ML20135F494
| ML20135F494 | |
| Person / Time | |
|---|---|
| Site: | 07000139 |
| Issue date: | 03/06/1997 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Cabot D ENGELHARD CORP. |
| References | |
| NUDOCS 9703120422 | |
| Download: ML20135F494 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
WASHINGTord, D.C. 20066-4001 e.,...../
March 6, 1997 j
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Mr. Donald Chabot Senior Environmental Engineer i
Engineered Materials Group Engelhard Corperation Route 152-Plainville, MA 02762
Dear Mr. Chabot:
4 The U.S. Nuclear Regulatory Commission staff has completed a review of i
remediation activities and the results of radiological surveys of buildings at the Engelhard facility in Plainville, MA. NRC staff reviewed the following l
two documents:
- 1) Engelhard's " Final Status Survey Report, Survey Units 1 and 2" for the building interiors at the Plainville, MA, site, originally submitted in November 1996; and i
- 2) Oak Ridge Institute for Science and Education Letter Report, " Confirmatory Survey for Survey Units 1 and 2, Interior of Building 2, Engelhard Plant, i
Plainville, Massachusetts (Docket No. 070-139; RFTA No. 97-7)", dated d
j February 4, 1997, (Attachment).
1 l
We found the.information you communicated in the above referenced Final Status-Survey Report provided adequate information to ascertain the thoroughness of i
l building remediation activities within~affected areas in buildings ~at the
-facility. Also, on January 7, 8, and 9 of this year, staff from the Oak Ridge i
Institute for Science and Education (0 RISE), performed a confirmatory survey at the Engelhard facility in Plainville, MA. ORISE was accompanied by staff
. from NRC and from the Massachusetts Department of Public Health, Radiation J
Control Program. The above referenced ORISE report documents the results of the confirmatory survey.
Based on the results of the ORISE confirmatory survey, the NRC staff finds that all affected Building 2 areas, with the exception of the east end of the tunnel, meet NRC guidelines for unrestricted release.
Later this month, it is expected that the Commonwealth of Massachusetts will be assuming regulatory jurisdiction, pursuant to Section 274b. of the Atomic Energy Act of 1954, as amended, over sites such as yours located in Massachusetts. Accordingly, Engelhard's decomissioning plan and other documentation related to remediation of contaminated soil and other exterior regions at the facility, should be submitted not to NRC, but instead, to the Commonwealth of Massachusetts, for review.
ikk Engelhard expressed interest in razing the buildings where radiological survey F and remediation activities were recently conducted, following NRC approval for unrestricted release. Soil sample measurements taken below the concrete NRC fu CENTER COPY
,i 9703120422 970306 PDR ADOCK 07000139 k
C PDR
Donald Chabot
- r flooring located at the southern end of Building 2, identified contamination i
in excess of the enriched uranium soil release guidelines, and concrete, below-grade flooring at the far east end of the tunnel running along the southern end of Building 2, contains elevated surface activity levels.
Although the contamination is generally well below the building's concrete flooring (greater than 4 feet), Engelhard should ensure against potential i
recontamination of clean building material during Building 2 demolition.
Prior to Building 2 demolition, your demolition plans, including measures to avoid contamination of clean building rubble, should be communicated to the Commonwealth of Massachusetts.
A copy of this letter is being forwarded to the Massachusetts Department of Public Health, Radiation Control Program.
Please contact Richard H. Turtil at (301) 415-6721 should you have questions concerning this letter.
Sincerely, 7
- ' l$/. l,/(k/ b3 John W. N. Hickey, Chief Low-level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards Attacheent: As stated Docket No.:
70-00139 cc: Engelhard C>rporation Distribution List
l Donald Chabot.;
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flooring located at the southern end of Building 2, identified contamination in excess of the enriched uranium soil release guidelines, and concrete, i-below-grade flooring at the far east end of the tunnel running along the southern end of Building 2, contains elevated surface activity levels.
Although the contamination is generally well below the building's concrete flooring (greater than 4 feet), Engelhard should ensure against potential recontamination of clean building material during Building 2 demolition.
Prior to Building 2 demolition, your demolition plans, including measures to avoid mntamination of clean building rubble, should be communicated to the Cos m nwnith of Massachusetts. A copy of this letter is being forwarded to the Massachusetts Department of Public Health, Radiation Control Program.
Please contact Richard H. Turtil at (301) 415-6721 should you have questions concerning this letter.
