ML20045A497

Certificate of Compliance 9793,rev 3,for Model M-140 Shipping Package

ML20045A497
Person / Time
Site:	07109793
Issue date:	06/08/1993
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML17349A962	List: ML17349A961 ML20045A497
References
NUDOCS 9306100391
Download: ML20045A497 (9)

Text

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CERTIFICATE OF COMPLIANCE L

1o cFR r1 FOR RADIOACTIVE MATERIALS PACKAGES L

1 a CERTIFICATE NUMBER D. REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d.PAGE NUMBER e TOTAL NUMaER PAGES l

9793 3

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2. PREAMBLE r

a. This certificate is issued to certify that the packaging and coritents described in item 5 below, meets the apphcable safety standards set forth in Title 10. Code of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Matenal."

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b. This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportation or other I

apphcable regulatory agencies. including the government of any Country through or into which the package will be transported.

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b 3.THI TIFICA S

ED THE BASIS OF A SAFETY ANALYSIS REP T OF THE ACKAG SIGN OR PPL CAT

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U.S. Department of Energy

" Core Independent M-140 Safety Analysis Report

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Division of Naval Reactors for Packaging" and "S3G-3 Recoverable Irradiated (

Washington, DC 20585 Fuel in the M-140 Safety Analysis Report for L

Packaging". transmitted February 27, 1991, as L

c. DOCKET NUMBpFIsup lemented.yj,,g7gg

4. CONDITIONS i

This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified below.

5.

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(a)

Packaging i

L (1) Model No.: M-140 f

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(2) Descripiion

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L A stainless steel cask for, transporting recoverable iriadiated fuel modules.

I The cask.is a. right circular cylinder arid'is, transported in the upright f

s position! The package has approxiniate1 dimensions andTw' eights as follows:

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Civity diameter L70 inches

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146 inches

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Cavity height w

,i Body, outer diameter 98 inches L

f Body steel wall thickness _

14 inches c

Package,overall outer 1 diameter 126. inches f

Package'overall height

,?l94 inches

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Packaging' weight, including C

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standard internal.s 1315,000 pounds

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Maximum package weight,( -

including contents 375,000 pounds j

i The cask body is made from 304 stainless steel forgings.

The cask walls are

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14 inches thick and the bottom p%te is 12 inches thick.

The cask body

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flange provides a seating surface for the closure head and its protective l

dome.

The flange contains 36 wedge assemblies located radially around the inside diameter.

Retention of the closure head is achieved by engaging the j

i wedges in a tapered groove in the circumferential edge cf the closure head.

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The cask body has 180 external cooling fins welded to the exterior wall. A

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support ring is welded to the external cooling' fins at a point above the center of gravity. The support ring seats on-and is bolted to the rail car mounting ring during transport. The cask bottom is equipped with an energy

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absorber which is composed of five concentric stainless steel rings varying

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j in thickness and height.

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9306100391 930600 PDR ADOCK 07109793

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CONDITIONS (continued) i I

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Pag'e 2 - Certificate No. 9793 - Revision No. 3 - Docket No. 71-9793 I

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(2) Description (con't)-

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The closure head is made from forged 304 stainless steel, and is I

I approximately 13 inches thick and 81.7 inches in diameter.

The closure head I

l is equipped with an access port, which is approximately 24 inches in l

g diameter, and is offset from the center of the closure head. The access a

port plug is a stepped design with a maximum diameter of approximately 31

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inches and is attached to the closure head by 24 bolts. The closure head l

N and access port are sealed with double ethylene propylene 0-ring seals.

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Seal test ports are provided for the closure head and access port seals. A I

l stainless steel protective dome is positioned over the closure head and is l

g secured to the cask body flange by-12,1.38-inch diameter, 38.5-inch long g

studs installed in a-vertical direction!and 6, 2.5-inch diameter, 9-inch

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long shear bolts installed in the radial direction.

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I The containment-system is composed of the cask body, the closure head and I

l the closure head access port plug. There are five penetrations in the j

g containment system:

a drain port and vent port in'the closure head, and a

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g thermocouple penetration, a water inlet penetration,~and a water outlet I

penetration in the cask body.

Each penetration is sealed with a plug and a l

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double ethylene propylene 0-ring seal, and'is equipped with a leak test j

port.

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l The fuel modules are positioned in an internals. assembly!

The internals

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I assembly is composed of stacked internal" spacer plates-which have openings I

for the fuel modules. The' internals, assembly has a top > plate or top plate i

I subassembly which is preloaded by springs against a retaining ring fitted in jl I

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a groove in the cask cavity wall. TheLinternals assembly may be a standard I

)l internals assembly or an S3G-3 internals assembly.

