II ORNL/RASA-92/l · (Activity No. EX 20 20 01 0; ADS317OOOO) Results of the Radiological Survey at...
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Transcript of II ORNL/RASA-92/l · (Activity No. EX 20 20 01 0; ADS317OOOO) Results of the Radiological Survey at...
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OAK RlDGE NATIONAL LABORATORY
hUW-l\ &?ir;; ITi’ m . 8
ORNL/RASA-92/l
Results o f the Radiological Survey a t the Former
Chapman Valve Manu facturing Company, Indian Orchard, Massachusetts
(cIooo1)
R. D. Fo ley M . S. Uziel
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY
ORNLJRASA-92/l
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HEALTH AND SAFETY RESEARCH DIVISION
Environmental Restoration and Waste Management Non-Defense Programs (Activity No. EX 20 20 01 0; ADS317OOOO)
Results of the Radiological Survey at the Former Chapman Valve Manufacturing Company,
Indian Orchard, Massachusetts (cIooo1)
R. D. Foley and M. S. Uziel
Date Issued - July 1992
Investigation learn R. E. Swaja - Measurement Applications and Development Manager
W. D. Cottrell - FUSRAP Project Director R. D. Foley - Field Survey Supervisor
Survey lkam Members R. A. Mathis D. E. Rice V l? Patania D. A. Rose
W. A. Williams*
*U.S. Department of Energy
Work performed by the MEASUREMENT APPLICATIONS AND DEVELOPMENT GROUP
Prepared by the OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee 37831-6285 managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC. for the
U. S. DEPARTMENT OF ENERGY under contract DE-AC05S40R21400
CONTENTS
LISTOFFIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v
LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii
ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix
ABSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi
INTRODUCI’ION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
SCOPE OF THE SURVEY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
SURVEYMETHODS . . . . . . . . . . . . . .._................................ 2
SURVEY RESULTS.. ................................................ 3 GAMMA EXPOSURE RATE MEASUREMENTS ....................... 3 BETA-GAMMA DOSE RATE MEASUREMENTS ....................... 4 DIRECT AND REMOVABLE ALPHA AND BETA-GAMMA
RADIOACTNITYLEVELS ...................................... 4 SOIL AND INDOOR DUST AND DEBRIS SAMPLES ................... 4 DISTRIBUTION OF CONTAMINATION .............................. 5
Grid Block Al and Building Exterior ................................ 5 Grid Block A2 .................................................. 6 Grid Block A3 ................................................. 6 Grid Block A4 ................................................. 6 Grid Block A5 ................................................. 6 Grid Block A6 ................................................. 7 Grid Block A7 and A8 ........................................... 7 Grid Block A9 ................................................. 7 GridBlockAll ................................................ . Grid Block Al3 ................................................ 8
SIGNIFICANCE OFFINDINGS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
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LIST OF FIGURES
1 Location of Building 23 (Department No. 40) at the site of the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
2 Building 23 at the site of the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
3 View looking east at the main entrance to Building 23 at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts . . . . . . . . . 12
4 View inside the main entrance looking east at grid blocks Al through A30 in the center of Building 23 (Indian Orchard, Massachusetts) . . . . . . . . . . . 12
5 Surface and l-m gamma exposure rates @R/h) taken at the center of the north and south sections of grid blocks Al through A30, Building 23, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
6 Average surface gamma exposure rates (a/h) measured in grid blocks at Building 23, Indian Orchard, Massachusetts. . . . . . . . . . . . . . . . . . 14
7 Ranges of beta-gamma dose rates (mradih) measured in grid blocks at Building 23, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . 15
8 Locations of soil, dust, and debris samples collected at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts . . . . . . . . . 16
9 Surface gamma exposure rates (a/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block Al . . . . . . . . . . . 17
10 Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A2 . . . . . . . . . . . 18
11 Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A3 . . . . . . . . . . . 19
12 Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A4 . . . . _ . . . . . . 20
13 Surface gamma exposure rates &R/h), beta-gamma dose rates (mradk), and alpha activity levels (dpm/lOO cm2) in grid block A.5 . . . . . . . . . . . 21