Sincerely, i
l
[0riginal signed by]
John W. N. Hickey, Chief i
Low-Level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards 4
Attachment:
As stated Docket No.: 70-00139 i
cc: Engelhard Corporation Distribution List DISTRIBUTION: Central File.
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ENGELHARD CORPORATION DISTRIBUTION LIST: 3..
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6 Jeffrey Barrett 4
Plainville Toxic Waste & Radiation Watch. Group 399 South St.
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- P1ainville, MA 02762
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Robert W. Brackett, RCRA Project. Manager i
U.S. Environmental Protection Agency, Region 3 d
.. JFK Federal Building, Room 2203 HRR-CAN3-Boston, MA 02203-2211 William Eart, Director Plainville Board of Health 140 South Street
-Plainville, MA 02762 Donald P. Chabot, Senior Environmental Engineer Engelhard Corporation
~ Route 152 i
Plainville, MA 02762 Jeffrey Chormann, Project Manager Massachusetts Department of Environmental Protection Bureau of Waste Prevention
- One Winter Street, 5th Floor Boston,'MA 02108
. Engelhard Site Information Repository Plainville Public Library 198~ South Street
'-Plainville, MA 02762
-Thomas'0'Connell Massachusetts Department of Public Health Radiation Control Program
- 305 South Street' Jaraica Plain, MA 02130 NRC Distribution
Ronald'R. Bellamy, Chief, Decommissioning and Laboratory Branch, RI
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4-Paul H.'Lohaus, Deputy Director, Office of State Programs DavidJ.Chawaga,StateLiaisonOfficer,;RI e - Robert L. Fonner, Special Counsel forJFuel Cycle and Safeg'uar'ds Regblation,
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' erd of Building 2, contains elevated surface activity levels. We understand that you-are aware of the contamination in these areas; and', because you have documented soil contamination in exterior areas outside Building 2, we further understand that it is your intent to consider these areas'in the exterior dacommissioning plan. Although the contamination is gen'erally well below the 4
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. building's concrete flooring (greater than 4 feet), we/believe it is prudent to exercise caution during building demolition to enstire that potentially contaminated soil, and concrete flooring in the sub drranean east end of the
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tunnel, remain undisturbed.
Engelhard has indicated that submission of a decommissioning plan and L
decommissioning activities for contaminated soi,l' and other exterior regions at the facility are scheduled for a later date.,These efforts will require i
Engelhard's direct involvement with the Commo6 wealth of Massachusetts, because the Commonwealth wili be assuming regulatory' jurisdiction over sites located in Massachusetts, such as yours, under the}r Agreement with the NRC, pursuant I
to Section 274b. of the Atomic Energy Act,0f.1954, as amended. This Agreement is expected to become effective on March /21, 1997.
301) 415-6721 should you have questions Please contact Richard H. Turtil at (/
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concerning this letter.
sincerely, e
John W. N. Hickey, Chief Low-Level Waste and Decommissioning-Projects Branch Division of. Waste Management t
Office of Nuclear Material Safety and Safeguards
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Attachment:
As stated f
Docket No.: 70-00139 cc: Engelhard Corporation Distribution List
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DISTRIBUTION: Central File
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ORISE OAK RIDGE iN$fif utt FOR 3C *E NC E AND E DUC AfiON j
Febma y 4,1997 Mr. Richard Turtil U.S. Nuclear Regulatory Commission Division of Waste Managervent - NMSS Two White Flint North T '/F21 3
11555 Reckvi!!e Pixe Rockville, MD 20852
SUBJECT:
LETTER REPORT-CONFIRMATORY SURVEY FOR SURVEY UNITS 1 AND 2, INTERIOR OF BUILDING 2, ENGELHARD PLANT, PLAINVILLE, MASSACHUSETTS (DOCMETNO:W79 IP, RFTA NO. 97-7)
Dear Mr. Turtil:
Enclosed is the subject letter report. This report provides information on the confinnatory survey activities conducted at the Engelhard facility in Plainville, Massachusetts on January 7 through 9, 1997. A draft confirmatory survey report is currently being prepared and will be sent to you for
' comment.
Please direct any questions or comments to me at (423) 576-3740 or Timothy J. Vitkus at (423) 576-5073.
Sincerely, N.