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l (3) Drawings lll l

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The packaging is ' constructed and assembled in'accordance with the

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Westinghouse Electric Corporation Drawings _in Appendix 1.3.2 of the j

l application.

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(b) Contents l

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l (1) Type and form of material l

Recoverable irradiated fuel modules, limited to the following types, j

q including associated activated corrosion products:

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(i)

S3G-3 recoverable irradiated fuel modules.

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S8G recoverable irradiated fuel modules.

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(iii) DIG Core 2 recoverable irradiated fuel modules.

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Page 3 - Certificate No. 9793 - Revision No. 3 - Docket No. 71-9793 I

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l (2) Maximum quantity of material per package y

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I Total package weight, including fuel modules and internals assembly, not to

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exceed 375,000 pounds; and I

(i)

For contents described in 5(b)(1)(i):

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I S3G-3 recoverable irradiated fuel modules, not to exceed 62,300 I

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Btu /hr decay heat per package.

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(ii)

For contents described in 5(b)(1)(ii):

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58G recoverable irradiated fuel: modules, not to exceed 51,609 Btu /hr i

I decay heat.per package (prototype modules), or 45,713 Btu /hr decay i

I heat per package (shipboard modules).

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(iii)

Forcontintsdescribedin5(b)(1)(iii):

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DIG' Core 2 recoverable irradiated fue1 mo'duleshnot to exceed 37,750 g

i Btu /hr decay heat.per package, y'f' I

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(c) Fissile Class;

. III'

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1 Maximum number"of tone "3

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packages per shipment 1

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For S3G-3 recoverable irradiated fuel shipments:

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(a) Only a full' load is authorizeds A. minimum.bf twelve' fuel modules must have 1

I either control, rods or poison' shipping rods. AllJodded and unrodded I

I modules must be! positioned as specified on page;6-ll (Rev.1) of."S3G-3 I

l Recoverable Irradiated Fuel in the M-140 Safety Analysis Report for I

l Packaging;"

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I (b) Minimum fuel cooling time is 130 days after shutdown; I

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l (c) Core age must be at least 4,000 logging corrected full power hours; l

l (d) Control rod hold-down devices must be installed on cells which have control l

I rods; I

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(e) All cells must have top and bottom energy absorbers; I

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(f) The weight of the fuel modules must be limited as specified on page 1-23 l

(Rev. 2) of "S3G-3 Recoverable Irradiated Fuel in the M-140 Safety Analysis I

Report for Packaging;" and i

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l (g) S3G-3 internals assembly must be used for shipment of S3G-3 fuel modules.

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E Page'4 - Certificate No. 9793 - Revision No. 3 - Docket No. 71-9793 I

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,j 7.

For S8G recoverable irradiated fuel shipments:

I (a) Only a full load is authorized.

Full and partial fuel modules may be i

8 shipped in any combination. All full and partial fuel modules must have 1

l control rods; l

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g (b) Minimum fuel cooling time is 248 days after shutdown for prototype modules, i

and 157 days after shutdown for shipboard modules; llg 8

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(c) All fuel modules must have lower supports and grapple adapters; j

l (d) Standard internals assembly < must be~used for shipment of S8G fuel modules.

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Full fuel modules must'have two full (side); spacers, partial fuel modules g

I must have two full. (side) spacers and one partial (inside) spacer; and

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(e) The weight of the fuel modules must be limited as specified on page 1.23 I

l (Rev. 4) of "S8G Recoverable Irradiated Fuel in the M.140 Safety Analysis I

y Report For Packaging."

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8.

For DIG Core 2 recoverable irradiated fuel shipments:

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(a) Up to eight fuel modules-may be ' shipped per p'ackage.

Fuel modules of I

l different types may be' shipped in any combination.

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(b) Minimum fuel cool _ing time is'181_ days after shutdown.

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(c) All normally rodded fuel modules;sust;have control rods 1 Control rod hold-I I

down devices must be: installed on; rodded modules'.

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l (d) Rodded modules.must have' top and bottom energy absorbers.

Unrodded modules g

must have top. energy absorbers.

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I (e) Standard intern'albassembly must be used for shipment of DIG Core 2 fuel I

l modules.

Fuel module cavity spacers must be used for all fuel modules.

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9.

The package must contain no more th'an; 6" gallons of residual water.

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10.

Failed fuel, or fuel with defective cladding is not authorized for shipment.

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6 11.

