ML20213E361

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Rev 3 to SAR for Nupac PAS-1 Packaging to 10CFR71 Type `B Packaging Requirements. Two Oversize Drawings Encl
ML20213E361
Person / Time
Site: 07109184
Issue date: 10/30/1986
From:
NUCLEAR PACKAGING, INC.
To:
Shared Package
ML20213E338 List:
References
NUDOCS 8611130123
Download: ML20213E361 (11)
v • d • e


Text

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SAFETY ANALYSIS REPORT FOR THE l

NUPAC PAS-1 PACKAGING i

TO 10 CFR 71 TYPE "B" PACKAGING 1 REQUIREMENTS A

l REVISION 3 i

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OCTOBER 30, 1986 t

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PREPARED BY:

i Nuclear Packaging, Inc.

4.

1010 South 336th Street i

j.

Federal Way, Washington 98003 l

(206) 874-2235 i

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-c gaseous and iodine fission products, are transported within the containment vessel.

Maximum activity of the liquid contents is estimated to be 2.846 curies per milliliter, or 49.09 curies total.

Relative co ncentra tion s of iso tope s present are given in Section 5.0.

Optional contents may be:

A.

Greater than Type A quantities of radioactive material as neutron activated metal or metal oxide in solid form.

B.

Greater than Type A quantities of byproduct material consisting of process solids or resins, either dewatered, solid, or solidi-fled in secondary containers.

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f Node Area (ft2)

Heat load (BTU /hr) 2 1.2272 301.68 10 3.6816 905.05 14 (top) 7.6576 1,882.50 14 (side) 5.3333 655.56 19 3.6667 450.69 26 2.0000 245.83 The internal heat loading due to the activity of the source may be caulculated by dete rmining a conversion f actor for curies to watt s.

A composite conversion is calculated by utilizing the following equation:

O Q, = (1/F F )

3(E +{E/3))/}S y2 1

y p

g U

Where:

E = gamma decay energy, MeV/ disintegration y

Ep = beta decay energy, MeV/ disintegration (ref:

CRC Handbood.gf Chemis try and Physic s. 53th Ed, B247-541)

Sg = contributing activity per isotope, C1/gm (Section 5.0, SHIELDING)

F1 = conversion factor: 1.6(10)-13 watt-sec/Mev F2 = conversion factor: 3.7(10)10 di sint e gra tion / Ci-sec The resulting conversion is:

Q, = 420.6 Ci/ watt Therefore, the heat contribution due to the source is:

q = (2.85 Ci/ gm)(15 gm)(3.412 BTU /wa t t-hr)/420.6 Ci/ watt =.35 BTU /hr 3-17

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Therefore, the internal hea t load is neglected in the thermal analyses.

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Conside ring sol ar insol a tion, it amount s to only.01% of the total heat load input.

3.4.2 Maximum Temperatures Table 3.4.2-1 shows the steady state nodal temperature distribution for the worst case normal conditions of transport.

Ambient air temperature is taken as 1300F, with the solar heat load taken as described above. The highest nodal temperature occurs at Node 2, 179.20F.

CLASS 2 - TEMPERATURE, T ID DEGREES F ID DEGREES F ID DEGREES F ID DEGREES F 1

130.0000000 2

179.2259012 3

170.4274427 4

152.8305258 5

144.0320673 6

143.3331152 7

143.3032776 8

143.2365052 9

143.2056550 10 177.8041637 11 169.3725489 12 152.5093192 13 144.0777044 14 155.3134081 15 153.9621338 16 149.3743777 17 144.0350438 18 143.3046392 19 141.8739336 20 142.1601665 21 142.8101232 22 143.1846292 23 143.2285834 24 143.2274964 25 143.2302849 26 141.7418783 27 141.8193709 28 141.9954227 29 142.0968851 30 143.1498358 31 143.1628402 32 143.1658794 O

V TABLE 3.4.2-1 3.4.3 Minimum Temocratures The minimum temperature the package will experience is -400F, per the r equiremen t of 10 CFR 71.