Eric W. Abelquist Assistant Program Director Environmental Survey and Site Assessment Program EA:dka Enclosure l
l cc:
R. Uleck, NRC/NMSS/TWFN 7F27 A
D. Tiktinsky, NRC/NMSSrfWFN 8A23 W. Beck, ORISE/ESSAP lg T. Vitkus, ORISE/ESSAP k
4 b
File /678 e:::i;;; : "7;;; -_
PDR ADOCK 07000139 C
PDR 140027
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l LETTER REPORT CONFIRMATORY SURVEY FOR SURVEY UNITS 1 AND 2 INTERIOR OF BUILDING 2 i
ENGELHARD PLANT U
PLAINVILLE, MASSACHUSETTS i
INTRODUCTION AND SITE HISTORY f
D.E. Makepeace, predecessor of the current Engelhard Corporation, manufactured nuclear fuel l
elements at its plant on Route 152 in Plainville, Massachusetts from 1957 until cessation of operations in 1962. ' Manufacturing operations were performed under the Atomic Energy Commission (AEC). predecessor agency to U. S. Nuclear Regulatory Commission (NRC), Docket
- No. 070-139. The Building 2 interior and equipment used in the fuel fabrication operations were decontaminated and a final radiological survey was performed by Engelhard industries in 1%3.
Based on the results of this survey, and a confirmatory survey of the Buildiog 2 interior and equipment conducted by the AEC, the facility licensen were terminated (Engelhard 1996). The decontanunated equipment was removed fmm the plant and sold to the Italian government.
Subsequently, the area used for nuclear fabrication was converted to other non-nuclear metal fabrication operations.
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A radiation scoping survey of the plant was conducted in July 1988 as a part of a multi-phase site manaamment initiated by Engelhard Corporation to identify potential areas of envimnmental concem.
l This survey identified the radiological contaminants of concem as U-238, U-235, and U-234, with low enrichments of U-235.
A more detailed characternation survey of Buildings 1 and 2 was conducted in March 1994, which resulted in delineating affected and unaffected areas based on current NRC regulatory guidelines.
An NRC-appmved Decontamination Plan for releasing the Building 2 affected areas in accordance with current criteria was then implemented. The affected areas were decontaminated from June through October 1996. The building decommissioning activities consisted of the removal of i
1 remaining equipment from the affected area, collecting and removing loose material, scabbling contaminated surfaces (mainly floors and some walls) and collecting the removed material, and sawing and breaking concrete floors to remove piping and floorjoints. The piping was generally og gg nw m,*um wre m PDR ADOCK 07000139 PDR j
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found to be physically intact and without perforation, with a few small pockets of contaminated scil i
undei locations where the pipe had been cut-contaminated soil was removed. In addition, expansionjo*nts were cut out of the floor to remove any contamination that had collected in these locations and IWi=d areas of contaminated material had been removed from overhead piping, j
structural members, and electrical buss ducts. Remediation contml surveys performed by Engelhard l
indicated that all surfaces were within NRC residual surface contamination criteria.
l Engelhard conducted a final radiological status survey of each of two survey units in Building 2 as
)
the' decontamination effort was completed. The results of the survey demonstrated that the radiation l
levels in '.ne building now satisfy NRC residual contammation guidelines, established for release of l
formerly licensed sites to unrestricted use. The final status' survey report covers only Buildings 1 S
and 2; the decommissioning project for the exterior regions of the facility is scheduled to be 4
undertaken later upon NRC approval of Engelhard Corporation's proposed approach to exterior l
decontamination.
1 f
At the request of the NRC's Division of Waste Management, the Envimnmental Survey and Site Assessment Pmgram (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed an independent conio' umy survey of Building 2 at the Engelhard Corporation plant in f
Plainville, Massachusetts.
l SITE DESCRIPTION i
l The Engelhard facility is located at 30 Taunton Street (also known as Massachusetts Highway Route l
152) in Plainville, Norfolk County, Massachusetts ne facility housed areas used both for nuclear i.
fuel fabrication and non-nuclear operations-fuel element fabrication operations were totally segregated from the non-nuclear manufacturing and other operations, i-I 4
A signi6 cant portion of the concrete floor surfaces in Building 2 were scabbled. Many of the floor f
trenches, created during Engelhard's remediation efforts to remove contmninM drain lines and k
contamination identified between floor expansion joints, had been backfilled. ne walls were generally of painted concrete block construction.
