Engineer 1 g ~~ Date rh W 3/8 / BL. Quali'ty Assurance D a't e ' Nj ~~~ Manufacturing / Production Date O Other Date [s_ f. n $' 9' bh -- /f,_ Docnment Control /Re'Iease Date

LT-16, Rov. 2 March 9, 1984 t () ASSEMBLY HELIUM SNIFFER LEAK TEST FOR THE NUPAC PAS-2 PACKAGING ~ ~, 1,9 SggeE j This procedure describes the requirements for performing a pressure drop leak test on the NuPac PAS-2 Post Accident Sampling Cask system to verify assembly prior to shipment. 29 BEEEBEHgE gggUMENIS 2 2.1 ANSI N14.5 Leakage Tests on Packages for Shipments of Radioactive Materials. 2.2 QP-5 NuPac Quality Procedure, Quality Planning. 2.3 QP-6 NuPac Quality Procedure, Inspection and Verification. 2.4 QP-7 NuPac Quality Procedure, Inspection and Verification. NOTE: If this test is performed by an organization other than Nuclear Packaging, Inc., the appropriate equivalent quality procedure dictating quality

planning, inspection and verification of the f"'

performing organization may be utilized in place of QP-5, QP-6 and QP-7. 3.0 REQUIREMCITS 3.1 Pressure gauge capable of measuring at least 25 psig to an accuracy of 1 psig shall be utilized. 3.2 Test location shall be well ventilated. 3.3 Helium probe-type Leak Detector capable of detecting a leak of 10-4 sec/see or smaller. 4.0 PROCEDURE 4.1 Assembly Verification Leak Test of the Sample Shield. 4.1.1 Verify that sample

shield, top

plug, and sample port plugs have been properly install-ed for shipment.

Remove the test port clo-sure bolt from the upper sample port plug. 4.1.2 Using appropriate fittings, attach a vacuum

pump, a source of helium gas, and a pressure gauge to the test port such that the vacuum

/'] pump and helium may be isolated from the () system without isolating the guage. I 4.1.3 Using the vacuum pump, reduce the pressure 8-13 l

'LT-16, rov. 2 March 9, 195G inside the sample shield to less than 1 psia. j~s; ) Isolate the pump from the system.

V 3.

4.1.4 Pressurize the sample shield with helium to 15 psig. Isolate the system from-the helium source. 4.1.5 Probe around each of the two valve operators, two valve plugs and the top shield' plug according to the leak detector manufacturer's recommendations. Record the worst possible leak detected. If the leakage exceeds the level indicated in Section 5.1, release the pressure in the system and'make adjustments as necessary. Repeat Steps 4.1.1 through-4.1.5 until the system can pass the require-ments of Section 5.1 or it becomes apparent that the system cannot be made leak tight to the indicated level. 4.1.6 After successfully completing Step 4.1.5, release the helium pressure, remove the fitt-ings from the test port and install the test port closure bolt. This should be done quickly to avoid significant loss of helium from the sample shield at atmospheric pres-sure. 4.1.7 Using appropriate fittings, attach the vacuum pump and the helium leak detector probe to the test port and evacuate the system to a level consistent with the leak detector manufacturer's recommendations. Determine the maximum leak rate past the test port closure bolt and record it. If the leak rate exceeds the level indicated in Section 5.1, release the vacuum and repeat Steps 4.1.6 and 4.1.7 until the closure bolt passes the test or it becomes apparent that the closure bolt cannot be made leak tight to the indicated level. 4.2 Assembly Verification Leak Test of the optional Secondary Containment Vessel (SCV) 4.2.1 If the optional SCV is not used to provide secondary containment, then the following test is not applicable. 4.2.2 After the sample shield has been properly installed within the SCV, replace the SCV lid and secure using the proper bolts. U( g 4.2.3 Install the test port sampling tool in the test port on the SCV and attach to a vacuum 8-14

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p i .LT-16, Rcv. ~2 March 9, 1904 l-i jm.

pump, pressure gauge, and a source of helium f

) such that the vacuum pump and helium source may be isolated from the system without isolating the pressure gauge. Set the test port c1soure bolt in the open position. 4.2.4 Using the vacuum pump, reduce the' internal-pressure of the SCV to less than 1 paia. 4.2.5 Isolate the vacuum pump from the system and pressurize the SCV with helium to a pressure of 15 psig. Isolate the system from the source of helium. 4.2.6 Probe around the SCV lid seal.according 'to the leak detector manufacturer's recommenda-tions. Also probe around the SCV base. Re-cord the worst possible leak detected. If the leakage exceeds the level indicated in Section 5.1 release the pressure in the 'sys-tem and make ad ustments as necessary. Re-3 peat steps 4.2.2 through 4.2.6 until the system can pass the requirements of Section 5.1 or it becomes apparent that the system cannot be made leak tight to the indicated level. 4.2.7 After successfully completing step 4.2.6, release the helium pressure and close the test port closure bolt. 4.2.8 Using appropriate fittings, attach the vacuum

pump, and helium leak detector probe to the test port and evacuate the system to a level consistent with the leak detector manufactu-rer's recommendations.

Determine the maximum leak rate past the test port closure bolt and record it. If the leak rate exceeds the level indicated in Section 5.1, release the vacuum and repeat Steps 4.2.7 and 4.2.8 until the closure bolt passes the test or it be-comes apparent that the closure bolt cannot be made leak tight to the indicated level. 5.0 Accentence Criteria 5.1 For each assembly to have an acceptably low leak rate, the detection equipment must indicate that the total assembly leakage is less than 1 x 10-3 standard cubic centimeters per second. ("'s 5,2 An inspection report shall be prepared in accordance (,/ with Op-5 and QP-6, describing the system and giving the part names and numbers for each component tested. The serial number and calibration date of the pressure 8-15

LT-16, Rev. 2 March 9, 1984 gauge shall be recorded. 5.3 If the systems test unacceptably 3 times in succesalon, Quality Discrepancy Report / Supplier Dispoaltion Re-a quest (QDR/SDR) shall be prepared for disposition in accordance with Op-7. O l O 8-16

o li l l NuPac PAS-2 System Consolidated SAR. Rev.- 0, February 28, 1989 9.0 QUALITY ASSURANCE i i ~ NuPac's-quality as surance program, used f or the design, fabrication, assembly, J t esting, use and maintenance of the NuPac PAS-2 packaging is designed and adminis t ered t o me et the 18 crit eria of 10 CFR 71, Subpart H. A des cription of this program has been submitted to the NRC under NuPac letter QA-78-1, Rev. 1, dated July 31,.1980, and has received Quality Assurance Program Approval No. 0192. 1 9-1 i}}