3.4.4 Maximum Internal Pressures Neglecting the small quantity of water in the sample cask, the maximum internal pressure may be calculated assuming a constant volume of air heated to 143.240F a t Node 8 pe r Tab l e 3.4.2-1.

As s um in g an initial tempera ture of 700F, the internal pressure for an isentropic process is:

1 = (T /T M -1 P /P 2

2 i O

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o The 15 milliliter payload for which the NuPac PAS-1 is designed is given below:

j Nuclide Concentration (Ci/cc)

B r-82

.0015 i

i Br-83

.0153 i-B r-84

.0103 Co-58

.002 Co-60

.000003 Cr-51

.004 Fe-5 5

.005 Fe-59

.002 j

I-13 0

.0062 I-131

.162 I-132

. 23 (,

I-133

.312 I-134

.262 1-135

.288 Kr-83 M

.037 Kr-85

.004 Kr-35 M

.072 1

Kr-87

.093 Kr-88

.176 j

i Mn-54

.003 Ni-63

.00001 Ie-131M

.002 Xe-133

.680 Xe-133 M

.028 i

Xe-135

.127 Ie-135M

.090 i

I Ie-138

.030 Others M

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Total 2.846 l

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  • m TABLE 5.0-1 h

These isotopes can be grouped according to gamma emission energy level s G

with all activities rounded upward for conservatism.

The resul ting energy levels with their activities are given below:

Enerav Activity (MeV)

(Photons /cm3-sec) 0.3 2.098 (10)10 0.5 5.753 (10)9 0.8 2.272 (10)10 1.3 4.475 (10)10 1.7 (includes 'Others')

1.759 (10)10 2.5 3.589 (10)9 3.5 1.258 (10)9 4.5 7.146 (10)8 Conservatively consider the payload a point isotropic source with no self-shie l ding.

From Blizard, Reactor Handbook, Second edition, Vol. III, Part B,

the photon flux through a multilayered shield is:

6 = Be (-ut)/4nR2 Where the buildup f actor, B, is de termined according to Brode r's me thod, discussed in DNA-1892-3.

For example, for a three layered shield of material s i, j, and k, having thicknesses of t, tj, and t, respectively, i

k the total buildup factor would be:

B = B(piti) + (B(pj(ti + tj)) - B( J ti)]

+ (B(pk(ti + tj + tk)) - B(pk(ti + tj))]

ne mass attenuation coefficient, p,

for various materials e.ny be found in Tabl e 10.1 of Bliz ard. The buildup f actors f or various material s may be found in Table 10.10 of Blizard.

De dose at the package surface and at six feet from the package surface at 5-2

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7.4 Anoendix -

7.4.1 Storane Procedures The following two sub-sections delineate PAS-1 storage in either of two co nf igura tion s, disassembled or assembled.

7.4.1.1 Storane Procedure,13 the D1 assembled Condition 7.4.1.1.1 The lower overpack shall be on a steel pallet with the upper overpack and overpack closure bolts set aside in a convenient location.

7.4.1.1.2 The secondary containment vessel shall be positioned inside of the lower overpack. The secondary containme nt v e s sel and lid, and eight 1-8 UNC closure bolts shall be removec and set aside in a convenient location.

7.4.1.1.3 The primary containment vessel shall be l o-cated on a pallet outside the secondary con-tainment vessel when not in use.

i 7.4.1.1.4 The primary containment vessel lid and eight j

3/8-16 UNC closure bolts shall be removed and l

set aside in a convenient l oca tion.

l 7.4.1.1.5 The foam vial hol de r and foam spacer (if I

required) shall be located with the primary f

containment vessel.

7.4.1.1.6 A quantity of vermiculite not less than two I

cubic feet shall be stored in an airtight t

container in a convenient location.

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7.4.1.1.7 All unpainted surfaces shall be kept coated with a high quality vacuum grease to prevent oxidation and to assure a tight seal when the system is in use.