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Buildings I and 2 were the only buildings existing at the time of nuclear fuel fabrication. Neither Building 1 or 2 is currently being used for any Engelhard operations, and there is no Engelhard j
worker population in these buildings. De affected areas in Building 2 were well delineated, based on the results of the characterization survey and knowledge of the plant operstmg history. The affected area was entirely within Building 2 and consisted of:
Rooms where localized average surface contamination levels on the floor and in cracks and crevices exceed applicable residual surface contamination criteria. These I
rooms included the tunnel ramp, the former precious metal storage room (2L), the former scrap melt mom (2M), the corridor and part of the floor in the room north of the scrap melt room (2N), part of the floor in the former melt room (2H), and the room on the left of the entrance corridor in Building 2 (2B).
Rooms where localized average floor surface contamination levels were less than the residual surface contamination release criteria, but were elevated above background levels (greater than 2-3 times background). These rooms were deconuminakd based on ALARA considerations. De rooms were designated as 2A,2C,2D,2F, room to the north of 21 (subsequently designated 2P), and 2K.
Subfloor piping originating in the affectM area where elevated radiation levels were measured in the drain inlet openings and outlets.
The remainder of Building 2, and all of Building 1, was classified as unaffected. During decontamination activities, rooms 2E and 2G were added to the affected area.
OBJECTIVE The objective of the confirmatory survey was te r,. sufficient radiological data for use by the NRC in evaluatir.g the radiological condition, relative to current guidelines, of interior areas of Buildings 2 of the Engelhard facility.
3 s w w w m3 Eagotani Corposemos (678). February 4,1997
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DOCUMENT REVIEW ESSAP has reviewed Engelhard's final survey report for the Engelhard facility (Engelhard 1996) and siA.cc between the NRC and Engelhard concerning NRC's comments on the final report.
Procedures and methods used by Engelhard were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness, and compliance with guidelines.
PROCEDURES Dunng the period January 7 through 9,1997, ESS AP performed independent confirmatory survey activities at the Engelhard facility in Plainville, Massachusetts. The survey was in accordance with a plan dated December 30,1996 (ORISE 1996a) submitted to and approved by the NRC's Division of Waste Management. Survey procedures were performed in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995a and b). This report summarizes the procedures and results of the survey.
SURVEY Paocanuars The rooms within Building 2 that were surveyed included the tunnel ramp, the former precious metal storage room (2L), the former scrap melt room (2M), the scrap melt room (2N), the former melt room (2H), and rooms 2A,2B,2C,2D,2E,2F,2G 2K,2P and the Entry corridor.
Reference Grid
. ESSAP r ferenced measurement and sampling data to both Engelhard's grid system and to prominent building features, and recorded the survey information on appropriate drawings.
Surfmee Seams Surface scans for alpha, beta, and gamma radiation were performed on approximately 100% of the accessible floor surfaces, and on approximately 5 to 10% of wall surfaces, in the surveyed rooms.
Surface scans were also performed on overhead areas in rooms 2M and 2L where contaminated 4
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' material may have accumulated. Scans were performed using gas proportional, GM, and/or Nal i
scinbHation detectors coupled to ratemeters or ratemeter-scalers with audib'e indicators. Locations of elevated direct radiation identified by surface scans were marked for further investigation.
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i Constmetion material speci6c backgmunds for scrbbled concrete, metal, ceramic brick, and dry wall l
were determined within Building 1, in areas of smuiu construction but without a history of t
l radioactive material use.
A total of 177 direct measurements for total uranium surface activity levels were performed on interior building surfaces. Two direct measurements were also performed on the building roof.
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Five, five-point measurements were performed to determine the averary,urface activity level over I m' areas. Direct measurements were performed using gas proportional or GM detectors coupled 1
to ratemeter-scalers. Areas of residual activity, in excess of the guideline:., were brought to the immediate attention of Engelhard and the NRC. In one instance, additional remediation was l
performed by Engelhard in room 2G and ESSAP performed follow-up measurements.
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A smeer sample for h mining the removable gross alpha and gross beta activity was collected at each direct measurement location.
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j Background exposure rate measurements were performed at five locations of similar construction within Building 1, but without a history of radioactive material use. Exposure rates were measured I
at ten locations within Building 2. Exposure rates were measured at I meter above the surface using a microrem meter.
I Sail Sampling i
j Eleven soil samples were collected from trenches, excavations and subfloor areas within the i
Building 2 areas.
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Background soil samples were collected during a previous site survey in the vicinity of the Engelhard site (ORISE 1985).
