ML20137U042
| ML20137U042 | |
| Person / Time | |
|---|---|
| Site: | 07001489 |
| Issue date: | 01/16/1986 |
| From: | Pflaum J GOODYEAR AEROSPACE CORP. (SUBS. OF GOODYEAR TIRE |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 26328, NUDOCS 8602190037 | |
| Download: ML20137U042 (11) | |
Text
- - - _
76-/Vl9 k
GOODYEAR A E R O S PA C E C O R P O R AT I O N
/
AKRON. OHIO 44315 RETURN.TO 396-SS PDA s
4 Ref:CIHS.1115P RECEIVED.
1
-3 Mr. W. T. Crow, Acting Chief 2
JAN 21 1986 >
Uranium Fuel Licensing Branch
~ U.S.Nuttus REGutMCRY 7 Division of Fuel Cycle and conss:0't Ifaterial Safety, NMSS
\\
g Nuclear Regulatory Commission g
Washington, D. C.
20555
/
m
SUBJECT:
Termination of NRC Source Material & Special Nuclear Material License No. SNM-1461 for Goodyear Ae ospace 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 c n am na e ma eria s, equipment, manufactured goods and waste, has 6
been 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 GAC 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 Aerospace 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.
We greatly appreciata your assistance in expediting this procedure.
Further work at the WFL facility is required to comply with the Depart-ment of Energy (DOE) directives for facility decomtamination.
If there are any questions concerning this request please contact Q
p b
Corporate Industrial Hygiene & Safety.
DocEHD B
Very truly yours, g
JAN 211986 > 3
.awu 8J. V. Pflaum, CIH uMt h Industrial Hygienist, Sr.
1 DocuTcttag Corporate Industrial Hygiene & Safe Department 131 G1, (216) 796-7299 0
g
/J 8602190037 860116 PDR ADOCK 07001489
((3 C
3 E_ H 0 R_ A 3 p g g November 21,'1985 UJP-823 To:
J V Pflaum, D/131
Subject:
Decontamination of Facilities (UF Related Items) 6 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 Commission, 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 Summary
- 4) Direct Floor Surface Radiation Measurement Results
- 5) Floor Wipe Test Radiation Measurement Results INTRODUCTION This report was prepared in response to Reference 1) and-describes the work 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 (UF ) was used. GAC operated the facility g
under NRC License (Reference 2) to cond0ct performance tests on developmental gas centrifuge machines from 1974 to 1985. The work was initially sponsored by GAC and then funded on DOE Contract DE-AC05-810R20789.
A summary of the UF Inventory at the facility is shown in Enclosure 1).
The 6
largest quantity of material was normal UF. Approximately 300 grams of '1% -
6 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-2 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 UF Storage Area Outside Casing Storage De ontamination Area
Page Two These areas were monitored periodically for any radioactive contamination and recorded in the UF radiation record book that is on file with D.E. Gleghorn, 6
D/131G.
l 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 tentrifuge components such as rotors and columns.
4
.r 2.
Packaging of contaminated DOE owned equipment and parts for shipment per DOE instructions.
3.
Packaging of contaminated GAC owned equipment for shipment to Teledyne Isotopes, Westwood, New Jersey per Teledyne instructions.
4.
Packaging of UF f r shipment to Goodyear Atomic for recycle.
6 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 disassembled according to the i
following procedures:
1.
Applied " Radioactive Material" stickers to contaminated parts and equipment.
1 j
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 3
j 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 areas with detergent water and sponge.
Disposed of wash solution in Teledyne waste barrel.
7.
Disposed of contaminated clothing in Teledyne barrels.
v
. _ _ ~ _
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:
I 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.
l 3.
Cut rotors to 40 inch lengths.
l 4.
Mopped inside surfaces of rotor sections with detergent water solution to re-move visible green uranium oxide residue.
1 5.
Poured contaminated wash water into Teledyne waste barrels.
6.
Placed plastic drop cloth on floor in front of hood and cut off saw area shown 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.
i 9.
Taped boxes shut, identified contents and stickered boxes with " Radioactive Material" labels.
- 10. Rolled up drop cloths and placed in cardboard boxes together with contaminated protective clothing worn by workers.
4 The radioactive contaminated 00E owned equipment that was designated for shipment i
to other DOE installations was packaged in wood boxes. The inside of each wood box was lined with 6-mil thick polyethylene plastic sheet. After 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-DSM and DWLVL-A). These barrels were sealed and weighed in accordance with Teledyne instructions.
l The UF containers were packaged in accordance with NRC and 00T requirements.
This mkterial was transferred to Goodyear Atomic on Nuclear Transaction Report j
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 summary of the removals is presented in Enclosure 3). The parts for shipment to Teledyne Isotopes were stored in a secured area for a later pick up.
The radiation survey of the ATC facility was conducted af ter the removal of all contaminated hardware. The areas surveyed are shown on the map presented in
' ). Results of the direct radiation measurements are presented in i ). 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 inert compounds of uranium penetrated into the concrete and could not be removed by scrub and mop procegures. Contamitation is well below the maximum pennissible of 15,000 cpm Alpha /100 CM. As noted, there was no measurable Beta or Gamma radiation.
i x._...
,.. _, ~,,.. - - -,...,. _ - _,, _, - -,.. _ -.,.,, _.....