1 7.4.1.2 Storane Procedure h the Assembled Condition J

7.4.1.2.1 If required for the current configuration, place a foam spacer block into the bottom of the primary containment vessel.

7.4.1.2.2 Install a foam vial hol de r into the prima ry containment vessel.

7.4.1.2.3 Obtain and secure a quantity of vermiculite not less than two cubic feet inside of an airtight containe r.

7.4.1.2.4 Install the v e rmic ul i t e into the primary containment ves sel.

7.4.1.2.5 Visually inspect the primary containme nt vessel lid seals and body sealing area for contaminates ( e. g., dirt, dust, etc).

If ne c e s sa ry, clean these areas and apply a light coating of vacuum grease.

1 7.4.1.2.6 Install the prima ry containment ves sel lid into the body, f ollowed by eight (8) 3/8-16UNC closure bolt s.

Tighten the closure bol ts to 16-18 f t-lbs torque each.

7.4.1.2.7 Install the as sembled primary containment vessel into the cavity of the secondary con-tainment ves sel.

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7.4.1.2.8 Visually inspect the secondary containment vessel lid seals and body sealing area for contaminants ( e. g., dirt, dust, e tc).

If necessary, clean these areas and apply a i

i light coating of vacuum grease.

4 7.4.1.2.9 Install the secondary containment vessel lid into the body, f ollowed by eight (8) 1-8DNC closure bol ts.

Tighten the closure bolts to 450-500 ft-lbs torque each.

7.4.1.2.10 In s t al l the secondary containment vessel assembly inside the lower overpack, located on a shipping pallet.

i 7.4.1.2.11 Install the upper overpack onto the l owe r overpack and secure with the eight (8) 3/4-10UNC (optionally sixteen (16) 1/ 2-13 DNC) closure bol ts.

Tighten the 3/4-10DNC closure bolts to 150-200 f t-lbs each (50-65 f t-lbs torque each for the optional 1/2-13DNC clo-sure bol t s).

7.4.1.2.12 Pe rf orm the final as sembly of the shipping pallet and store in a convenient location.

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TOR 7JE REQUIRE.*ENTS:

Al PRIPARY CCNTAlt9ENT - 3/8-16 x 8.02 16-18 FT-LB

3) SECCTARY CONTAINFENT 8 x 3.0 450-500 FT-L3 C) CVERPACKS - 3/4-10 x 1.25; 110-130 FT-LB.

L LC'iGITO!RAL SEA 9 'JELDS FOR ALL *COERS SHALL BE FULL NOTES: UNLESS OTHERWISE SPECIFID j

GROUC CR FACHINED 5,00T3.

I. MATERIAL:

A) CCNTA!hMENT WESSEL - 304 SST PER ASTP-A2tJ

3) SHIELD. CARBON STEEL PER ASTM-AS16, 64 70
  1. EC

- LDD PER QQ-L-1716, GR A CR C Cl QVERPACK - CARBON STEEL PER ASTM-A 36

- 7. 75 -=

2 3.SU

- FOAM PER NUPAC SPEttFICATIONS TVP UN*

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2.. ALL WELDIN

G. PROCEDURE

S AND PERSONNEL SHALL BE QUALIFIED IN ACCCROANCE WITN Cwd AC C1.1 OR Asnt CCCE, SECTION II. WELD PROCDURES SHALL BE AVAILABLE FOR AUDIT OR REVIEW, 3.

ALL WELDS SMALL BE v!SUALLY EXAMIND IN ACCORLANCE WITN AWS D1.1. SECTION 4.15.1

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ALL DPOSD CAR 20N STEEL SURFACES (EXCEPT 0-RING GLANDS AND ADJACENT SEATING SURFACES) SHALL BE PAINTO PER NUPAC APPROVED PROCEDURES.

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LDD PauRING SHALL BE PER NUPAC APPROVD PROCEDURES.

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CONDUCT FABRICATICN VERIFICATICM LEAK TEST IN ACCCRCANCE WTTN 47 x C

SECTION 4.3.2.'

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