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SAMPLE ANALYSIS AND DATAINTERPRETATION i
Samp!m and survey data were returned to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Soil samples were analyzed by solid-state gamma spectrometry, and f.
based on sample results, three samples were analyzed by alpha spectrometry. Sample analyses were j.
performed in accordance with the ORISE/ESSAP Laboratory Procedures Manual (ORISE 1995c).
Enriched uranium was the radioactive material of concem; spectra were reviewed for U-238 and
,f U-235, and any other identifiable photopeaks. Soil sample results were reported in units of picocuries per gram (pCi/g). Smears were analyzed for gross alpha and gross beta activity using a i
j
. Iow-background proportional counter. Direct measurement data were converted to units of -
disintegrations per minute per 100 square centimeters (dpm/100 cm'). Specifically, the residual l
uranium surface activity was calculated by:
i surface activity = 2.9 *
(eftetency) (probe areal 100) i i
This equation is specific to measurements of 4% enriched uranium usmg gas proportional detectors l
2 l
(3.8 mg/cm window) calibrated to SrY-90; the technical basis is documented in the site logbook, i
The conversion factor (2.9) accounts for the detector's response to 4% enriched uranium alpha and beta radiations (12% efficiency) relative to the detector efficiency for SrY-90. Smear data were converted to units ofdpm/100 cm'. Exposure rates were reported in microroentgens per hour ( R/h).
FINDINGS AND RESULTS i
i DOCUMENT REVIEW i.
l ESSAP reviewed Engelhard's final survey report, including the final status survey data and comment letters, documenting these reviews, were submitted to the NRC (ORISE 1996b). Engelhard's documentation provides an adequate description of the radiological status of the surveyed areas.
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4 SURFACE SCANS J
4 Surface acans identified several locations exhibiting elevated direct radiation. In room 2F, a small 1
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amount ofsignificantly elevated contamination (approxunately 36,000 dpm/100 cm ) was identified between a floor expansionjoint. Another location was identified on the concrete floor in inom 2G.
Two locations were identified on overhead surfaces in room 2M. Engelhard performed remediation activities at each of these locations-small amount of contamina*M material was removed from i~
room 2F, concrete floor was scabbled in room 2G, overhead light fixture was removed in room 2M, and a wmdow ledge was vacuumed in room 2M. Other locations identified by surface scans were either resolved through averaging surface activity levels in 1 m' areas or by noting that surface activity was less than guideline.
i SURFACE ACTIVITY LEVELS i
Uranium surface activity levels are shown in Table 1. Prior to additional rWiation by Engelhard, 2
uranium surface activity levels range from -1,400 to 36,000 dpm/100 cm for single-point measurements. Following remediation, the surface activity levels ranged from -1,400 to 12,000 dpm/100 cm'. 'Ihe average uranium surface activity within the five 1 m' areas investigated ranged from 1,400 to 7,600 dpm/100 cm'.
Two direct measurements performed on the building roofindicated background levels of surface activity.
All removable activity was less than the mimmum detectable concentration of the procedure, which was 9 dpm/100 cm for alpha and 15 dpm/100 cm' for beta.
2 2
ExroSURE RATES Background exposure rates (Table 2) performed in Building I ranged from 7 to 9 R/h.' Site
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exposure rates for Building 2 surveyed areas ranged from 8 to 12 pR/h and are summarized in Table 2.
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1 RADIONUCLIDE CONCENTRATIONS IN SOIL Total uranium concentrations for samples were calculated by multiplying the measured U-235 concentration by 21 to account for the U-234 (based on Engelhard's isotopic uranium results) and adding to that value the measured U-235 and U-238 concentrations.
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j Total uranium concentrations (based on natural isotopic ab=imaca=) in background samples, i
l previously determined at a nearby site, ranged from 1.0 to 2.4 pCi/g (ORISE 1985).
