ML20235J740

Environ Rept Dismantling Plan for Westinghouse Nuclear Training Reactor, to Allow NRC to Make EIS Re Dismantling Per 10CFR50.82

ML20235J740
Person / Time
Site:	05000087
Issue date:	07/08/1987
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20235J693	List: ML20235J691 ML20235J701 ML20235J711 ML20235J740
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

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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 p PDR

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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.

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.p Solid waste ! disposal to an approved f'acility will be limited l

.U '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'e ral public to radiation during the dismantling or 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 l

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 Q

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.- 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. l l

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r-10 FIGURE-1 V INTEGRATED POWER

1. t4UAL REPORT SLtt%RY 1972-19E6 I

This is a summary of the in te gaa t e d power and run hours f or l i t wa s l i c ens e d (R 119) cr. Jan 2E, 1972.

l the NTR since j

RLN TIME Itn E GR.'-T ED P OWER REF ORTING YEAR HOURE _

( N-HRE)

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931 28.559 o 1972 -

760 1B.260 1973 l

245 14.200 l l

1974  !

564 13.377 1975 l

1014 29.727 1976 2062 46.439 1977 .

1465 33.280 1978 1851 45.048 .

i 1979 1989 50.900 1980 .

24,7 i 1981 1422 j

2419 56.289 i 1982 1329 28.500 1983 1530 32.440 1984 .

1529 21.430 1985 566 15.735 1986 .

49 0.857 1987 __

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g Dose Est:rretes 4cr- D i s . e r, - l i n ; tb+ ?.TR

' end S h i p ; i r. ; E#p r odu c t s A:';vits Es'irete- Dese

1. 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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2. 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+' 10 mR Ei e. e t or .

6. Cisccnnect er d rem [ve Steinless Eteel Ficat 10 mR 5.; t c *. .

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- i. D i s i s s eitbl e UelVes :-nd p;p.9; Svstems ir 5 mR

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