ML20046C724
| ML20046C724 | |
| Person / Time | |
|---|---|
| Issue date: | 08/05/1993 |
| From: | Mccann G, Wideman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20046C723 | List: |
| References | |
| REF-QA-99990003-930805 99990003-93-13, NUDOCS 9308120009 | |
| Download: ML20046C724 (11) | |
Text
{{#Wiki_filter:* U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 99990003/930S(DRSS) Docket No. 070-000198 (terminated) License No. SNM-175 (terminated) Licenses No. 34-000999-01 through 34-000999-09 (terminated) License No. SMB-038 (terminated) Licenses No. C-3680, C-3758, C-4206, C-4989 (terminated) Facility: Union Carbide Corporation Parma Research Laboratory 12900 Snow Road Parma, Ohio Inspection At: UCAR Carbon Company, Inc. (a former Union Carbide Corporation facility) 12900 Snow Road Parma, OH 44130 Inspection Conducted: June 21-22, 1993 .I Inspector: t D. iedema6 Datd Senior Health Physicist Approved By: -b
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.:f, /f93 f George' M. McCann, GTif [ Tate / Fuel Facilities and De:or aing Section Inspection Summarv Inspection on June 21-22. 1993 (Recort No. 99990003/93013(DRSS)) Areas Inspected: This special inspection included a review of the former i licensee's activities associated with the decontamination and remediation of their previous manufacturing, processing, and research\\ development areas of the building. This inspection was in response to 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 the facilities may have a potential for residual radioactive contamination. Due to the lack of decontamination and decommissioning documentation in the Union Carbide Corporation (UCC) retired license files, the NRC concluded that onsite surveys were necessary. 9308120009 930805 REG 3 GA999 EMVUCARC 99990003 PDR
Results: The NRC inspector identified low levels of fixed uranium contamination on the floor of the former licensee's machine shop and manufacturing building (No.111), and NRC regulated source materials were found in several laboratories. In addition, several consumer products containing natural source materials were identified. The inspector did not identify any radiation levels above natural background outside the facility. Based upon'the inspection findings, it was concluded that the facility was not -i decontaminated to levels below the current NRC release criteria. L p I i l 1 2 \\
DETAILS 1. Persons Contacted
- Vicki Vesel, Senior Administrator, Health and Safety, UCAR Carbon Co.
- Roger M. Flowers, Director, UCAR Carbon Co.
- J. W. Davis, Senior Engineer, Umetto Reclamation Corp.
Todd T. Brady, R.T., Cuyahoga County Board of Health @ James Moon, Project Manager, UCC
- Attended the exit meeting conducted on June 22, 1993.
- Telephone conversation conducted on July 14, 1993, regarding the results of the smear tests taken on the day of the inspection.
0 Telephone conversation regarding inspection results on July 5,1993. 2. Backaround There were several licenses that authorized regulated activities at this i site: a. License No. SNM-175 was issued to Union Carbide Corporation for possession of <500 grams (0.5 kg) of enriched uranium-235 at their facility located at 12900 Snow Road, Parma, Ohio. The authorized activities included fabrication or special nuclear material into uranium-graphite fuel elements then transferred to i other licensees for testing. i b. License No. SMB-038 authorized natural uranium and thorium up to 200 lbs, to be used in graphite fuel studies. At the time of an AEC inspection on June 20, 1963, the licensee possessed 5 lbs. of UF and 1,000 grams (1 kg) of thorium pellets. s c. Source Material License No. C-3680 was issued on March 11, 1957, and authorized 200 lbs. of thorium compounds; this license expired { on April 30, 1959. d. License No. C-3758 was issued on June 28, 1957, and authorized 50 lbs. of uranium oxide; this license expired on July 1,1958. l e. License No. C-4206 was issued on July 25, 1958, and authorized 100 lbs. of refined source materials; this license expired on j December 31, 1959. i f. License No. C-4989 was issued on January 18, 1960, and authorized i 200 lbs. of refined source materials; this license expired on j January 31, 1961, and was superseded by Source Material License i No. SMB-038. j g. Byproduct Material Licenses No. 34-00999-01 through 34-00999-08 (except -05) were terminated or expired at the time of the issuance of a broadscope license, License No. 34-00999-09, on 3
