ML20235J740
| ML20235J740 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 07/08/1987 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20235J693 | List: |
| References | |
| 0183N, 183N, NUDOCS 8707150707 | |
| Download: ML20235J740 (9) | |
Text
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ENVIRONMENTAL REPORT
' f3 g/
DISMANTLING PLAN FOR WESTINGHOUSE NUCLEAR TRAINING. REACTOR LICENSE N0. R-119
)
1 s
i This environmental report is written to allow the Commission to make an environmental ~ impact assessment concerning the dismantling of the J
Westinghouse Nuclear Training Reactor -in accordance with 10CFR part 50.82.
This report has been written along applicable guidelines given in j
10 CFR part 51.45.
i (a)
DESCRIPTION OF PROPOSED ACTION:
f I
Westinghouse Electric Corporation desires to dismantle the l
Westinghouse Nuclear Training Reactor (License No.
R-119) and
(~h) terminate its f acility license.
All Special Nuclear Material, 4.9 5
kg of high enriched Unranium Fuel and two Pu-Be neutron sources, have been transferred to a
DOE facility for reprocessing.
Westinghouse desires to dismantle the remaining
- reactor, decontaminate and/or transport any remaining activated / contaminated material within the f acility in accordance with NRC/ DOT regulations to a low level waste burial site, f ree release the f acility and any j
remaining material in accordance with Regulatory Guide 1.86 and have the NRC terminate the NTR Facility license.
(b)
IMPACT OF THE PROPOSED ACTION:
The Westinghouse Nuclear Training Reactor is housed in the south wing of the Westinghouse Nuclear Training Center, Zion, Illinois.
Constuttion of the f acility was completed in conjuction with the remainder of the building.
Dismantling the reactor and O
Q f ree releasing the f acility will not ef f ect the structure of the Ol83N 1
8707150707 870700 l
PDR ADOCK 05000087 i
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f acility 'or any 'of the surrounding parts 'of the Training Center.
Free ' release of the f acility will not alter its structure, but assures safe use of the area for other purposes.
The use of Regulatory Guide 1.86 and SpR/hr.above backround at one meter f rom the surf ace as survey acceptance criteria assures that free release at the f acility will not have a negative ef fect on the surrounding terrain, vegetation, wildlife, nearby waters or aquatic life.
(c) ADVERSE ENVIORNMENTAL EFFECTS WHICH CANNOT BE AVOIDED:
Due to the extremely low integrated power history-(Figure 1),
irradiation of all core components and support structures is minimal.
The predominate use of aluminum as the structural material minimized the quantity of activated material to a few-components.
The present radiation levels in the reactor, reactor I
tank and dump tank are shown in Figure 2.
Air and ~ water samples taken in ' the NTR Reactor Room have consistently been below 10CFR20 Appendix B table limits.
Summa ries of water and air survey results for 1986 and 1987 are given in I
figures 3 and 4.
Smear surveys taken monthly in the Reactor Room are summarized in Figure 5.
The f acility' has generated no liquid or gaseous wastes during its operation and the dismantling process also is not expected to require the generation of any such waste or effect on the surrounding environment.
Since Commonwealth Edison maintains environmental surveys of the area and the NTR has not
. generated radioactive releases during its operation, environmental surveys of the surrounding area will not be conducted as part of the NTR dismantling.
Therefore there will be no significant exposure (approximately zero) of the general public to radioactive effluents released during the dismantling activies.
bu Ol83N 2
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Solid waste ! disposal to an approved f'acility will be limited l
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'to a small quantity of activated structural components and graphite i
used in the reactor.
It is estimated that approximately 20 cubic feet of material will be transported f rom the f acility to a low level radioactive materials burial site in accordance with NRC and DOT regulations.
The collective dose equivalent to workers during the dismantling and waste, shipment is estimated at 80 millirem (Figure 6).
There is expected to be no significant exposure (approximately zero) to the gen' ral public to radiation during the dismantling or e
low level waste shipment.
Frea Release of materials and the f acility will be based on Regulatory Guide 1.86 and a dose rate of SpR/hr above backround at one meter from the surface.
These criteria have been established to assure that there will' be no significant environmental ef fects due to radiation on the general public during U
future use of the facility.
-(d) ALTERNATIVES TO THE PROPOSED ACTION:
The three alternatives for decommissioning the reactor f acility are described by the psuedo acronyms "SAFSTOR", "FNTOMB" i
and "DECON"
( ANSI /ANS-15.10-1981 ).
Westinghouse Electric
)
Corporation feels that both the options of SAFSTOR and ENTOMB are not as desireable as DECON.
The DECON option will remove i
radioctive materials f rom the f acility and permit f ree use of the area by the general public.
This option will allow long term utilization of the facility with no significant environmental ef fects on the general public due to radiation exposures while the f
SAFSTOR and ENTOMB options would require the continued maintenance j
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0183N 3
I and supervision of the facility or portions of the f acility in l
t order to protect the public f rom exposure to any radiation from I
material maintained at the site.
The small quantity and low level of-' radiation in the facility will allow its removal economically.
(e)
IRREVERSIBLE and IRRETRIEVABLE COMMITMENTS of RESOURCES:
Westinghouse Electric Corporation has committed adequate financial and man-power resources to establish the necessary plans and procedures to dismantle the reactor and remove the. radioactive materials f rom the facility. Westinghouse Electric Corporation has the technical. and financial capabilities of successfully completing this project and returning the Westinghouse Nuclear Reactor Facility to general'public use.
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r-10 FIGURE-1 V
INTEGRATED POWER
- t4UAL REPORT SLtt%RY 1972-19E6 This is a summary of the in te gaa t e d power and run hours f or I
l i t wa s l i c ens e d (R 119) cr. Jan 2E, 1972.
l the NTR since Itn E GR.'-T ED P OWER j
REF ORTING YEAR RLN TIME
( N-HRE)
HOURE 28.559
{
931 1972 o
1B.260 760 1973 l
14.200 l
1974 245 l
13.377 564 1975 l
29.727 1014 1976 46.439 1977 2062 33.280 1978 1465 45.048 1979 1851 i
50.900 1980 1989 24,7 i
1981 1422 j
56.289 1982 2419 i
28.500 1983 1329 32.440 1984 1530 21.430 1985 1529 15.735 566 1986 0.857 49 1987
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Electrically disconnect end, r er:ov e 10 cA NI s f r om Rx Tank end r emove wi r ing.
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Remove CICs end BF3s and su;p er t Dreckets 15 rr.R from the Reector Tank 3.
Ren.ove S c'ur e Tube tr om Rx Tenk 5 mR 4.
Remc ie Con tr o' R o d E r. r c. : d T u t + s 10 mR 5.
D. s c or.n e : t, disassentie end remove Fu+'
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