ML20195C617

Safety Evaluation Re Amend Request to Terminate Licensed Activities

ML20195C617
Person / Time
Site:	07001489
Issue date:	03/27/1986
From:	Mallett B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20195C597	List: ML20195C591 ML20195C607 ML20195C617 ML20195C629
References
NUDOCS 8811030247
Download: ML20195C617 (2)

Text

a UNITED STATES

1. g r80g'C, NUCLEAR REGULATORY COMMISSION

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0 4 j 799 ROOSEVELT RO AD 4 CLE N E L8.YN. ILLINO15 60137 g n /

MAR 271995 SAFETY EVALUATION REPORT License Number: SHM-1461 Docket Number: 070-01489 Licensee: Goodyear Aerospace Corporation Akron, Ohio 44315

Subject:

Amendment request to terminate licensed activities, dated January 16, 1986 Background / History In a letter, dated July 30, 1984, Goodyear Aerospace Corporation (GAC) indicated a desire to renew its NRC License Number SNM-1461. Subsequent to this request, NMSS amended the license to extend the expiration date to April 1, 1986 in accordance with a letter dated July 23, 1985. Region III has had the renewal request pending since July 30, 1984 as Control No. 23906. The July 23, 1985 letter indicated tut GAC was discontinuing the activities authcrized on the license and planned to decontaminate and decommission the equipment and facilities. In a letter dated January 19, 1986, GAC indicated that they had completed the decontamination activities; and they requested that the license be terminated. The letter also enclosed a copy of GAC's close-out survey for the facilities. The license was issued on January 14, 1974 for normal and depleted uranium and uranium enriched in U-235 (not to exceed 349 grams of U-235 in 46 kilograms total uranium). The material was used as uranium hexafluoride (UFs) and standards for the development and testing of gas centifuge equipment.

The place of use was the Wingfoot Lake Advanced Technology Center (see diagrams of facility and surrounding areas in Attachment 1).

Conclusions / Recommendations The licensee's survey is on'y confirmatory (i.e., it utilizes only random samples taken at points where the licensee surmised would have presented the greatest potential for contamination during plant operations). It is therefore not a complete close-out survey and the licensee should be instructed to resubmit.

Following receipt of an adequate close-out survey, the NRC should perform a confirmatory survey at the GAC site prior to termination. In the interim, the license should be amended to extend the expirat'on date to August 31, 1986 to 8311030247 660327 PDR C

ADOCK 07001489 PDC

O Safety Evaluation Report 2 allow GAC sufficient time to retrieve the necessary survey results. There will be no increase in the amounts of any effluents that may be released off-site, no significant increase in individual or cumulative occupational exposure, and no potential for or consequences from radiological accidents as the result of this amendment. Therefore, no Part 51 Environment Report is necessary in accordance with 10 CFR 51.22(c)(ii).

tws. kJ Bruce S. Hallett, Ph.D., Chief Materials Licensing Section 4

i me i

f FEB 2 61986 FCUF:VLT 70-1489-i Goodyear Aeraspace Corp.  ;

. ATTN: J. V. Pflanm '

Department 131 G1  ;

o "

Akron, Ohio 44315 i

. Gentlemen:

As stated in the enclosed Fib ial Register Notice (48 FR 16030) dated  !

f April 14, 1983, the Nuclear Regulatory Commission has further implemented the  ;

r Regional Licensing Program. Your License No. SNM-1461, Docket No. 70-1489 is affected by this regionalization, and we have transferred the "official files" >

to Region !!!. In the future, all correspondence should be addressed to: i f

U. S. Nuclear Regulator.y Comission ,

Region !!!

Material Licensing Section ,

799 Roosevelt Road i Glen Ellyn, IL 60137 l Sincerely, Original Signed ByI w.T. Crow W. T. Crow, Acting Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS

Enclosure:

As stated DISTRIBUTION w/out encl:

WTCrow VLTharpe MMoriarty FCLA CCovington, FCLA WBrown, SGMI OWeiss, LFMB GBennington, SGRT LCobb, IE NMSS R/F FCUF R/F FCUP R/F SHO POR JAHind, Region III ' SSMallett,' Region 111-EYShum MYoung Docket 70-1489 0FC:FCUF

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NAFE:VLWa rpe/ks :WTCrow :  :  :

DATE:A /JW86 :J//4/86 :  :  :  :  :

OFFICIAL RECORD COPY

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GOODYE AR A E R OSPAC E C O R P O R AT I O N AKRON. CHIO 44315

'/ 16 January 1986 4 Ref:CIHS.1115P e RECElVED

- .m Mr. W. T. Crow, Acting Chief -

Uranium Fuel Licensing Branch h'

