ML20046C720
| ML20046C720 | |
| Person / Time | |
|---|---|
| Issue date: | 08/05/1993 |
| From: | Mccann G, Wideman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20046C718 | List: |
| References | |
| REF-QA-99990003-930805 99990003-93-14, NUDOCS 9308120006 | |
| Download: ML20046C720 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 99990003/93014(DRSS)
Docket No. 070-00273(terminated)
License No. SNM-252 (terminated)
Licenses No. SMB-366 & R-109 (terminated)
Facility:
National Carbon Company E
Division of Union Carbide Corporation i
200 North Town Street Fostoria, Ohio Inspection At:
National Electrical Carbon Corp.
(a former Union Carbide Corporation facility) 200 North Town Street i
Buildings 61 A, B and 63.
Fostoria, OH 44830 Inspection Conducte -
June 23, 1993
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Mar %
8 Inspector:
iedeman Date' Senior Health Physicist Approved:
D.
hfu hg[93 G. M. McCantf, Chief Date
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Fuel Facilities and Decc.nmissioning Section Insoection Summarv Insoection on June 23. 1993 (Report No. 99990003/93014(DRSS))
Areas Insoected:
This was a special inspection which included a review of the former licensee's activities associated with the decontamination and remediation of their 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 i
contractor, Oak Ridge National Laboratories (ORNL). On the basis of the
,l information in the retired license file, ORNL concluded that these facilities may have a potential for residual radioactive contamination. Due to the lack of adequate decontamination and decommissioning documentation for certain buildings in the Union Carbide Corporation (UCC) retired license files, the NRC contractor concluded that the former facilities used by UCC could have significant amounts of residual contamination and some likelihood that outside contamination could have occurred.
9308120006 930805 REG 3 GA999 EMV*****-
PDR 99990003
Results: The NRC inspector identified low levels of predominantly fixed uranium contamination, with a small fraction being removable, on the floor and countertops inside a walk-in safe in Building 63. The inspector did not identify any radiation levels above natural background outside the Town Street facility; however, contamination was found in a storm drain between Buildings 101 and 102.
These findings are documented in NRC Inspection Report No. 99990003/93016(DRSS).
Based upon the inspection findings, it was concluded that the walk-in safe in Building 63 was not decontaminated to levels below the current
.J release criteria.
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DETAILS i
1.
Persons Contacted
- Michael Wentzel, Manager, Health, Safety and Environmental Affairs, l
National Electrical Carbon Corporation (NECC)
Dennis Zullig, Director of Manufacturing, NECC l
- R. L. Halsey, Senior Engineer, NECC i
Harold Bogatz, Esq., Robbinsville Development Ltd. Partnership (current owners of Building 101 and 102)
- Attended the exit meetiag conducted on June 23, 1993.
- Telephone conversation conducted on July 15, 1993, regarding the results of the smear tests taken on the day of the inspection.
2.
Backaround License No. SNM-252 was issued to National Carbon Company, a Division of Union Carbide Corporation, on October 3,1958, for possession of 350 grams of enriched uranium-235 at their facilities located in Niagara Falls, New York and Fostoria, Ohio. Subsequent amendments to the license in 1963 authorized up to 2,000 grams (2.0 kg) of enriched uranium (see Attachment A). The authorized activities included 1
fabrication of special nuclear material into uranium-graphite.
License No. SMB-366 authorized fabrication of carbon and graphite forms containing source material (uranium and thoriuu, oxides). During the' middle 1950's to early 1960's, the licensee also manufactured carbon rods for arc lighting using core materials of rare earth compounds containing less than 0.25% of natural thorium (by weight) under AEC l
license R-109.
This license expired on April 30, 1961.
During the license file review by ORNL, they concluded that, due to the i
way that the radioactive material was used, there was a potential for an off-site release and the on-site buildings could have been left with
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residual contamination. The NRC contractor also concluded that' there was a possible inappropriate disposal or abandonment of contaminated waste material and the close-out survey conducted by the licensee of Building 61 contained procedural deficiencies and did not include areas outside the buildings.
