ML20235U678

From kanterella
Jump to navigation Jump to search
Summary of 870218 Meeting W/Doe,Westinghouse,Nupac,Ge & Unc Nuclear in Silver Spring,Md Re Proposed Shipment of Shippingport Reactor Vessel
ML20235U678
Person / Time
Issue date: 03/02/1987
From: Odegaarden R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20235U644 List:
References
FOIA-87-631 NUDOCS 8710140195
Download: ML20235U678 (3)


Text

- _ - _ - -

p 4

b

./

o,,

UNITED STATES.

./

NUCLEAR REGULATORY COMMISSION o

.I WASHINGTON, D. C. 20655 k

i T,,e.../

(

me or aar l

MEMORANDUM FOR:

The Files FROM:

Richard H. Odegaarden, FCTC, NMSS

SUBJECT:

SHIPMENT OF. REACTOR YESSEL Attendees Westinghouse DOE UNC Nuclear R. J. Jackson Deborah Kenyon Glenn Van Sickle Larry Hansen John V. Schreiber Donn M. Burgess Gordon Chalfant W.E. Murphie NUPAC GE NRC l

CharTis Temus F.A. MacLean R.H.Ifdegaarden J

C.R. Marotta

]

'~

W.H. Lake i

D.T. Huang C.E. Williams H.W. Lee

(:

C.R. Chappell E.P. Easton C.E. MacDonald

{

Introduction

- A meeting was held at the request of the Department of Energy (DOE) at Silver l

Spring, Maryland, on February 18, 1987, concerning the proposed shipment of the Shippingport Reactor Yessel.

Discussion

]

I The staff met with the DOE to dis ing for the shipment of the Shippingport Reactor Yessel and'N r

ank from Shippingport, PA to Hanford, WA. The package will weigh approximately 930 tons and is about 17.5 t

feet in diameter by 43 feet long andGNdG00Nily would be transported by barge.

The decay heat load would be less than 100 watts.

j 4

8710140195 871008 PDR FOIA PARRISH87-631 PDR k

g/l

^

4m u t 4

);

. )1 q;l:f!

r i

j q,

]

a

,r m

m, 1

'~' The Files, '

24 MAR 02 W

,M b R

L.

gAnn q t

7 q

/

)

(z 77q.

r

?The bssic components of the reactof vessel and neutron shield tank are as.

j

.follows (outside to inside):

~

1" thick'A-36' carbon steel oute'r shield tank-

35". thick concrete' grouti(replacing water used during reactor operation)

'1"-. thick A-36 carbon steel inner shield tank:

1

= 4" thick compressed insulation (not structural member)'

4.i e

J 8.13" thick steel reactor vessel
1/4" thick stainless' steel; reactor vessel cladding :

f a

1

2-1/2" thick 300 Series st,ainless steel thermal s11 eld

'/

/

j f

q 1.49" thick inconel reactor. core barrel 3

J304 stainless steel filler plates and grovt fill f

j y

The bottom of the reactor vessel is dished and the neutron: shield tank exter.ds i

slightly above' tis ' location of the fuel assemblies. The-reactor vessel will J

~

be: transported without fuel. assemblies present.-

'A one-inch thick lifting skirt has been added and welded around the upper j p section of the reactor vessel between the outer neutron shield tank and the top p'

lifting beam' configuration. The reactor-head is held in place by'20 short head l

1 bolts and.16 long (6-inch diameter) bolts extending from the sidefof the reactor, through; the reactor vessel lid to the lifting beam conffirJration.'

~7 f The entire package would contain about 6,500 ci of Co-60, Fe-55 and Ni-63.-

~

(.

Almost(all.the material is activation products in the thermal shield, core

' barrel,'and filler plates. No fissile or fission products are present.. Total

.)

surface contamination is about 7.2 ci of Co-60. Attempts. to remove the surface contaminaticd were only possible with electro-polishing. Basically, all J

1 radioactive material is non-dispersible.

i 0

.i y

,./'

(

s' t

q 3>

k y

.c

. a i

j.

'The' Files 3

MAR 02 Eli

.y (.

3 There was'some q'uestion as to whether the package would be classified LSA Type A.or a Type B package.- In either case, the package should be shown to I

meet the general and normal conditions of transport.. The staff suggested that t.

model testing and analysis be used to demonstrate the adequacy of the packaging.

1 Escape of radioactive material.is not considered significant due to the

.i nondispersibility of the contents. ' More information is needed to assess the a

significance of external radiation.

DOE intends to submit an application for this package later this-year. The application would include the acceptance tests, maintenance program and operating procedures for the package.

Our initial' review would require between 3 and 4 months.

Richard H. Odegaarden, Project Manager Transportation Certification Branch Division of Fuel Cycle and

~~

Material Safety, NMSS

-(

) -.

t i

i B

I 9

i e

___.m____