\

o.JAN 21 1986 > ^#)

s.Nuctttt RL;ULAftu Division of Fuel Cycle and COTust:'t y Material Safety, NMSS Nuclear Regulatory Commission h\ [h e/

/

l Washington, D. C. 20555 N 1 en

SUBJECT:

Termination of NRC Source Material & Special Nuclear Material License No. SNM-1461 for Goodyear Aerospace Corporation Advanced Technology Center (ATC)

Dear Mr. Crow:

Goodyear Aerospace Corporation has completed its work at the Wingfoot Lake ATC facility. As part of the decommissioning of this facility all UF, contaminated materials, equipment, manufactured goods and waste, has beUn removed and properly disposed. The last shipment of contaminated materials was picked-up by Teledyne Isotopes on January 8,1986.

The Wingfoot Lake ATC facility has had a radiation survey conducted by

CAC engineers. All results from this survey are well below NRC guide-l lines, for de-commissioning a facility. The full report of the radiation

! survey is attached.

Goodyear Acrospace Corporation has completed all the NRC requirements for closing a plant and is requesting Source Material License No. SNM-1461 be terminated so CAC can open the plant for unrestricted use.

l We greatly appreciate your assistance in expediting this procedure.

I Further work at the WFL facility is required to comply with the Depart-ment of Energy (D0E) directives for facility decomtamination.

If there are any questions concerning this request please con *.act p Corporate Industrial Hygiene & Safety.

Very truly yours, 00CIUtn  %

g p/ ! ( J "i -

JAN 211986 > 3 J. V. Pflaum, CIH untErEgy Industrial Hygienist, Sr. I cccxtictExt '

Corporate Industrial Hygiene & Safe s

' Y Department 131 C1, (216) 796-7299 g

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. O O MEM0RANOUM November 21, 1985 UJP-823 To: J V Pflaum, D/131

Subject:

Decontamination of Facilities (UF6 Related items) at ATC-WFL Site

References:

1) Memorandum, CHIS994P, dated 29 October 1985

2) NRC Material License, SNM-1461, Amendment 1, dated 15 October 1985 (Expiration date 1 April 1986)

3) Annex A: Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted use or Termination of Licenses for Product, Source, or Special Nuclear Material, U.S. Nuclear Regulatory Comission, Division of Fuel Cycle and Material Safety, Washington D.C. 20553

Enclosures:

1) Nuclear Material Inventory Sumary 2 Radiation Survey Map, Advanced Technology Center 3 Contaminated Parts Removal Sumary 4 Direct Floor Surface Radiation Measurement Results

5) Floor Wipe Test Radiation Measurement Results INTRODUCTION s

This report was prepared in response to Reference 1) and describes the work i that was done at the Advanced Technology Center (ATC) in preparation to release the facility for unrestricted use. The ATC was the only facility operated by Goodyear Aerospace Corporation (GAC) where radioactive material in the form of Uranium Hexafluoride (UFg ) was used. GAC operated the facility under NRC License (Reference 2) to cond0ct perfortnance tests on developmental 4

gas centrifuge machines from 1974 to 1985. The work was initially sponsored by GAC and then funded on 00E Contract DE-AC05-810R20789.

A summary of the UF 6 Inventory at the facility is shown in Enclosure 1). The largest quantity of material was nonnal UF 6. Approximately 300 grams of 1%

enriched standard material was used on the Mass Spectrometer.

The specific locations where the material was used or stored are shown on the map presented in Enclosure 2). These locations were:

AGC-1 Gas Stand Mass Spectrometer Laboratory AGC ? Gas Stand Column Cut Up Area AGC-4 Gas Stand Power Hacksaw Hood and Cut Off Saw Waste Barrel Storage Rotor Cut Up Area Part Storage UF6 Storage Area Outside Casir] Storage Decontamination Area

. O O ,

Page Two These areas were monitored periodically for any radioactive contamination and recorded in the UF radiation record book that is on filo with D.E. Gleghorn, 6

D/131G.

TERMINATION ACTIVITIES Termination activities were initiated at the ATC in June 1985 using the NRC Guidelines for Decontamination described in Reference 3).

The work included:

1. Disassembly of all contaminated equipment and centrifuge components such as rotors and columns.

2, Packaging of contaminated DOE owned equipment and parts for shipment per DOE instructions.

3. Packaging of contaminated GAC owned equipinent for shipment to Teledyne Isotopes. Westwood, New Jersey per Tel,edyne instructions.

