ML20080K867

From kanterella
Jump to navigation Jump to search
Decommissioning Plan for Univ of Il Lopra
ML20080K867
Person / Time
Site: 05000356
Issue date: 02/28/1995
From:
ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20080K865 List:
References
NUDOCS 9503010371
Download: ML20080K867 (4)


Text

- - - - _ - _ - - - - - - - - - _

I l

l l

)

I Decommissioning Plan for the '

University of Illinois Low Power Reactor Assembly (LOPRA)

License R-117 Docket 50-356 February 1995 l 1

9503010371 950210 fDR ADOCK 0500 6

_ _ _ _------ _ _ ___ _ _--_ _ _------------- ---- ---.-- _ J

st -

1

.i

= > . I

'V

'1.. '

SUMMARY

OF PLAN i n

, The University of Illinois intends to decommission the Iew Power Reactor Assembly j (LOPRA) and convert the facility to a subcritical assembly. The LOPRA is a 10 kW l TRIGA fuel assembly utilizing both aluminum clad and stainless steel clad fuel i elements that is positioned in the Bulk Shielding Facility of the University _of Illinois - I Nuclear Reactor Laboratory (see figure 1). Decommissioning of the reactor will l consist of reducing the number of elements in the core such that the keff in the l

.' assembly shall not be greater than 0.99 to be in compliance with Section 3.9 of the l Advanced TRIGA Technical Specifications. 'All other systems associated with the- l LOPRA,' as discussed in the LOPRA SAR, will remain in existence to assist in the -  !

operation of the facility as a subcritical assembly. The fuel will be transferred to the  ;

- Advanced TRIGA license (R-115, Section 2.B) and the associated physical structure of  ;

the LOPRA that has become activated will be transferred to the 10 CFR Part 30 portion l of the Advanced TRIGA license (R-115, Section 2.C).  !

The operating history of the LOPRA fuel, including burnup that occurred to the fuel before it was utilized in the LOPRA is a total of 595 kW-hrs. Of that amount,480 kW-hrs were generated prior to 1%5 when the fuel was utilized in the AFRRI reactor.

l Operation of the LOPRA from 1971 to 1974 consisted of coupling studies between the i TRIGA and LOPRA reactors. Since 1974 the LOPRA has been used primarily for an  !

approach to critical experiment. .;

2. DECOMMISSIONING ACTIVITIES Decommissioning of the LOPRA reactor will consist of reducing the number of elements in the core such that the keff in the assembly shall not be greater than 0.99 to be in compliance with Section 3.9 of the Advanced TRIGA Technical Specifications.

All other systems associated with the LOPRA, as discussed in the LOPRA SAR, will-remain in existence to assist in the operation of the facility as a subcritical assembly.

3. PROTECTION OF THE HEALTH AND SAFETY OF RADIATION WORKERS AND THE PUBLIC 3.1 Disposition of Fuel The fuel for the LOPRA reactor,58 aluminum TRIGA fuel elements with a U2n  ;

inventory of 2251 grams, will be transferred to the TRIGA license number R-115 part.

l 2.B which allows for 2.6 kilograms of contained uranium 235 in TRIGA type fuel j elements in connection with operation of a subcritical assembly in the Bulk Shielding l Facility of the reactor. The 11 stainless steel TRIGA fuel elements currently on the  !

2 LOPRA (R-117 license), containing 422 grams of U n will be transferred to the l

reactor operations portion of part 2.B of the TRIGA license. The fuel will physically i remain in the Bulk Shielding Facility. j i

m- ,

, g 1j e.- .

- o. . . .J

.. .i 4-

^

3.2. Disposition of Radioactive material A license amendment is being requested to transfer all radioactive components of the l LOPRA structure, as byproduct material, to the 10 CFR part 30 section of the TRIGA ,j license'(R-115). This includes the estimated fission product activity in the fuel elements. The calculated estimated activity of the item is as follows:  ;{

i ITEM MASS (kilorrams) ACTIVITY (mci) l Grid Plates (2) 16.2 3.15 j

~f Spacers 2.3 0.46 .j u  ;

Control rods 11.6 176. v i

Fission Product Activity ----

438  ;

I Plutonium in Fuel ---- ---

0.0812 l l

4. PROPOSED FINAL RADIATION SURVEY PLAN  !

1 i No final radiation survey plan is submitted as the Bulk Shielding Facility that contains' l the LOPRA will remain in operation to be utilized in conjunction with the Advanced i TRIGA reactor (License R-115). A final radiation' survey for the facility will occur ' j

- when the Advanced TRIGA reactor is decommissioned.

5. TECHNICAL SPECIFICATIONS The current LOPRA Technical Specifications will be active until the decommissioning- f order is placed. Upon issuance of the decommissioning order the LOPRA will be j defueled to the point that core 4 1 r is less than 0.99. At this time the LOPRA will be a  !

subcritical assembly subject to the Advanced TRIGA Technical Specifications Section- - 3.9 "Subcritical Experiments Using the Reactor nermal Column or Bulk Shielding l Facility" and the Technical Specifications for the LOPRA License R-117 will be null ,

and void. .;

t

6. PHYSICAL SECURITY PLAN -!

The Physical Security Plan for the University of Illinois Nuclear Reactor Laboratory '}

will remain in force during all phases of the decommissioning plan and afterwards.  !

7. EMERGENCY PLAN l l

The Emergency Plan for the University of Illinois Nuclear Reactor laboratory will -l remain'in force during all phases of the decommissioning plan and afterwards.  !

\

..~

l se' s*

f6s"'

_ r_

_ e'. m" _ _

ev _

p.a

., . . s'. t*

o er . g w'

,g g,'.... .-

y9.*. *,..y4 ,.. * :;gr;eg s.v.

.,a3 i

i

.4. . .

.v.

g

. .T. ** ' '

. .'?.. ,.*.c,... .

.- TwEnus ' -

,, ,. cotone ' ' ..,' ' . * '

1 .,,.,.,

3 '

i fe j> * . .., ; .'.

'g f:.M.'

..stsat N .

ff

. ' *. , .es. ',,
.,l, ., e

,o 4_ { ,. .

.,I, 9

, ,. 4 .9# E L S g .

1. i j Q ;
  1. ~p.

o I

, .o e .; 1 -

- .- l- l' l g 6E jd* -

^

, .= 3  ; .s , ~g ,

i w [ .n- ~

g--

C bgAO- N, Ii "'*

c

,.?-

e .

.- , . , . \ ,- '

s

,, gh..

9

~ ~~ e

/ POLYrfetVLENE ,g d JoPRA .<.y

r. ..

j em f,t 7:.*

2

%t' .

e

~ 7..e,. '

-r.

'7s .

  • ,, t'. s .

Sans Y*i .

g.,. .' *

  • 2 ., *
v. , . -

, y, a.f

%*t , 38Es&tRBee ll .

t's rassa 'f *

. *.f -

  • g 4

't 2-

~

y  % % w .:;:::.. ;.:::k:d{ .

s'- o' d-a" _

T g ,

Sestion of beam port level,

  • Fig. 1 Crose4Section Plan View abouring location . -

of the 14HtA and the I111oots Advanced TRIGA 4

l a


w - - - + - .,-

ym . - _m_,- - - - . . -