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Facility Status National Electrical Carbon Corp. purchased the property and buildings from Union Carbide Company on December 12, 1986.
The company currently manufacturers various carbon products used in industrial applications.
Most manufacturing is currently being done in Building 61 and an employee credit union now occupies one office in Building 63; all other offices and former laboratories in Building 63 were vacant.
Former licensed activities were conducted in Buildings 61, 61A, 61B, 610, 63, 50, 101, and 102 (see Attachment B).
Buildings 101 and 102 were sold to Robbinsville Development Ltd. Partnership of Robbinsville, New Jersey, 3
on May 24, 1989. Building 50 was razed in 1989.and now the only buildings that remain that licensed activities were conducted are Buildings 61, 63, 101, and 102.
Buildings 101 and 102 are vacant and have been since 1985 and 1988, respectively.
Buildings 63 and 61 are being used by National Electrical Carbon Corp. The surrounding neighborhood is a mixture of commercial and manufacturing facilities and single family residences.
4.
Independent Measurements The inspector conducted radiologic surveys in and around the former i
manufacturing areas in Building 61 and research laboratories in Building 63.
The areas surveyed included restrooms, hallways, research laboratories, offices, former manufacturing areas, basement areas, t
parking lot, and building down spouts and loading docks.
The inspector noted that some remodeling of the facility and razing of buildings 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 the remodeling. The NRC inspector's surveys of the parking lot and adjacent property did not identify any radiation levels above natural background.
Radiation surveys were performed with a Victoreen, Model 190 portable survey instrument with a Model RP-1 pancake probe, NRC Tag No. 042444, calibrated on January 22, 1993, and an Eberline ESP 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 j
minute (cpm) which equates to 600-700 microrad/ hour (prad/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 / hour { 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 C of this report shows 8 locations and measurement results and Attachment D shows direct radiation measurement and smear test results of areas that showed elevated readings above natural background. Radiation surveys conducted in the walk-in safe on the first floor of Building 63 showed elevated radiation levels above natural background. The alpha contamination was approximately 100 times above natural background and the beta + gamma readings were approximately 24 times-l above background. Further investigation by the inspector showed that several areas on the floor and on cabinet tops inside the safe had low levels of predominantly fixed contamination with a small fraction being removable. 4 Background measurements taken in the parking lot with the Victoreen, Model 190 showed 40-50 cpm which equates to 10-20 prad/hr and 0.1-1.0 cpm (alpha) was measured with the Eberline ESP alpha meter. Random measurements on contact with the floor inside the walk-in safe showed low level contamination in the southwest corner near the door 4 i [ i i
that was approximately 4" X 4" that ranged from 1,240 to 1,280 cpm (beta + gamma) and 60-150 cpm (alpha) on contact. The maximum contact reading of 1,200 cpm equates to 28,000 dpm {465 Bq}/100 cm2 which is in ? excess of the NRC release criteria and the fixed alpha contamination was 150 times above natural background. All other areas in Buildings 61 and 63 were within the normal range of background. Dry smear tests were taken on various areas that showed elevated radiation levels. These smears were analyzed in the Region Ill laboratory and indicate that the contamination is