Each packaging must meet the Acceptance Tests and Maintenance Program of I

l Chapter 8 of the application, except:

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All containment seals, including the main closure head seal, must be p

I replaced with new seals within the 12-month period prior to each shipment,

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or earlier if inspection shows any defect.

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The package must be prepared for transport and operated in accordance with l

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Chapter 7 of the application, except:

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l The containment seals, excluding the main closure head seal, must pass a I

8 leak test after final closure prior to The leak test must I

haveasensitivityofatleast1x10',eachsgipment.

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std-cm /sec.

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,_______________________________________-__r__________.

.I conomons tcontinued)

I Page 5 - Certificate No. 9793 - Revision No. 3 - Docket No. 71-9793 1

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13.

Prior to first use, and within the 12-month period prior to each shipment, all g

I containment seals, including the main ci,osure hgad seal, must be leak. tested to 1

I show a leak rate no greater than 1 x l{/sec.

std-cm /sec. The leak test must have a I

I sensitivity of at least 5 x 10' std-cm I

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g 14.

Expiration date: October 31, 1996.

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REFERENCES I

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" Core Independent M-140 Safety Analysis Report For Packaging," and "S3G-3 Recoverable-1 l

Irradiated Fuel in the M-140 Safety Analysis Report For Packaging," transmitted I

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February 27, 1991.

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Supplements dated: May 23,. June 21, and July 17, 1991,cand February 4 and 7, I

l August 17, and December 2,x1992.

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II FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

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(C' ass'R..Chappell;lS on Lea' der I

I Cask Certifichtion Section

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iTransportation; Branch.

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< Divi _sion of)IndustrialLand-i g

f edical; Nuclear Safety; NMSS; I

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'AJN 0 81993 Date:

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[E UNITED STATES 3.T ' " '3 NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 o%.m..- }

APPROVAL RECORD Model No. M-140 Package Certificate of Compliance No. 9793 Revision No. 3 By application dated December 2, 1992, The Department of Erargy, Naval Reactors, requested an amendment for Certificate of Compliance No. 9793, for the Model No. M-140 package Naval Reactors requested that the certificate be amended to authorize DIG Core 2 recoverable irradiated fuel modules as contents for the M-140 Package. The contents include both full size rodded modules and partial size, unrodded modules, which can be transported together in any combination. A maximum of eight fuel modules are transported per package.

Structural The M-140 standard internals will be used to ship the DIG Core 2 fuel modules.

The DIG Core 2 package meets all design requirements and restrictions in sizes and weights for the M-140 standard internals and container. The only exception is a small increase in temperature in the closure head (+6*F) and protective dome (+28'F).

However, the higher temperatures have negligible effects on the package because the DIG Core 2 package is 12% lighter in total weight. Thus, no new analyses of the M-140 container are required.

The package rslies on aluminum impact absorbers to protect the fuel modules from excessive impact load during the 30-foot drops.

The impact absorbers are cylindrical, axially loaded aluminum tubes. The energy absorbing capability and the maximum impact load of the impact absorbers were determined by full scale 30-foot drop tests at the Sandia National Laboratories. These were performed at 300*F and -20*F to envelope both the hot and cold environments.

Base! on the maximum impact loads of the impact absorber, the application provideo results of the structural evaluation of the fuel modules to show that stresses in the fuel cladding, which is the primary containment boundary for the package, do not exceed the yield strength of the cladding i

material.

In addition, the movement of the control rods was much less than the movement assumed in the criticality analyses.

Shieldina The shielding analysis included gamma rays and neutrons from fission products and activated hardware.

The assumed source term was eight full sized fuel modules from the part of the DIG Core 2 with the highest total burnup. The minimum cooling time after shutdown was 90 days. The length of the fuel module was broken into 22 source regions to model the axial variation. The dose rate from the gamma rays was calculated with the SPAN 4 point-kernel code using iron buildup factors. The dose rate from the neutrons was calculated using a 2-D transport code.

The analysis included worst case fuel movement under hypothetical accident conditions. The analysis also considered crush and puncture damage to the side of the container.

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The applicant's estimated external dose rates are within the regulatory limits for both normal and accident conditions.

Criticality The applicant's criticality safety analysis assumed that the container was<

filled with eight of the most reactive fuel elements (i.e., the full size fuel module with the highest fissile content). The fuel modules were turned so the most reactive section is toward the center of the package.

The beginning of life fissile loading was used.

The full size fuel module is shipped with its control rod secured in place.

The package was analyzed as Fissile Class III with one package per shipment.

The normal conditions analysis modeled a single dry container with mirror reflection at the container surface to bound a 2 package array. The accident analysis considered preferential flooding that filled the fuel module voids but left dry voids between the fuel modules, and assumed a control rod withdrawal distance greater than the structural analysis estimate.