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l Concentrations of U-235, U-238, and total uranium in soil samples ranged from <0.1 to 190.1 pCi/g, 0.7 to 656 pCi/g, and <3.5 to 4,260 pCi/g, respectively. Results are summanzed in Table 3.
l Alpha spectrometry was performed on 3 samples to verify the U-235 enrichment levels reported by l
Engelhard. Preliminary results indicate that the U-234 to U-235 isotopic ratios are consistent with t
i i the ratios reported by Engelhard.
t COMPARISON OF RESULTS WITH GUIDELINES i
The primary contaminant of concern for this site is enriched uranium (approximately 4%). The l
applicable surface activity guidelines for uranium are as follows (NRC 1987):
Total Activity 1
2 2
5,000 a dpm/100 cm, averaged over a 1 m area 15,000 a dpm/100 cm, maximum in a 100 cm' area 2
Remnvahle Activity 2
1,000 a dpm/100 cm As previously dim!==~i, surface scans identified several locations of elevated direct radiation at the site that were marked for further investigation. Direct measurements were performed at each of c
these locations which resulted in four of the locations exceeding surface activity guidelines that were i
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remediated by Engelhard. Following the additional remediation, with the exception of surfa e l'
activity levels in the tunnel, all surface activity levels satis 6ed the guidelines. - Surface activity levels on the floor at the east end of the tunnel, exhibited I m' averages of 1,900 and 7,600 dpm/100 cm,
2 i
All removable activity levels satisfied the guideline.
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The exposure rate guideline is 10 R/h above background at one meter above soil surfaces and 5 l
pR/h above background at one meter above building surfaces (NRC 1991). All exposure rates j
satisfied the guideline levels.
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The generic NRC guidelines for residual concentrations of uranium in soil are provided in the NRC Branch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium Wastes from 3
l' Past Operations" (NRC 1981). Specifically, the Option 1 average soil guideline for enriched 4
i uranium is 30 pCi/g. Total uranium concentration within the tunnel soil areas and two locations i
'within the excavation in room 2M exceeded the soil guideline for enriched uranium. All other soil samples satisfied the guideline.
SUMMARY
During the period of January 7 through 9,1997, the Environmental Survey _and Site Assessment Program of ORISE performed a confirmatory survey of Building 2 at the Engelhard facility in Plainville, Massachusetts. Survey activities included document reviews, surface scans, surface activity measurements, exposure rate measurements, and soil sampling.
The confirmatory survey identified several locations of elevated direct radiation in Building 2 that required further rWMon. The confirmatory survey surface activity results, following additional remediation, are consistent with those of Engelhard and support the licensee's conclusion that residual surface activity levels, excluding the east end of the tunnel, satisfy the guidelines for release for unrestricted use.
9 h%WaseWE Eagnewd Corporamme (679). February 4.1997 e.
While elevated soil concentrations were anticipated in the tunnel soil areas, two soil samples from within the excavation in room 2M exceeded the enriched tunium soil gu:deline. Results of the renainmg soil sample analyses support the final survey performed by Engelhard, and in ESSAP's opinion, indicate that the radiological conditions of the surveyed areas satisfy the NRC guidelines l
for release for unrestricted use.
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l TABLE 1
SUMMARY
OF SURFACE ACTIVITY LEVELS BUILDING 2 i
ENGELHARD CORPORATION i
PLAINVILLE, MASSACHUSETTS l
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Total Ursalem Surface l
Number of Activity Range Removable Measurement (dpm/100 cm')
Activity Range j
to,,g,,
Locations (dpm/100 cm*)
4 l
Single Grid Block l
Single-Grid Measurement Average Alpha Beta Point Blocks I
Room 2A/ Floor and Iower Walls 10 NA*
-150 to 3,100 NA
<9
<l5 Room 2B/ Floor and IAwer Walls 10 NA
-340 to 770 NA
<9
<15 l
Room 2C/ Floor and Lower Walls 17 2
-590 to 6,700 1,800 to 2,100
<9
<l5 l
Room 2D/ Floor and Lower Walls 10 NA
-220 to 3,200 NA
<9
<l5 1
i Room 2E/ Floor and Lower Walls 5
NA 39 to 2,700 NA
<9
<l5 Room 2F/ Floor and Lower Walls 12 NA
-200 to 3,100*
NA
<9
<l5 i
Room 2G/ Floor and Lower Walls 12 NA
-280 to 2,800" NA
<9
<15 Room 2H/ Floor and Lower Walls 10 NA
-1,400 to 20 NA
<9
<15 Room 2K/ Floor and Lower Walls 10 NA
-660 to 610 NA
<9
<15 Room 211 Floor and Lower Walls 14 1
-20 to 6,000 1,400
<9
' <15 Room 2UOverheads 2
NA
-350 to 39 NA
<9
<15-Room 2M/ Floor andlawer Walls 14 NA 140 to 4,000 NA
<9
<l5 Room 2M/ Overheads 5
NA
-370 to 640' NA
<9
<15 Room 2N/ Floor and Lower Walls 11 NA
-l80 to 4,000 NA
<9
<15 Room 2P/ Floor and Lower Walls 5
NA
-550 to 53 NA
<9
<l5 Entry / Floor and Lower Walls 10 NA
-13 to 2,100 NA
<9
<l5 Tunnel / Floor and Lower Walls 20 2
-370 to 12,000 1,900 to 7,600
<9
<l5
'Not applicable.
