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Summary of 891018 Meeting W/Ga Co,Eg&G Idaho,Weston & DOE in Rockville,Md to Discuss Legal Weight Truck Casks. GA-4 & GA-9 Cask Development Project Presentation Encl
	ML19332D370
Person / Time
Issue date:	11/14/1989
From:	Osgood N; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
	NUDOCS 8912010083
	Download: ML19332D370 (95)
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' MEMORANDUM FOR:

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Nancy L. Osgood F

an Transportation Branch, NMS$

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SUBJECT:

MEETING

SUMMARY

CONCERNING GENERAL ATOMICS LEGAL WEIGHT i-l TRUCK CASKS 1

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! Attendees NRC EG&G.5 Idaho

-M GA.

Ross Chappell Mel Jensen i

A Earl Easton

. ;/ Rich Boonstra George Gardes Weston

'c ' Jack Boshoven Daniel Huang j

Maria Koploy Henry Lee Heraj Rahimi Richard Meyer Curt Lindner i

Larry Pickering Nancy Osgood DOE Idaho j

Shiaw-Der su Carl Withee i

Al Zimmer Li Yang Walt Mings introduction A meeting was held at the request of General Atomics (GA) at Rockville, Maryland,

-i on October 18, 1989, to discuss the GA-4 and GA-9 spent fuel shipping casks.

3 TheGA-4(4PWRassemblies)andtheGA-9(9BWRassemblies)arebeingdeveloped d

for the Department of Energy for spent' fuel shipment by truck under the Nuclear 1

Waste Policy Act. The meeting marked the end of the preliminary design stage.

j Discussion 4

The discussion followed the meeting handout, which is enclosed. Additional points are described below, j

1.

Fuel Basket. The basket has-been redesigned, and now incorporates B4C cores for neutron poison..The structural

- response of the basket will be discussed in detail in a future meeting.

It was suggested that testing.of the basket be considered.

~

i 2.

Fuel Burnup. Burnup credit is taken for the GA-4 cask.

.i Credit for fuel depletion and fission product poisions j

. will be used.

It was stated that any request for burnup y

credit must include physical measurements of fuel burnup and must address potentially unburned fuel in fuel assembly enos.

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FAisen Credit.- Criticality analyses use a 5% reduait in y

boron,in B4C poison cores to allow for uncertaintes.- Chemical

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assa,, a ta will be used to confirm this allowanua.

4.

Rar"ation Shielding. Radir. tion dose rates are chown to met' a'

'egulatory limits. Accident dose rates are-calculated-assuming no neutron shield and no impact limiters.

- 5.:

Schedule. -An application for the GA-4 and GA-9 casks is l

expected to be submitted to NRC in 1992.

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Nancy L.-Osgood Transportation Branen, HMSS l

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Enclosure:

Meeting llandout

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-NL0sgood CEMacDonald Meeting Attendees Meeting Notebook i

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MEMORANDUM FOR:

The Files

'FROM:;

Nancy L.: Osgood.

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Transportation Branch, NMSS

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SUBJECT:

-MEETING

SUMMARY

CONCERNING GENERAL' ATOMICS LEGAL WEIGHT' 4

TRUCK CASKS

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i6t Attendees

NRC EG&G,1 Idaho-4

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'Ross Chappell.

-Mel.Jensen;

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Earl-Easton 3.:..

Rich Boonstra George Gardes Weston

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' Jack Boshoven-Daniel Huang f

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Maria;Koploy.

Henry Lee

.Heraj Rahimi

,lu 4 M Richard Meyer Curt Lindner

. s,M a x

Larry Pickering; Nancy Osgood

DOE. Idaho-

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,.Shiaw-Der su zCarl Withee fj

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,v -Al'Zimmer Li Yano Walt Mings

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,' Introduction <

j-A meeting was heldLat.the' request of General Atomics.(GA) at Rockville,. Maryland, on October!18, 1989, to discuss,the GA-41and 'G/-9 spent fuel shipping. casks.

-The GA-4 (4 PWR assemblies)'and the GA-9 (9 BWR assemblies) are being.. developed i

forithe Department of.. Energy for spent-fuel shipment by truck under the Nuclear -

Waste Policy Act.- The meeting' marked the. end of the~ preliminary design stage.-

i Discussion The discussion followed the meeting handout, which is enclosed. Additional points are described below.