predominantly a beta emitter and the contaminant is fixed; however, a small fraction was removable. In conclusion, the inspector's direct radiation measurements indicate that the low level contamination that remains on the floor and on top of the cabinets inside the walk-in safe in Building 63 exceeds the current NRC release criteria for release'of facilities for unrestricted use, j The NRC limit for release of a licensed facility for unrestricted use is 1,000 dpm {16.6 Bq}/100cm2(removable), 5,000 dpm {83.3 Bq}/100 cm2 (average over 1 m') and 15,000 dpm {250 Bq}/100 cm2(maximum) and direct radiation measurements not to exceed 200 prad/hr {2.0 gGy/h} (average) and 1,000 rad /hr {l0 gGy/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. 5. Exit Meetina t 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 survey results indicated that portions of the walk-in safe in Building 63 did not meet current NRC release criteria. The property owner was also informed that this survey was a limited in scope and should consider conducting additional surveys of heating and air exchange system in Building 63. The building occupant committed to t restrict access to the contaminated area of the walk-in safe, post the area with signs stating " Caution Radioactive Materials," and notify employees with access to the safe that the area is now restricted. Attachments: A. AEC license dated 10-3-58 and memo dated 5-22-63 B. Locations where former licensed activities were conducted C. Locations surveyed and direct radiation measurement results D. Direct radiation survey and smear test results of selected areas 5 1 m +=
ATOMIC ENERGY COMMISSION 3 y i 1, i SPECIAL NUCLEAR MATERIAL LICENSE L i ( h 9 khg l 1, Port 70, "Special Nuclear Material Regulations," o license is hereby issued authorizing the licensee h Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of Federal Regulations, Chapter ; h[p[{ l gl 3 l to receive and possess the special nuclear material designated below; to use such special nuclear l material for the purpose (s) and < 1 the place (s) designated below; and to transfer such material to l l i persons authorized to receive it in accordance with the regulations in said Part. This license shall l E , [ to all applicable rules, regulations, and orders of the Atomic Energy Commission now or herea be deemed to contain the conditions specified in Section 70.32(a) of said regulations, and is subject l effect and to any conditions specified below. j [M:$ l~ Licensee l 3. License No. I 1.Name I-National Carbon Company l 4 A Division of Union Carbide Corporation I
- 2. Address 47; MhtedMmt l
l September 30,1961_._ I New York 17, N. Y. F f S. Docket No. ( l i i_70-273.._.- j
- 6. Special Nuclear Material
- 7. Maximum quantity of special nuclear material. I i
Uraniu:n enriched in the s lic$1s ne t U-235 isotope. , 350 grams of contained U-235 l l y ,..,; A.uthor,iz,ed use 8 n l f For use'in'research'and' development'activitie' 'iri accordance'with'the ~~ s j procedures described in the licensee's application of July 28, 1958. [ 9. Quantity of special nuclear material allocated to licensee pursuant to Section 70.31(b) of said part { l a None. CONDITIONS -l
- 10. Unless otherwise specified, the authorized place of use is the licensee's address stated in Item 2
) above. ( g I jdJ. Authorized place of use: The licensee's development Imboratories of f, National Carbon Coc:pany located.<st 3625 Highland Avenue, Niagara Fans, 'd g New York, and Town Street, Fontoria, Ohio. A .. b for the U. S. ATOMIC ENERGY COMMISSION l ' Date of issuonee Ob A__o -mm a w mj ATTACHMENT A PAGE_/ of$~PAGES