4. Packaging of UF 6 for shipment to Goodyear Atomic for recycle.

5. Radiation survey of the ATC facility All parts of equipment that came in contact with UF, were considered contaminated in excess of the limits and were therefore disassem8 led according to the following procedures: ,

.. Applied "Radioactive Material" stickers to contaminated parts and equipment.

2. Limited access to work area to only personnel wearing protective clothing

- paper coveralls, gloves, shoe covers and half face respirator masks.

3. Provided tools and supplies to work area.

4. Disassembled equipment only to major assembly level and covered openings on pipes, pumps and valves with duct tape. Long columns were first cut to 20 f t lengths and then power hacksawed to about 3 f t lengths.

5. Placed parts and equipment on wood skids and moved skids to packaging area.

6. Checked floor and tools in work area for contamination using Alpha Counter.

Cleaned contaminated arets with detergent water and sponge. Disposed of wash solution in Teledyne waste barrel.

7. Disposed of contaminated clothing in Teledyne barrels.

. O O Page Three j The 7 contaminated gas test rotors were cut up in the designated area shown in Enclosure 2 map. For this work, the following additional precautions were taken: 1

1. Roped off the work area which was approximately 20 feet wide by 50 feet long.

2. Placed plastic drop cloths on floor inside roped off area. Operated air monitors in work area.

3. Cut rotors to 40 inch lengths.

4. Mopped inside surfaces of rotor sections with detergent water solution to re-  !

move visible green uranium oxide residue.

5. Pourd contaminated wash water into Teledyne waste barrels.

t

6. Placed plastic drop cloth on floor in front of hood and cut off saw area shown j on Enclosure 2) map.  ;

7. Moved rotor sections to hood and cut off saw.

8. Cut rotor sections axially into two pieces and stacked in cardboard boxes.  ;

9. Taped boxes shut, identified contents a'nd stickered boxes with "Radioactive Material" labels, t

10. Rolled up drop cloths and placed in cardboard boxes together with contaminated protective clothing worn by workers.

The radioactive contaminated 00E owned equipment that was designated for shipment  !

to other DOE installations was packaged in wood boxes. The inside of each wood box was lined with 6-mil thick polyethylene plastic sheet. Af ter box lids were installed, the boxes were banded and the contents identified.

The GAC owned radioactive contaminated equipment and liquid waste was packaged in steel Teledyne barrels (Type 55-05M and DWLVL-A). These barrels were sealed and weighed in accordance with Teledyne instructions.

The UF containers were packaged in accordance with NRC and 00T requirements.  !

This n.6aterial was transferred to Goodyear Atomic on Nuclear Transaction Report

• No. 40 {NRC 741 Form, dated 9-27-85 from XGG to BXA).

The removal of all DOE owned contaminated equipment was completed by 30 October }

1985. A succary of the removals is presented in Enclosure 3). The parts for j shipment to Teledyne Isotopes were stored in a secured area for a later pick up. ,

l The radiation survey of the ATC facility was conducted af ter the removal of cll -

contaminated hardware. The areas surveyed are shown on the map presented in Enr.iosu re 2). Results of the direct radiation measurements are presented in inclosure 4). These results indicated there is slight alpha contamination of the floor in three specific areas (Decontamination area, rotor cut up area and power hacksaw area) where chemically incrt compounds of uranium penetrated into the concrete and cculd not be removed by scrub and mop procegures. Contanination is well below the maximum pemissible of 15,000 cpn Alpha /100 CM . As noted, there was no measurable Beta or Ganma radiation.  ;

l Page Four Results of the floor wipe tests are presented in Enclosure 5). These results indicated slight contamination of the floor in the rotor cut up area, de-contamination area, power hacksaw and waste barrel storage area. It should be noted that the normal background count was 0 to 4 cpm as specified in Note 3 so the measured readings at 4 cpm or lower were not considered significant.

This report does not include data on outside air monitoring, water effluent, or personnel related items such as film badges, urine samples, and physicals.

These records have been retained by Industrial Hygiene and Safety. D/131.

?b. f F D Yoder, D/486 rks cc: D.E. Gleghorn D/131G D.C. Cully D/486C D.D. Seemann D/3920 -

E.P. Prentice D/301D P.R. Rosio D/537 WFL J.J. Adams D/5380 R.D. Lilley D/486C l

- O O Enclosure.1 UJP-823 UF INVENTORY

SUMMARY

6

~

REPORT NUMBER GRAMS - UF 6

YEAR JP < UJP BEGINNING ADDITIONS REMOVALS ENDING 1/

1974 1234 821 49454.8 49454.8 1975 1908 819 49454.8 169.9 28:26.1 20898.6 1976 2488 811 20898.6 25499.0 1l52.6 45245.0 1977 3229 812 45245.0 499.1 f.537.7 43206.5 1978 4066 813 43206.5 25068.7 f.8962.5 39312.8 1979 5436 814 39312.8 25250.1 18330.2 46232.6 1980 6418 815 46232.6 84.4 46317.0 1981 7352 816 46317.0 25067.0 17708.4 53675.6