1. -

Fuel Basket. The basket has been redesigned, and now.

incorporates B4C cores for neutron poison. The structural response of the basket will be discussed in detail in a.

future meeting.

It was suggested that testing of the e o basket be considered.

~

2.

Fuel Burnup.

Burnup credit is taken for the GA-4' cask.

Credit for fuel depletion and fission' product poisions wil1~be-used.

It was stated that any request for' burnup credit must include physical measurements of fuel burnup and must address potentially unburned fuel in fuel assembly ends.

/

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L;

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Memo to Files'

2 -

3. <

Poison Credit;- Criticality analyses use' a 5% reduction in M

boron in 84C poison cores to allow for uncertainties.

Chemical.

- assay data will be.used to confirm this allowance.

4. --

Radiation Shielding. Radiation dose rates are shown to. meet 1

all' regulatory limits.- Accident dose rates are calculated t

assuming no neutron; shield and no impact limiters.

P 5.

Schedule. ~ An application for the GA-4 and GA-9 casks' is expected to be submitted-to NRC in 1992.

l e

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p' Nancy L. Osgood

-Transportation Branch, NMSS i

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Enclosure:

' Meeting Handout c

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DEVELOPMENT PROJECT 1

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PRESENTATION TO l

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NRC TRANSPORTATION BRANCH ROCKVILLE, MD i

l OCTOBER 18,1989 l

+--

J-059(1) i i

10-12-89

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L GA-4 AND GA-9 CASK SHIELDING DESIGNS ARE COMPATIBLE l

q e OPTIMlZED FOR MAXIMUM PAYLOADS i

e SIMILAR SHIELDING CONFIGURATIONS-1 t

i e SAME SHIELDING MATERIALS j

e IDENTICAL-ANALYTICAL APPROACH i

i i

i e SIMILAR RADIATION DOSE LEVELS EXTERNAL TO CASKS I

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4' J-217(45)

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NEUTRON SOURCE DATA BASED ON DOEJRW-0184 i

DESCRIPTION GA-4 (PWR)

GA-9 (BWR) l l

ENRICHMENT (% U-235) 3.2 2.75 j

j BURNUP (MW0lMTU) 35,000 30,000 l

i COOLING TIME (YR) 10 10 l

FUEL LOADING (MTUlASSEMBLY)

OA69 0.197 i

7 NEUTRON SOURCE (NIS-ASSEMBLY) 1.2 x 108 4.0 x 10 l

l TOTAL NEUTRON SOURCE PER CASK (NIS) 4.8 x 108 3.6 x 108 NEUTRON SPECTRUM Cf-252 Cf-252 4

l l

J-217(46) i 10-11-89 l

l l

+ - -

GAMMA SOURCE DATA BASED ON DOEJRW-0814 1

t i

e INCLUDING FUEL AND HARDWARE i

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.i e DEPENDENT UPON BURNUP AND COOLING TIME l

1 l

e INSENSITIVE TO FUEL ENRICHMENT l

j e SAME DESIGN BASIS AS FOR NEUTRON SOURCE DM.

1 3

1 i

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j J-217(47) j 10-11-89 J

ass en - um em uma e

amm am aus -mus. sus aus me sus : sum;:aus amm aus aus i CENERAL ATEMEECS 1.25 MEV GAMMAS ARE THE PRINCIPAL

CONTRIBUTORS TO EXTERNAL DOSE RATES i

1.25 MEV GAMMASlS-ASSEMBLY I

i 4

1 COMPONENT PWR BWR

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ACTIVE FUEL 1.1 x 1 014 2.3 x 1913 l

TOP HARDWARE 1.1 x 1012 2.7 x 1911 BOTTOM HARDWARE 2.0 x 1012 1.0x1912 i

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J-217(48) f 10-11-89 1

.._______________________,u___._.

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DOSE CALCULATIONS INCLUDE ALL SOURCE COMPONENTS a

2 i

i e PRIMARY NEUTRONS FROM SPENT FUEL.

l e SECONDARY NEUTRONS FROM ADDITIONAL FISSION IN FUEL AND HEPLETED URANIUM l

1 i

e PRIMARY GAMMAS FROM FUEL AND HARDWARE.