' Surface activity level following additional remediation.
s e e c.,p.,m em. r*=,o. im 11 n w si.e risarusoixi
?
t TABLE 2 EXPOSURE RATES ENGELHARD CORPORATION i
PLAINVILLE, MASSACHUSE'ITS Number of Exposure Rate Exposure Rate Range Location Measurements at 1 m (pR/h)
Room 2B 1
11 Room 2C 1
12 Room 2H 1
9 l
Room 2K 1
9 Room 2L 1
9 Room 2M 2
9 to 10 Room 2N 1
8 1
Tunnel 2
10 to 11
Background
Building 1 5
7 to 9 12 a:wsi,,,,,sionii.ao3 Engetard Corporanon (678). Fetruary 4.1997
_ _ _.. - _ _ _. _ _. _ ~. _
i l
TABLE 3 URANIUM CONCENTRATIONS IN SOIL BUILDING 2 l-ENGELHARD CORPORATION PLAINVILLE, MASSACHUSETTS i
Uranium Concentration (pCi/g) 1-Location U-238 U-235 Total Ursalem" l.
Room 2A 4.9 0.8*
0.8 0.2 22.5 l
Room 2K 1.6 t 0.6 0.2
- 0.1 6.0 j
l Room 2L 1.3 0.6
<0.1
<3 ',
Room 2M/ Pit North Wah 29.4 2.1 18.5 + 0.8 436 Room 2M/ Pit East Wall 0.7
- 0.5
<0.2
<5.1 Room 2M/ Pit Bottom 8.1 1.0 3.3*0.3 81 Room 2N 1.0
- 0.7 0.3
- 0.2 7.6 Tunnel / Trench 76.1
- 6.2 57.2
- 2.5 1,330 Tunnel / Trench 656 34 101.4 4.4 2,890 Tunnel / Trench Wall 77.7
- 7.2 190.1
- 7.4 4,260 Tunnel / Pipe Chase Area 1.2
- 0.9
<0.2
<5.6
- Uncertainties represent the 95% confidence level, based only on counting statistics.
Total uranium calculated based on a U-234 to U-235 ratio of 21:1; background levels have not been subtracted.
13 nw w m w % *m - w. m
r._____
i 9
i.
REFERENCES Engelhard Corporation. Final Status Survey Report, Survey Units 1 and 2 in Interior of Plainville, Massachusetts Plant of Engelhard Corporation. Plainville, Massachusetts; November 1996.
Oak Ridge Institute for Science and Education (ORISE). Radiological Survey of the Texas Instruments Site, Attleboro, Massachusetts. Oak Ridge, Tennessee; January 1985.
Oak Ridge Institute for Science and Education.
Survey Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; April 30,1995a.
Oak Ridge Institute for Science and Education.
Quality Assurance Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; January 31,1995b.
Oak Ridge Institute for Science and Education.
Laboratory Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; January 31,1995c.
Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for Survey Units 1 and 2 in Interior of Building 2, Engelhard Plant, Plainville, Massachusetts (Docket No. 070-139; RFTA No. 97-7). Oak Ridge, Tennessee; December 30,1996a.
Oak Ridge Institute for Science and Education. Document Review-Final Status Survey Report, Survey Units 1 and 2 in Interior ofPlainville, Massachusetts Plant of Engelhard Corporation (Docket No. 070-139; RFTA No. 97-7). Oak Ridge, Tennessee; December 6,1996b.
U.S. Nuclear Regulatory Commission (NRC). Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations. Wanhinginn, DC: Federal Register 46 (205): 52061-52063; October 23,1981.
U.S. Nuclear Regulatory Commission (NRC). Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of License for Byproduct, Source, or Special Nuclear Material. Washington, DC; August 1987.
U.S. Nuclear Regulatory Commission. Office of Nuclear Safety and Safeguards, Review Plan:
Evaluating Decommissioning Plans for Licensees Under 10 CFR Parts 30,40, and 70, Washington, DC; 1991.
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m.renp.m 14
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_ _ _..