The applicant used the Monte Carlo computer program RACER for the criticality analysis. The applicant's calculated results show that the package will be adequate?y subcritical under normal and accident conditions.

Thermal The applicant performed a thermal analysis of the M-140 package with the DIG Core 2 fuel modules for normal and hypothetical accident conditions using the i

REFLEX computer code. The analysis assumed the contents were shipped dry with a maximum decay heat load of 37,750 Btu /hr. The applicant showed that any package loaded with any number of partial, unrodded assemblies will be bounded by the M-140 loaded with eight rodded assemblies.

The maximum decay heat load was determined for the package based on an analysis of fuel blister and blister rupture temperature limits. The maximum decay heat was limited so that fuel blistering would not occur under normal conditions (a maximum one year dry shipment period), and that rupture of the fuel cladding would not occur under accident conditions. The applicant showed that the normal condition criterion is the most limiting case.

In analyzing the package for normal conditions, the applicant assumed a 100*F ambient temperature and the solar insolation given in the Insolation Data 1

Table in 10 CFR E71.71(c).

The maximum temperatures which were calculated for normal conditions are given in the following table:

Location

.Tempqta.ture. *F Spacer Plate 429 Cavity Wall 209 Seal Region 178 f

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, i The results of the applicant's analysis showed that the seal region remained well below the acceptable service temperature for the ethylentpropylene 0-rings. The maximum temperature of the fuel modules did not exceed the fuel blister temperature.

The calculated temperatures were within the limits for-

.i the package materials.

The M-140 package was also analyzed for a 100*F ambient temperature without insolation. The maximum temperature at any accessible _ point.on the package _

surface was 161*F. The M-140 package meets the requirements of J

10 CFR 6 71.43(g) for exclusive use shipments.

The M-140 package was also evaluated for hypothetical accident conditions.

The applicant showed that the fuel temperature remained below the minimum calculated temperature for fuel blistering. The temperatures of the 0-ring seals were not calculated for the accident condition, since the seals were not necessary for the package to meet the accident conditions containment requirements.

The applicant calculated the maximum normal operating pressure (MNOP) based on the maximum fuel temperature and an initial loading at atmospheric pressure and a temperature of 70*F.

In addition, the applicant assumed that there was enough residual water in the package to result in a saturated condition at the maximum fuel temperature. The MN0P was calculated to be 39.2 psig, which is less than the pressure calculated for the S3G-3 contents.

j Containment The fuel cladding provides containment of the_ fuel, fission products, and fuel' activation products. The structural analysis showed that the integrity of the cladding would be maintained under accident drop-test conditions'.

In addition, the thermal analysis showed that the maximum fuel _ temperatures do not exceed the _ fuel blister-or blister rupture temperatures under normal _or fire test conditions.

t The containment of the corrosion products present on the fuel surfaces is provided by the M-140 packaging. The applicant provided an estimate of the total amount of radioactivity present on the fuel. module surfaces. The j

estimate was based on the maximum surface area-of the' fuel modules. The fuel' surface contamination concentration was based on data available for: cores with water chemistry similar to the DIG Core 2.

The total amount of activity in:

terms of the number of A2 quantities availab)e for release was lower for the DIG Core 2 than that evaluated by the NRC staff for the core-independent

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package.

Therefore, the leak testing provisions specified in the Certificate of Compliance are adequate for the expected contamination levels for th'e O1G Core 2.

The package, subject to the conditions specified in the Certificate of Compliance, meets the containment requirements of 10 CFR Part 71.

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4-plicant requested that the amount to 6 Residual Water the M-140 be increased from 2 gallonsience w In addition to the revised contents, the ap ld of residual water permitted withinaximum volume of water which woutable sinc This was based on actual shipping exper The increased quantity was considered acceplcu h

and a conservative calculation of t e m gallons.

The eak containment wall temperature.

remain in the package.

the maximum internal pressures were cawithin the con ld not be affected by freezing of the applicant stated that the package wou residual water.

mended to include O1G Core 2 fuel Qonclusions Specific packaging The Certificate of Compliance has been a The l modules have been included. amended to package.

modules, with up to eight modules per restrictions for the OlG Core 2 fueCertificate of Compli transported with up to 6 gallons o f the package to meet the the t to the conditions specified in These changes do not affect the ability o requirements of 10 CFR Part 71, subjec Certificate of Compliance.

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l CassR.Chappell/dectionLeader Cask Certification Section Transportation Branch Division of Industrial andMedical Nucl JUN 0 8 1MG Date.,

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