1 I

i l

e SECONDARY GAMMAS FROM NEUTRON INTERACTIONS 1

i j

t i

e ' SCATTERING OF NEUTRONS AND GAMMAS FROM AIR AND GROUND i

I J-217(49) d l

10-11-89 1

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SHIELDING ANALYSES USE STANDARD MATERIAL i

. DENSITIES lWITH NEGLIGIBLE HYDROGEN

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DEPLETION FOR NEUTRON SHIELDING MATERIAL 1

j DENSITY-COMPONENT MATERIAL

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GAMMA SHIELD DEPLETED URANIUM 19.05 l

NEUTRON SHIELD RX-201-1 (1.0 WT % B) 0.90-l STRUCTURE XM-19 AND SS-304L 7.92 IMPACT LIMITER AL HONEYCOMB-0.0 i

I

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J-217(50) 10-11-89

+$+ 88mem monacs WE USED 3-D MCNP MONTE CARLO CODE

~ l TO SIZE SHIELDING CONFIGURATIONS-

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e RECOMMENDED BY ORNL AS A STANDARD MONTE CARLO CODE 1

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l e EXPLICIT 3-D MODEL OF CASK GEOMETRY i

1 e BUILT-IN POINTWISE CROSS SECTIONS

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i e TREATMENT OF ALL SOURCE COMPONENTS i

e NO CORRECTIONS REQUIRED TO DOSE RESULTS l

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J-217(51) j 10-11-89

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ii DESCRIPTION PATH TWODANT l

METHOD POINT KERNEL MULTIGROUP DISCRETE INTEGRATION ORDINATES i

GEOMETRY XYZ (3-D)

RZ CYLINDRICAL (2-D)

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l PRIMARY GAMMAS YES NO l

l NEUTR0hS + (n,y)

NO YES j

AIR SCATTERING YES YES 1

l GROUND SCATTERING NO NO y

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'RESULTS NORMALIZED TO MCNP TO ACCOUNT FOR APPROXIMATIONS

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l SHIELD ANALYSIS CONSIDERS NORMAL AND i

i HYPOTHETICAL ACCIDENT CONDITIONS 1

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NORMAL HYPOTHETICAL DESCRIPTION TRANSPORT ACCIDENT NEUTRON SHIELD INTACT REMOVED l

l STEEL SKIN INTACT REMOVED l

i IMPACT LIMITER VOID REMOVED l

I I CASK SURFACE 1 m FROM DAMAGED l

DOSE POINTS 2 m FROM TRAILER CASK SURFACE l

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o' DOSE RATES IN MREMlH FOR GA4 CASK

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i ACCIDENT DOSE RATES ARE KEPT BELOW 1000 MREMJH i

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i i-o e DOSE RATES IN MREMlH ILLUSTRATED BELOW FOR GA-4 CASK WITHOUT DU CRACK

-i e ABOUT 500 MREMlH AVAILABLE TO ALLOW FOR DU CRACK l

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GA-4 AND GA-9 CASK SHIELDING DESIGNS 3

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. COMPLY WITH REGULATIONS t

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s MOST EFFECTIVE SHIELDING MATERIALS USED 1

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i e OPTIMUM DISTRIBUTION OF NEUTRON AND GAMMA DOSES i

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{ ~ 20% n AND 80% 7 SPLIT) i i

e SHIELBING ADEQUACY DEMONSTRATED BY 3-D MCNP l

e TRANSPORTATION DOSE LIMITS MET FOR NORMAL TRANSPORT AND HYPOTHETICAL ACCIDENT CONDITIONS.

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CRITICALITY DESIGN AND ANALYSIS l

INCORPORATES NRC RECOMMENDATIONS i

e MOST REACTIVE FUEL TYPE TO BE DETERMINED IN FINAL DESIGN e 5% MARGIN FOR BORON CONTENT IN B C IN ADDITION TO 2%

4 MANUFACTURING UNCERTAINTY l

e NO NEUTRON SHIELDING FOR ACCIDENT CONDIT0NS l

e ADDITIONAL BENCHMARK CALCULATIONS FOR CRITICAL EXPERIMENTS WITH DU REFLECTOR l

i e IMPLEMENTATION OF PHYSICAL MEASUREMENTS OF FUEL REACTIVITY l

FOR GA-4 CASK l

l J-217(23) 10-11-89

m.,

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WE HAVE COMPLETED OUR PRELIMINARY DESIGN i-4 e INTRODUCTION I

l

- AGENDA REVIEW AL ZIMMER

- PROJECT ORGANIZATION

- PROGRAM STATUS 1

i e DESIGN UPDATE DICK MEYER i

i l

e SHIELDING EVALUATION SHIAW-DER SU i

e CR!TICALITY EVALUATION JACK BOSH 0VEN f

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e THERMAL EVALUATION RICH BOONSTRA

