ML20057G014
| ML20057G014 | |
| Person / Time | |
|---|---|
| Issue date: | 10/07/1993 |
| From: | Mccann G, Wiedeman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20057G008 | List: |
| References | |
| REF-QA-99990003-931013 99990003-93-28, NUDOCS 9310200084 | |
| Download: ML20057G014 (16) | |
Text
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4 U.S. NUCLEAR REGULATORY COMMISSION REGION III
(
Report No. 99990003/93028(DRSS)
Docket No. 040-00029 (terminated)
License No. STB-00049 (terminated)
License No. C-2210 (terminated) l Facility: McDonnell Aircraft Corporation McDonnell Douglas Corporation Robertson and St. Louis, M0.
i Inspection At:
McDonnell Douglas i
l McDonnell Aircraft Company l
Building 32 (Robertson, Mo.)
{
Buildings 102 & 27 (St. Louis, Mo.)
1 Building 91 (St. Charles, Mo.)
Mailing:
P.O. Box 516 St. Louis, Mo. 63166-0516 l
Inspection Conducted:
September 14, 1993
/#~7~
Inspector:
7 m
s l
D.
G'. Wiedemin Date Se r Health Physicist
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Approved:
fh MM]f p
/O-7-i3 i
e G.E.Mcgann,ChieffuelFacilitiesandDecommissionin[g-Date
/c Section inspection Summary inspection on September 14 1993 (Report No. 99990003/93028(DRSS))
i Areas Inspected:
This was a special inspection of McDonnell Douglas Corporation a former Atomic Energy Commission (AEC) Source Material licensee.
The inspection included a review of activities associated with the decontamination and remediation of former manufacturing and processing areas of Buildings 32, 27, 91 and 102.
This inspection was part of an NRC project in which an evaluation of approximately 17,000 retired licenses was conducted by an NRC contractor, Oak Ridge National Laboratories (ORNL).
On the basis of the information in the retired license file. ORNL concluded that these facilities may have a potential for residual contamination.
Due to the quantity of materials used and lack of decontamination and decommissioning l
documentation for certain buildings in the McDonnell Douglas Corporation retired license files, the NRC contractor concluded that the facilities used by McDonnell Douglas could have been left with residual contamination.
It was further concluded that the AEC/NRC did not conduct a final close-out inspection.
l 9310200084 931013 REC 3 GA999 ENVMCDAC 99990003 PDR
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i Results: The NRC inspector did not identify any radiation levels above natural background in the former processing, manufacturing or research areas and outside environs of Buildings 32, 27, 91 and 102.
However, it was determined that during 1968, McDonnell Douglas transferred licensable quantities of stock magnesium-thorium (4% thorium) metal to Washington University. This material had been in storage for the past 25 years in a locked concrete bunker (No.35) at the Washington University, Tyson Research Center.
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p DETAILS 1.
Persons Contacted J. Lindsey Chalk, Manager, Occupational Safety and Environmental Health
- M. Bien, Laser Safety Officer, Occupational Safety and Environmental Health
- Eric Dennison, Radiation Safety, Occupational Safety and Environmental Health
- Vaughn Meister, Group Manager, Occupational Safety and Environmental Health Anna Chatman, Industrial Hygienist, Occupational Safety and Health Administration
- Gary McNutt, Radiological Health Analyst, Missouri State Department of Health John Eichling, Ph.D, Radiation Safety Officer, Washington University David Schilling, Manager, Tyson Research Center, Washington University
- Attended the exit meeting conducted on September 14, 1993.
- Telephone conversation on September 27, 1993, regarding the disposition of materials stored at Tyson Research Center.
2.
Backaround AEC License No. C-2210 was issued to McDonnell Aircraft Corporation on December 18,1956 (see Attachment A), for possession of 2,000 pounds of source material (thorium metal aircraft parts) for use in the production of aircraft parts at their facility located in Robertson, Missouri.
This license was subsequently superseded by AEC Source Material License No. STB-00049 for possession and use of thorium at their facility located at the Municipal Airport, St. Louis, Missouri, (see Attachment B).
During the period that licensed activities were conducted (1956-1975) at both facilities, the maximum quantity of source material authorized under the license was 114,000 pounds of thorium.
Licensed activities included machining, milling, drilling, lathe work, deburring and grinding aircraft parts containing thorium. At the licensee's request, License No. STB-00049 was terminated in 1977. According to information provided to the NRC inspector at the time of the inspection, licensed activities were conducted in Buildings 27, 32, 91 and 102,(see Attachment C for building layout and survey results).