January 11, 1960. This license authorized any byproduct material with the atomic numbers between 1 to 83, along with 1,090 grams (1.09 kg) of uranium-238 and 100 grams of thorium-232. The -05 license authorized curie quantities of cobalt-60 to be used in an underground irradiator. On February 9,1982, the licensee submitted an NRC Form 314, " Certificate of Disposition of Materials," and indicated that no materials were procured and also indicated that all materials were transferred to J. L. Shepherd and Associates, California License No. 1777-70 (see Attachment A). Based upon this information, the NRC terminated this license on March 23, 1982, without requesting a close-out radiation survey by the licensee and without conducting a confirmatory radiation survey. During the license file review by ORNL, references were made in the terminated license file that disposal of contaminated waste materials were made in an on-site incinerator and/or burial in a specified area. The NRC contractor also concluded that, due to the way that the radioactive material was used, there was a potential for a release and the on-site buildings could have been left with contamination. The NRC contractor also concluded that there was a possible inappropriate disposal or abandonment of contaminated waste material and confirmatory radiologic surveys were not conducted by the NRC. 3. Facility Status UCAR Carbon Company is a joint venture between Union Carbide Corporation and Mitsubishi and joint ownership is 50% between both parties. UCAR Carbon Company manufactures carbon and graphite electrodes for electric arc furnaces for the steel industry. The entire site is 57 acres (230,622 m2) and the building is approximately 300,000 ft2 (27,870 m2); the former fabrication and manufacturing area (Room 111) where contamination was found is approximately 30,000 ft2 (2,787 m2). Currently, this area is not occupied full-time by employees. The surrounding neighborhood is a mixture of commercial and manufacturing facilities and the nearest residence is approximately mile (.402 km) away. 4. Indeoendent Measurements The inspector conducted radiologic surveys in and around the former manufacturing areas in Room 111 and in the following former research laboratories and radioactive storage areas: R-20. H-10, H-11, H-13, H-17, G-1 through G-4, G-9, G-14, G-15 & 15A, G-16 through G-18A, F-20, D-4 & 6, B-14, A-20, C-6 through C-8, E-1, E-7 through E-9, and E-19. The areas surveyed included locker rooms, restrooms, hallways, research laboratories, offices, former manufacturing areas, basement areas, parking lot, and building down spouts and loading dock. The inspector noted that some remodeling of the facility has occurred during the past 10 years. The current property owner did not maintain records of the disposition of the building rubble and equipment that was removed during 4
the remodeling. The NRC inspectors radiologic surveys of the parking lot and adjacent property did not identify any radiation levels above natural background. Radiation surveys conducted in Room H-10 and C-6 indicated elevated radiation levels above natural background. Further investigation by the inspector showed that these laboratories contained several consumer products \\ items and NRC regulated source materials containing radioactive material which included (1) a radium-226 luminous clock dial measuring 2,500 microrads/ hour {25 pGy/h) (beta + gamma) on contact, (2) a glass tube containing source materials measuring 200 microrad/ hour {2.0 pGy/h), (3) an insulation cloth containing source materials measuring 80 microrad/ hour {.8 uGy/h), (4) 5 containers containing 25 grams each of uranium oxide (U,0,) measuring 270 microrad/ hour {2.7 pGy/h) on contact, and (5) one 40z. container of thorium nitrate. It was concluded that these source materials are authorized under 10 CFR 40.13 and 40.22. i Independent radiation surveys were performed with a Victoreen, Model 190 portable survey instrument with a Model RP-1 pancake probe, NRC Tag No. 042444 which was calibrated on January 22, 1993, and an Eberline ESP - 4 Alpha scintillation counter, NRC Tag No. 33846, calibrated on January 1, 1993. An instrument response check with the Victoreen, Model 190 was made with a.006 pCi (222 Bq) thorium-230 check source and showed 2,900 counts per minute (cpm) which equates to 600-700 microrad/ hour (grad /h{ beta + gamma}) and a 1 pCi (37 kBq) cesium-137 check source showed 19,000 cpm which equates to 2.8 millirads/ hour (mrad /h{ beta + gamma}). Prior to the radiation surveys both instruments were also checked for constancy with a 2.0 pCi (74 kBq) natural uranium check source. Both instruments responded as expected. Attachment B of this report shows locations that were surveyed and Attachment C shows direct radiation l measurement and smear test re.sults. Background measurements in the parking lot of this facility with the l Victoreen, Model 190 showed 40-50 cpm which equates to 10-20 grad /h and 0.1-1.0 cpm was measured with the Eberline ESP alpha meter. Random i measurements on contact with the floor of room 111 showed low level contamination in the south-west corner that was approximately 16" X 24" that ranged from 1,200 to 2,800 cpm (beta + gamma) and 5-200 cpm alpha. The maximum dose rate found in this area equates to 1,120 grad /h {11.2 uGy/h} and the maximum fixed alpha contamination was approximately 200 times above background. All other areas in room 111 were within normal range of background. Smear tests were taken on various areas that showed j elevated radiation levels. These smears were analyzed in the Region III laboratory and indicate that the contamination is not removable. In conclusion, the inspectors direct radiation measurements indicate that i the low level contamination that remains on the floor in the former manufacturing area of room 111 exceeds the NRC release criteria for release of facilities for unrestricted use. The NRC limit for release of a licensed facility for unrestricted use is 1,000 dpm (16.6 Bq)/100 { cm2 (removable), 5,000 dpm (83.3 Bq)/100 cm2 (average over 1 m') and j 15,000 dpm (250 Bq)/100 cm2 (maximum) and direct radiation measurements 5