- ANALYSIS j~

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- TESTING j

l e STRLtCTURAL EVALUATION MARIA KDPLOYlLARRY PICKERING

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- ANALYSIS l

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- TESTING J-217(41) i 10-11-89 1.

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PRELIMINARY: DESIGN REVIEW IS IN PROGRESS-e o PRELIMINARY DESIGN PACKAGE COMPLETED I

l e DESIGN REVIEW COMMITTEE REVIEWING PRELIMINARY-DESIGN PACKAGE e

e REVIEW MEETING SCHEDULED FOR NOVEMBER 6,1989 i

l e ADDITIONAL IMPACT LIMITER TESTING PLANNED i

l

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e PLANNING FOR HALF-SCALE MODEL i

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l PROJECT STATUS 4

l GENERAL ATOMICS GA-4i9 LEGAL WEIGHT TRUCK CASK DESIGN 4

e PRELIMINARY DESIGN PACKAGE SUBMITTED TO DOE - 9130189 l

l i

e MATERIAL SELECTION COMPLETE l

i j

e MAJOR STRUCTURAL, THERMAL AND NUCLEAR CALCULATIONS COMPLETE j

t j

e ENGINEERING TESTS OF NEUTRON SHIELD MATERIALS COMPLETE 4

1 e PHASE ONE OF IMPACT LIMITER TESTING COMPLETE q

e PRELIMINARY DESIGN OF TRAILER COMPLETE i

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WE HAVE MADE SIGNIFICANT DESIGN IMPROVEMENTS

'TO THE GA-419 CASK DESIGNS i

l e IMPACT LIMITER REDESIGN BASED ON ENGINEERING TESTS.

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e SUPPORT STRUCTURE UNDER IMPACT LIMITERS IS ROUND j