During the license file review Dy ORNL, they concluded that due to the former manufacturing processes, a potential for on-site building contamination existed.
The NRC contractor also concluded that an inappropriate disposal or abandonment of contaminated waste material may have occurred.
Further, the files did not contain a close-out survey conducted by the licensee and the AEC did not conduct a close-out survey of the facility prior to termination of the license.
3
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3.
Facility Status Currently Buildings 27, 32, 91 and 102 are being used for a combination of manufacturing, production work, research and office space. The former analytical laboratory area in Building 102 has been remodeled and is now an office area. Buildings 27, 32 and 91 are currently used as manufacturing, machine shops and storage areas.
4.
Indeoendent Measurements The NRC inspector conducted radiologic surveys, with the assistance of a representative from the Missouri Department of Health, in and around Buildings 27, 32, 91 and 102. The areas surveyed included restrooms, hallways, offices, former manufacturing areas, parking lots, building down spouts, storm / floor drains, loading docks and adjacent property.
None of the original manufacturing equipment remains in the buildings.
All surveys of the buildings and outside environs did not show any radiation levels above natural background.
Background radiation measurements taken in the St. Louis area with the Victoreen, Model 190 showed 40-50 cpm and the Ludlum Model 19 microR meter indicated 7-15 microR/ hour (yR/h) (1.5-3.7 nC/kg/h).
Radiation surveys were performed with a Victoreen, Model 190 portable survey instrument with Model RP-1 pancake probe, NRC Tag No. 042444, calibrated on July 28, 1993, and a Ludlum, Model 19 microR meter, NRC Tag No. 011021, calibrated on May 8,1993. A response check of the Victoreen, Model 190 was made with a.006 pCi {222 Bq} thorium-230 check source and showed 2,900 counts per minute (cpm) { beta + gamma}.
The instrument was also checked with a 1 pCi (37 kBq} cesium-137 check source which showed 19,000 cpm { beta + gamma}.
Prior to the radiation surveys, all portable survey instruments were also checked for constancy with a Coleman lantern mantle which contains 0.04-0.07 yCi {1.5-2.6 kBq}
of thorium-232. All portable survey instruments responded as expected.
Attachment C of this report shows locations surveyed and measurement results.
Prior to this inspection, the NRC inspector learned that in approximately 1968, McDonnell Douglas transferred approximately 150 sheets (see photograph in Attachment D) of stock magnesium-thorium to Washington University in St. Louis, Missouri.
This material had been in storage for the past 25 years in a locked concrete bunker (No.35) at the Washington University, Tyson Research Center.
At the time of this transfer, Washington University did not hold a valid ALC source material license.
The NRC inspector concluded that this type and form of source material did not meet the license exemption criteria in 10 Cf R 40.13 (c)(4) because this material is not considered a " finished product or part" and the criteria for possession and use under a general licenso under 10 CFR 40.22 did not apply because the 15 pound maximum possession limit was exceeded.
It was agreed that McDonnell Douglas would immediately make arrangements to properly dispose or transfer the material and would coordinate their efforts with the staff from 4
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Washington University. On September 27, 1993, the NRC Region III office was notified that all remaining source material was transferred to l
Spectrulite Consortium, Madison, Illinois, Illinois License No. 11-01-750-01.
i In conclusion, the inspectors' direct radiation measurements indicate that the former licensed facilities were decontaminated to a level consistent with the current NRC release criteria.
5.
Exit Meetina The NRC inspector met with the individuals identified in Section 1 of this report and summarized the findings of the inspection.
The inspector informed the former licensee representatives that the independent radiologic survey indicated that the facilities appear to meet the current NRC release criteria.
In addition, options for i
transferring or disposing of the magnesium thorium sheets were discussed with the former licensee representatives.
l Attachments A.
AEC license dated 11/18/56 B.
AEC license dated 2/17/70 C.
Locations surveyed and direct radiation measurement results l
D.
Photograph of source material sheets @ Tyson Research Center I
5
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UNITED STATES 4
ATOMIC ENERGY COMMISSION l
wAsmNGTON M. D. C.
l SOURCE MATERIAL LICENSE License No.
M 210 l
Moonell Aircraft Co paration Dated:
D E C 1 ' '"...
Poet Office Box $16 4
St. Louim ), Missouri Attentions Mr. 7. A. Fletcher 2 -
[
Senior Buyer Gentlemens 4
Pursuant to the Atomic Energy Act of 1994 and Section 40.21 of the code of Federal Regulations, Title 10 - Atomic Energy, Chapter 1i Part 40 - Control of Source Material, you are hereby licensed to receive. possession of"during and j
title to t** th;'usand 0,000) pounds of refined source material the term of this license for use in the pmduction of aircraft paM.