- y/hr} (average) and 1,000 prad/h not to exceed 200 prad/h {2.0 G
{l0 nGy/h} (maximum) above natural background when measured at 1.0 cm from the surface. This criteria is described in " Guidelines for Decontamination of facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licensees for Byproduct, Source, or Special Nuclear Material" dated August 1987. i 5. Burial Site UCC's license application dated April 1959 stated that they plan to bury i toxic, unstable, and possibly radioactive materials. Records of the l' burial site were maintained by the current owner of the property. These records indicate that the only materials that were buried were water and air reactive chemicals, e.g., sodium and potassium reactive chemicals. The records did not indicate that radioactive materials were included in the burials. The use of this burial site was discontinued.in the 1960's and was capped about this same time. This burial site is known as the Auxiliary Chemical Reacting Site and is located North of the auxiliary building. The burial site is approximately 10 ft X 10 ft X 6 ft deep and is covered with a concrete cap. The inspector's radiation surveys of this area did not identify any radiation levels above natural ambient background. The inspector concluded that radioactive materials were not buried at this site. 6. 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 current property owner representatives that the independent radiologic survey indicated that portions of the former Union Carbide Corporation machine shop and fuel processing facility (Room 111) did not meet current NRC criteria for release of facility for unrestricted use as described in the NRC document " Guidelines for Decontamination of facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or l Special Nuclear Material" dated August 1987. The NRC inspector also emphasized the point that this survey was not complete and all t encompassing and consideration should be given to have Room 111 characterized for further residual contamination. The current occupant committed to restrict access to the contaminated area of Room 111 and i make arrangements to properly dispose of the various radioactive consumer products and source materials found in Rooms H-10 and C-6. t Attachments: A. NRC Form 314 dated 2/9/82 l B. Locations surveyed C. Survey, smear test results, l and isotopic identification i of certain items ) 6 i
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4 Direct Removable Activity Location \\ Room No. measurement dpm/100cm' cpm beta + gamma alpha beta 1 L-20 former storage area 60 neg. neg. 2 H-10 former research lab 60 H-10 various consumer 800 neg. neg. 3 products 4 H-17 former laboratory 50 5 H-13 former laboratory 50 G-16,17,18 &l8A 50 6 G-15A former source storage 55 7 pit 8 G-1,2,3,4,and 9 50 9 F-20 former storage area 50 10 E-1,7,8,9 &l9 former labs 50 11 D-4 & 6 former laboratories 50 12 A-20,C-7 & 8 former labs 50 13 C-6 former laboratory 65 Source materials found in 1,350 14 lab cm 1 former general 60 15 area) manufacturing area 16 Room 111 South-west corner 2,800 3.1tl.3 5.7 1.3 17 Around former burial area 50 Parking lot and around 50 18 buildings 19 hallways and restrooms 50 20 air duct in room 111 70 3.7 1.4 16.3 2.4 21 floor drain 50 neg. neg. 22 23 24 25 26 1 27 28 Instrument - Victoreen Model 190 Probe - PP-1 Background = 40-50 com Note: All direct measurement readings include background neg = no removable activity detected Date of survey 6-21\\22-1993 Survey by: D. G. Wiedeman ATTACHMENT C j rAosj or_2-PAGES
Direct Removable Activity 2 Location \\ Room No. measurement dpm/100cm cpm alpha alpha beta 1 L-20 former storage area 1-10 neg. neg. 2 H-10 former research lab 1.0 H-10 various consumer 400 neg. neg. 3 products 4 H-17 f ormer laboratory 0.1 5 H-13 former laboratory 0.1 G-16,17,18 &l8A 0.1 6 G-15A former source storage 0.1 pit 8 G-1,2,3,4,and 9 0.1 9 F-20 former storage area 0.1 10 E-1,7,8,9 &l9 former labs 0.1 Il D-4 & 6 former laboratories 0.1 12 A-20,C-7 & 8 former labs 0.1 13 C-6 former laboratory Source materials found in 74 lab m 111 f rmer(general 1.0 15 area) manufacturing area 16 Room 111 South-west co rne r 5-200 3.1tl.3 5.7 1.3 17 Around former burial area 1.0 parking lot and around 1.0 18 buildings 19 hallways and restrooms 0.1 Glass tube found in room neg. neg. 20 H-10 contained natural uranium Piece of insulation cloth found in laboratory H-10 ,y contained natural thorium & uranium + radium-226 Instrument - Eberline ESP-1 Alpha counter Probe - AC-3-7 ( 5 9 an ' ) Background = 0.1-1.0 com Note: All direct measurement readings include background neg.= no removable activity detected Date of survey 6-21\\22-1993 Survey by: D. G. Wiedeman s. __,}}