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1 - ,grg } ~ "3 W 3j "i ?~ , hM 4-UNITED STATES GOVERNMENT - ,s 3' i --s ' - dvem0Tanaum y ~ Donald A. Itassbaumer, Chief DATE: lo MY p p g Source & Special Itaclear Materials Branch, DLR { rROM ' Charles D. Inke, Chief Jk Criticality Evaluation Branch, DLR suujncT: NATIONAL CARDON, FOS 20RIA, OHIO, AMENIMENT TO SN4-252, SUPPLUSTIARY INFOR4ATION TWX DATED MAY 21, 1963, DOCKET 70- 273. SYMBOL: DLR:FKD s We have reviewed the subject supplementary information which satisfactorily resolves the issues delineated in our memorandum dated May 15, 1963. By application dated July 6,1962, (amendment to increase from 500 gra=s to 1 kg cf U-235), page 2, paragraph 7, national Carbon specified contract material and license material is not handled or processed in the same area at the same time. 2his clause is still applicable to the subject amendment (increase from 1 kg to 2 kg U-233), however, the subject license material vill be stored with contract material in storage. We have no objection to this combination since arrangements within the cabinets described by application dated March 4, 1963, specify safe volume (3.6 liters) for individual units based on hble 4 vith 16 inches center to center minimum spacing between units. 2bese criteria are in accordance with TID-7016, Revision I, %ble 5, which specifies no limit per isolated linear or plain array of Ibble h units with 16 inches center to center spacing between units. Closer review of sketch IIE-683-D1 of the March 4, 1963 application reveals a ring stand support for each unit, thus negating any request on our pcrt for physical means to maintain the specified storage conffguration. i i s-__ T p. f J .p1 c
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BLDG. 61 ORTH \\ 0lY ) Q DRY CHEMICAL BLDG. 618 N f; BLOG. 61C ) Q CO2 l a \\ 0 lO /> /0 /> fy Q Q AIR WATER j% l0 l0 FOAM (WHEELED) i i IV BLDG. 61A \\ l@ DR1' CHEM; CAL (WHEELED) Ll* j @/ CO2 (WHEELED) ,f,g \\ it HALON (exa 1 iv g l /* &FI! \\ HOSE llb ^ 8 l ,y @ /> SPRINKLER CONTROL 1lE \\ EYE WASH STATION E \\ ' Y \\ U / fat 4 H l L$ 13 /0 STRETCHER 1 ) FIRE CALL STATION l /> pp jo FIRE BLANKET agl ' '*",g>l } CALL BOX NUMBER 0 /7 A M j@ jo f( NOTE-All units of measurement ,-1 ) /2- [ are in microR/ hour /d All readings include /0 background radiation /k l Background =10-20microff l l <tsjga ger; oate or survey 6/23/93 d /* r /t /8 'E /* .t i b /7 I \\ [ cxa) BLOG. 28 AITACHMENT C /f /D PAGE_/ o(1PAGES je ,y g i
BLDG. o3 a /1 E 1st FLOOR 2nd FLOOR fo /0 fy llll & FIRE E)(IT P{[.an,hg y-/G#f/A I/ /( j(' F n (: [ g- ? ?I 1gi ( /1 /( l i[_f R ~ i o /{ jo N 0 ib
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(/sc gos u 50,jplW l} l^ ,'( I" /0 /$ I r! / s ,o = e, = jf /L b 10 gs/f /( /0 10 7 i /L '( if @~ l g->(, ( /[ /[ ,( y g/y (\\g W c, /o v^'. # h IIHilll 2, g,[ 11111111 l@ l /0 "l l 1111llll // /0 /o @ /f f Q DRY CHEMICAL SPRitJKLER COtJTROL CO2 EYE WASH STATIOtJ STRETCHER AIR WATER FIRE CALL STATIOtl FOAM (WHEELED) CALL BOX tJUMBER DRY CHEu/ CAL (WHEELED) fJOTE-All units of measurement are in units 4 YUUY CO2 (WHEELED) y All readings include background radiatic HALON Background = 10-20 microR/ hour Date of Survey 6/23/93 HOSE
l-I Direct Removable Activity Smear Location measurement dpm/100cm' Number cpm beta + gamma alpha beta 1 Bldg.63 air vent 60 3.611.3 4.8 1.2 Bldg. 63 walk-in safe floor 1,280 25.514.0 50.614.8 l 2 Bldg. 63 walk-in safe 160-170 25.514.0 50.614.8 3 cabinet 4 Outside buildings 61 and 63 40-50 I Inside building 61 and 61A 40-50 5 storage areas Bldg. 62 40-50 6 offices / laboratories I Bldg.63 restrooms and 40-50 7 hallways Bldg. 61 offices and general 40-60 8 work areas and former processing areas 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 l 25 26 27 t 28 r Instrument - Victoreen Model 190 Probe - Model RP-1 pancake Background = 40-50 cpm Note: All direct measurement readings include background j Date of survey 6-23-1993 Survey by: D. G. Wiedeman ATTACHMENT D PAGE) d[PAGES t}}