This lieer.se perhina to your plant at Robertson, Missouri, only.
1 You are further licensed to transfer and deliver possession of and title to I
refined source material to any person 1icenced by the Atomic Energy Co:muission, within the limits of his license.
l As a condition of issuance of this license, you are required to maintain j
records of your inventories, receipts and transfers of refined source ma-terial.
This license le subject to all the provisions of the Atomic Energy Act of 1994 now or hereaf ter in effect and to all valid rules and regulations of the U. S. Atomic Energy Commission.
Except as herein provided, it is subject also to the provisions of the Commission's proposed regulations, published in the Fede.?al Register July 16, 1955, Title 10, Code of Federal Regulations, Part 20, entitled " Standards for Protection Against Radiation" until such time as said proposed regulations or revisions thereof shall become effective regulations of the Co::rnission.
Notwithstanding Section 20.24(f) of said i
standards, labeling shall not be required for laboratory containers such as beakers, flasks and test tubes, used transiently in laboratory procedures during presence of the user.
Neither this license nor any right under this license shall be assigned or otherwise transferred in violation of the provisions of the Atomic Energy Act of W A.
Thir 1icenne shi :. exM re J'au'YJ 1, 1950.
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Pursuant to the Atomic Energy Act of 1954, and Title 10, Code of Federal Regulations, Chapter 1,
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Port 40, " Licensing of Source Material," and in reliance on statements and representations heretofore r
h made by the licensee, a license is hereby issued authorizing the licensee to receive, possess and impori {
N the source material designated below; to use such material for the purpose (s) and at the place (s) j designated below; and to deliver or transfer such material to persons authorized to receive it in I"y This license shall be deemed to contain the conditions g
cecordance with the regulations in said Port.
Q specified in Section 183 of the Atomic Energy Act of 19S4 and is subject to oli applicable rules, g
!q regulations, and orders of the Atomic Energy Commission, now or hereafter in effect, including Tit h
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to any conditions specified below.
- 3. License No.
Licensee lg STB-49 9f 1.Name McDonnell Douglas Corp.
- 4. Expiration Date id f1 February 28, 197S f
- 2. Address P. O. Box 516 St. Louis, Missouri 63166 i
l@4l S. Docket No.
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- 6. Source Material
- 7. Maximum quantity of source material which b
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- 8. Authorized use (Unless otherwise specified, the authorized place of use is the licensee's address p
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Authorized Place of Use: The licensee's Municipal Airport facility,
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A/s)eeb = Y2 c/m Date of radiation survey-9/14/93 j
Survey Instrument-Victoreen 190, w/10cm* pancake probe Calibration date-1/22/92 Serial No. 699 NRC Tag No. 042444 Background reading-40-50 counts / minute (cpm) (beta + gamma}
Note-All direct radiation readings include background and all surveys conducted outside the buildings were supplemented with a Ludlum microR meter, NRC Tag No. 011021, calibrated on 5/8/93. All readings outside the buildings are in units of microroentgens/ hour (pR/h)%and include background (7-15 pR/h).
Survey by:
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Department of Health Attachment C-Building 32, Rcbertson, Mo.
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l Date of radiation survey-9/14/93 1
Survey Instrument-Victoreen 190, w/10cr2 pancake probe Calibration date-1/22/92 Serial No. 699 NRC Tag No. 042444 Background reading-40-50 counts / minute (cpm) (beta 4 gamma}
Note-All direct radiation readings include background and all surveys conducted outside the buildings were supplemented with a Ludlum microR meter, NRC Tag No. 011021, calibrated on 5/8/93.
All readings outside the buildings are in units of microroentgens/ hour (pR/h) and include background (7-15 pR/h)
Survey by:
D.
G.
Wiedeman, NRC with the assistance from G..
McNutt, Mo.
Department of Health Attachment C Building 27, Level 1,
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Survey Instrument-Victoreen 190, w/10cm' pancake probe Calibration date-1/22/92 i
Serial No. 699 NRC Tag No. 042444 Background reading-40-50 counts / minute (cpm) (beta + gamma}
l Note-All direct radiation readings include background and all surveys conducted outside the buildings were supplemented with a Ludlum microR meter, NRC Tag No. 011021, calibrated on 5/8/93. All readings outside the buildings are in units of microroentgens/ hour (pR/h) and include background (7-15 pR/h).
Survey by:
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G.
Wiedeman, NRC with the assistance from G. McNutt, Mo.
Department of Health l
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