i l

e TRUNNIONS MOVED T0 CORNERS FROM FLATS e REMOVARLE FUEL SUPPORT STRUCTURE WITH B C RODS 4

e 304 SST TO XM-19 SST l

l e ADDITIONAL BOLTS ADDED FOR IMPACT LIMITER ATTACHMENT 1

e ADDED PROTECTION AROUND CLOSURE i

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i BURNUP CREDIT YES NO i.
MAXIMUM ENRICHMENT 4.5%
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i MAXIMUM K-EFF O.93 0.86 I
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1 ENRICHMENT BURNUP-I (WT % U-235)
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%-INF FOR INFINITE ARRAY OF 1A3 W 17 x 17 ASSEMBLIES (4 WT %)
DELTA-K DUE TO FINITE CASK
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AND ASSOCIATED STEFL DELTA-K DUE TO BURNUP
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j J-217(31) l 10-11-89 f
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U0 DENSITY (% TD) 94 94 2
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l
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CRITICALITY ANALYSIS USES CONSERVATIVE ASSUMPTIONS e INFINITE ARRAY OF CASKS (FISSILE CLASS 1) 3 i
e COMPLETE LDSS OF NEUTRON SHIELDMG FOLLOWWG THERMAL EVENT 1
i i
i r
e FULL WATER FLOODING l
e OMISSION OF GRID PL ATES, SPACERS AND HARDWA!4E E FUEL ASSEMRIY l
e NO BURNABLE POISONS l
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J-217(35) l 10-11-89 i
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BOTH 27-GROUP AND 123-GROUP CROSS SECTION DATA 1
ARE ACCEPTABLE FOR CRITICALITY ANALYSIS.
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DESCRIPTION 27-GROUP 123-GROUP 1
I i
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CASK TYPE GA-4 GA-9 1
4 i
i FUEL ASSUMPTION BURNED FRESH l
FISSION PRODUCT DATA COMPLETE L9111TED l
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ANALYTICAL BIAS
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-l ll ANALYSIS DURING FINAL DESIGN d
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e EVALUATION OF NON-UINIFORM AXIAL BURNUP DISTRIBUTION l
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J-217(37) l 10-11-89 i
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l Km FOR1NDIVIDUAL ASSEMBLIES i-DETERMINES MOST REACTIVE FUEL i
e INFINITE R ANE ARRAY OF FUEL ASSEMBLIES e FINITE FUEL HEIGHT WITH WATER REFLECTORS l
e INCLUS!03 0F FISSION PRODUCT AND ACTINIDE ABSORBERS l
FOR BUT.TdED FUEL
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e CALCULATIONS OF K FOR VARIOUS FUEL ASSEMBLES
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l J-217(38) 10-11-89 4
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FISSION CHAMBER t
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- CALIBRATION AGAMST A PRESELECTED FUEL ASSEMBLY
- DEASUREMENT OF K-EFF VS COUNT RATE (CPS) i J-217(39) 10-11-89 l
me um as en am se em amm uma ese en sus an as sus en en aus em
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t PRELIMINARY CRITICALITY CONTROL DESIGN IS COMPLETE l
i i
e USE OF PROVEN AND MOST EFFECTIVE POISON MATERIAL (8 C) 4 e ESTABLISHMENT OF BURNUP CREDIT REQUIREMENT FOR GA-4 CASK l
l e SPECIFICATION OF FIXED ABSORBER (B C) REQUEEMENTS FOR GA-4 AND 4
GA-9 CASKS TO MEET K-EFF <0.95 FOR FISSILE CLASS I e COMPLETION OF BENCHMARK CALCULATIONS AGAINST CRITICAL l
EXPERIMENTS FOR FRESH FUEL USING 27-GROUP AND 123-GROUP l
CROSS SECTIONS 1
l e ADDITIONAL CRITICALITY ANALYSIS TO BE PERFORMED IN FINAL DESIGN i
FOR INCLUSION IN SARP l
J-217(40)
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e TESTING OF NEUTRON SHIELD j
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'U#~88
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SI, KS1 PSI 0F SAFETY FLAT ORIENTATION NORMAL 39.6 49.8-
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ACCIDENT 95.2 99.5
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LOCATION TYPE Si,KSI Si, KSI SI, MSI SI, KS!
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2.16 3.08 4.78 E.76 b
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30.51 43.24 20.99 35.54 l
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3b RIDLENGTH P,
31.60 44.87 42.48 60.30 i
Z=94, CORNER P,+Pb 36.01 50.74 44.73 63.83 ALLOWABLES:
l Pm (2OO'F) " 08 7 ESI i
P,+ P (200'F) = 99.5 KSI b
i MINIMUM MARGIN i
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P,
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+ 0.16 f
J-217(95)
P,+Pb
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+0.39 10-11-89 I
me :
se sus:
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CRUSHED TOP IMPACT LIMITER 1
CRUSHED-CLOSURE N PACT FLANGE LMITER NEUTRON NOLE FROM i
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10-10-89
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STRESSES AND DISPLACEMENTS s
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i l
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l
- CLOSURE BOLT (129 KSI VS 138 AT 400'F) j l
- SURFACE NEAR SEAL K35 KS1 VS 40.8 AT 400*F) l l
l
- SIDEWALL K22 KSI VS 43.4 AT 300*F) i l
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l e SEAL INTERFACE OPENS TO O.044 IN. MAXIMUM 1
i j
J-217(68) i 10-11-89 l
i i
I sum. mum uma uma num amm sum num

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~~SUMMARY~~
OF DISCUSSIONS i
~I l
q i
e PHASE I IMPACT LIMITER TEST RESULTS WERE USED TO IMPROVE IMPACT LIMITERS i
l t
e CLOSURE BOLTS ARE DESIGNED TO WITHSTAND ALL CLOSURE LOADS AND MOVEMENTS q
i e ANALYSES SHOW SIDE DROP IS MOST CRITICAL FREE DROP FOR i
CASK BODY
-I e FUEL CAVITY LINER AND SUPPORT STRUCTURE WILL MAINTAIN GEOMETRY AFTER HYPOTHETICAL ACCIDENT EVENTS-J-217(82) 10-11-89 i
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ML19332D370

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