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 nonnal 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 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
Enclosure.1 UJP-823 UF INVENTORY
SUMMARY
6 REPORT NUMBER GRAMS - UF6 YEAR JP UJP BEGINNING ADDITIONS REMOVALS ENDING 1/
1974 1234 821 49454.8 49454.8 1975 1908 819 49454.8 169.9 28726.1 20898.6 1976 2488 811 20898.6 25499.0 1152.6 45245.0 1977 3229 812 45245.0 499.1 2537.7 43206.5 1978 4066 813 43206.5 25068.7 28962.5 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 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 "UJP" reports may be obtained from D.E. Gleghorn, D/131/G.
' s.
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e HOOD 8 CUT OFF SAW MASS SPEC. LAB fi$iN HMEM SLDG Si ROTOR CUT UP AREA q X
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ECONTAMINATION AREA l
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h AGC-2 GAS STAND M HOOD _l:
i AGC-1 GAS STAND %
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UF STORAGE AREA 6
AGC-4 GAS STAND L.
I hD00R#4 COLUMN CUT UP AREA 4:
s A
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I 2 DOOR #2 M OR #3:'
fPOWERHACKSAW i
DOOR #1 l'
ute '
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l RADIATION SURVEY MAP ADVANCED TECHNOLOGY CENTER l
+
UJP-823 Page 1 of I HANGAR SPACE ALLOCAT10N1 50 Fi.
ULDG.
- 1) 0FFICES (INCLUDING LOH9Y) 9440 91
- 2) LAB 1535 91
- 3) HIGH DAY: UNDER 20 TON CRANE S460 91
.[llANINE 10660 91 HI".H DAY: SIDE HAY UND(R
- 4) LOW BAY: UNDER 5 TON CRANE
/170 91 Low e4Y: $1Df OAY JND(9 PEllANINE 6870 91
- 5) NAINTENANCE 2465 91
- 6) HANGAS: HIGH BAY 4740" 91 HANGAR:
SIDE RAY 18E00_
91 TOTAL 112600 112/00 FT 1 (H ANGf.R DIMENSIONS:
141' E POO' I
l WASTE BARREL STORAGE.!
I
--,. r.rsm.2 2,q
~f
' ARTS STORAGE !
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NOTE:
DARKENED AREAS DEN 0TE LOCATIONS OF RADIATION SURVEY TI APERTUllE I
CARD Also available On
' Aperture Card g6oa.\\qoo27-op-
UJP-823 Page 1 of 1 CONTAMINATED PARTS REMOVAL
SUMMARY
GAC BILL DATE DESTINATION OF LADING NUMBER 59979 9-17-85 Martin Marietta, Oak Ridge, Tennessee 59980 9-27-85 Goodyear Atomic, Piketon, Ohio 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 9
e
VJP-823 Page 1 of 1 DIRECT FLOOR SURFACE RADIATION MEASUREMENT RESULTS 1/
BETA-GAMMA ALPHA CORRECTED LOCATION 2/
READING ~3/
READING 4/
ALPHA 5/
~
(mR/HR)
(CPM)~~
Hood and Cut Off Saw 0
0 0
Mass Spec Lab 0
0 0
Decontamination Area 0
500 to 1100 795 to 1749 Lab. Hood-Filter Vent (2nd Floor) 0 0
0 UF Storage Area 0
0 0
6 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
Waste Barrel Storage Area 0
0 0
Outside Casing Storage Area 0
0 0
if Measurements were conducted November 6 and 7,1985 2/ Refer to Enclosure 2) Map for Locations.
3] Beta-Gamma readings were made using Mini-Rad !!, Radiation Monitor, S/N 20-0982.
Manufacturer's calibration.
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)
[CP_M)_
237 300 1190 1000 5/ Corrected Alpha (CPM /100CM ) were obtained by multiplying the Alpha readings by 1.59 since the actual area of the detector was 63 CMr.
2 100 CM 1.59 2
=
63 CM
Enclosure S UJP-823 Page 1 of 1 FLOOR WIPE TEST RADIATION MEASUREMENT RESULTS 1/
LOCATION 2/
ALPHA READINGS 3/
(Average - CPM);
Door #1 3
Door #2 3
Door #3 2
Door #4 3
Lobby Door 3
- - ~ ~ - '
4 Mass Spec Lab. Door
__f *. J L. -
3
---~~~~
AGC-1 Gas Stand Area
,, y ;g.e
....__..n----
AGC-2 Gas Stand Area
.47;a N' 3
AGC-4 Gas Stand Area
_.. A 1 1
- n..
3 Hood and Cut Off Saw
.1 G Rotor Cut Up Area
~~{
34 m
31 Decontamination Area
.g.,; ;o Column Cut Up Area oly. ' '
2 Power Hacksaw 7
2 Parts Storage Area
= - --
~ ~ '
12 Waste Barrel Storage Area
= =. - -
1/ Wipe Tests were conducted _Nov,e,mbqLLL985.Each -wipe-area was 100 CM.
2/ Refer to Enclosure 2 Map.for LocadI'" -- - - ~ ~ ~
-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 23?
274 237 248 250 237 251 237 239 BLANK 0 2
0 4
2 0
0 0
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LPDR Di I6E REF.
b MiUR SAFCCUARDS FCIC OTliER DESCRIPTION:
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