~

1982 8551 817 53675.6 182.0 25.8 53831.8 1983 17589 818 53831.8 24824.0 33783.5 44872.3 1984 18358 820 44872.3 165.0 6863.4 38173.9 1985 -

822 38173.9 38173.9 s

-1/ Report Numbers with prefix "JP" are classified. These reports were declassified and issued new numbers with prefix "UJP" in November 1985. Copies of the "UJF" reports may be obtained from D.E. Gleghorn, 0/131/G.

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, '( ) Enclosure 3 UJP-823 Page 1 of 1 l CONTAMINATED PARTS REMOVAL

SUMMARY

GAC 81LL DATE , DESTINATION Of LADING NUMBER 59979 9-17-85 Martin Marietta, Oak Ridge. Tennessee 59980 9-27-85 Goodyear Atomic, Piketon, Ohio 4

59983 9-30 85 Goodyear Atomic,- Piketon, Ohio 59982 9-30-85 Goodyear Atomic, Piketon, Ohio 59985 9-30-85 Goodyear Atomic, Piketon, Ohio 59916 10-18-85 Martin Marietta, Oak Ridge, Tennessee  ;

59920 10-31-85 Goodyear Atomic, Piketon, Ohio page b

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. O O Enclosure 4 UJP-823 Page 1 of 1 DIRECT FLOOR SURFACE RA0!ATION MEASUREMENT RESULTS 1/

BETA-GAMMA ALPHA CORRECTED LOCATION 2/

~ READING ~3/ READING 4/ ALPHA 5/ 2 (mR/HR) (CPM) ~ ,(CPMi10D CM )

Hood and Cut Off Saw 0 0 0 stass Spec Lab b 0 0 De' contamination Area 0 500 to 1100 795 to 1749 Lab. Hood-Filter Vent (2nd Floor) 0 0 0 UF6 Storage Area 0 0 0 Rotor Cut Up Area 0 400 to 1500 636 to 2385 Door #4 0 0 0 AGC-1 Gas Stand Area 0 0 0 AGC-2 Gas Stand Area 0 0 0 AGC-4 Gas Stand Area 0 0 0 Column Cut Up Area 0 0 0 Power Hacksaw Area 0 300 477 Parts Storage Area 0 0 0 l Waste Barrel Storage Area 0 0 0 l

Outside Casing Storage Area 0 0 0 1 1/ Measurements were conducted November 6 and 7,1985 2/ Refer to Enclosure 2) Map for Locations.

3/ Beta-Gamma readings were made using Mint-Rad II, Radiation Monitor, S/N 20-0982.

Manufacturer's calibration.

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4/ Alpha readings were made using an Eberline Alpha Counter, Model PAC 45. The Instrument was calibrated on November 6,1985 using Eberline Standards 592-245.

Calibration results were as follows:

Standard Instrument (CPM) (CPM) 237 300 1190 1000 2

5/ Corrected Alpha (CPM /100CM ) were obtained by multi ging the Alpha readings by 1.59 since the actual area cf the detector was 63 C R$ . i.59

..' Enclosure 5 VJP-823 Page 1 of 1 FLOOR WIPE TEST RADIATION MEASUREMENT RESUI.TS ~ 1/ ,

l LOCATION -2/ , ALPHA READINGS 3/

l (Average - CPMT i

Door #1 3 Door #2 3 Door #3 2 Door #4 3

' Lobby Door 3 Mass Spec Lab. Door 4 AGC-1 Gas Stand Area 3 AGC-2 Gas Stand Area 3 AGC-4 Gas Stand Area . 1 Hood and Cut Off Saw 3 Rotor Cut Up Area 34 Decontamination Area 31 Cuiumn Cut up Area 2 Power Hacksaw 7 Parts Storage Area 2 Waste Barrel Storage Area 12 1/ Wipe Tests were conducted November 6, 1985. Each wipe area was 100 CH2 .

2/ Refer to Enclosure 2 Map for locations

-3/ Alpha Readings were made using an Eberline Scintillation Detector, Model LASS-l. The detector was calibrated November 6,1985 using Eberline Standards 592-245. Calibration results were as follows: -

STANDARD INSTRUMENT (CPM) (CPM) AVERAGE 237 237 237 274 237 248 250 237 251 237 239 BLANK 0 2 0 4 2 0 0 0 3

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UJP-823 Page 1 Of 1

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