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14 Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A6 . . . . . . . . . . . 22
15 Surface gamma exposure rates &R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A7 . . . . . . . . . . . 23
16 Surface gamma exposure rates &R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A8 . . . . . . . . . . . 24
17 Surface gamma exposure rates (&/Ii), beta-gamma dose rates (mradh), and alpha activity levels (dpm/lOO cm2) in grid block A9 . . . . . . . . . . . 25
18 Surface gamma exposure rates (a/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block All . . . . . . . . . . 26
19 Surface gamma exposure rates (pR/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block Al3 . . . . . . . . . . 27
20 View looking east northeast at Building 23, Indian Orchard, Massachusetts . . . . . . . . . . .._...................................... 28
21 View of contaminated area located north of the concrete ramp immediately inside the main entrance . . . . . . _ . . . . . . . . . . . . . . . . . . . . . . . . . . 28
22 View of area just north of main entrance with elevated beta-gamma levels on the wall, a ledge, and the door jamb . . . . . . . . . . . . . . . . . . . . . . . . . _ . 29
23 View of brick facing on column B2 (right side of photo behind cabinet). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
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LIST OF TABLES
1 Applicable guidelines for protection against radiation . . . . . . . . . . . . . . . . . . . . . 30
2 Background radiation levels and concentrations of selected radionuclides in soil for Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
3 Alpha and beta-gamma measurements at Building 23 at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts . . . . . . . . . 33
4 Concentrations of radionuclides in soil, dust, and debris samples collected at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36
5 Comparison of mu concentrations in selected dust samples from overhead beams with DOE guideline value for removable surface contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38
6 Alpha, beta-gamma, and gamma radiation measurements at dust and debris sample locations at the former Chapman Valve facility, Indian Orchard, Massachusetts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
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ACKNOWLEDGMENTS
This project was sponsored by the Office of Environmental Restoration, U.S. Department of Energy, under contract DE-AC05-S40R21400 with Martin Marietta Energy Systems, Inc. The authors wish to acknowledge the contributions of R. E Carrier, W. D. Cottrell, V I? Patania, D. A Roberts, and J. K Williams of the Measurement Applications and Development Group; J. Lovegrove of D. R. Stone and Associates; and W. A. Williams of the U.S. Department of Energy for participation in the analyses, editing, and reporting of data for this survey. The authors also wish to thank J. E Allred and D. A Rose for sample preparation.
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ABSTRACT
At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Building 23 (Department No. 40) at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts. The survey was performed in August 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally ?J, as a result of work done for the Atomic Energy Commission (AEC) during the 1940s. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha activity; measurement of direct and removable alpha and beta-gamma levels; and the collection of soil, dust, debris, and smear samples for radionuclide analyses. Survey emphasis was on interior floors, walls, and overhead beams.
Radionuclide analysis of soil, dust, and debris, and analysis of smear samples indicate that residual mu attributable to former AEC-supported operations is present at this site. Elevated levels of radioactivity were particularly evident on the floors and walls in the western part of the central area of the building (grid blocks Al through A6). Concentrations of 238U in dust samples collected from overhead beams exceeded DOE guidelines in grid blocks Al through Al4 and remained elevated in grid blocks Al5 through A19. Dust on a movable overhead crane in grid block A23 was well above the guideline, probably because the crane had at some time been located further west. Some contamination was evident in grid blocks Bl through B5, but clutter and debris in this area prevented a thorough survey.
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Resu l ts o f th e R a d io log ica l S u rvey a t th e fo rme r C h a p m a n V a lve M a n u fac tu r i ng C o m p a n y , In d i a n O rchard , Massachuse tts
(cI0 0 0 1 ) *
INTRO D U C T IO N
T h e C h a p m a n Va l ve M a n u fac tu r ing C o m p a n y in In d i a n O rchard , M a s s a c h u s e tts, was o n e o f m a n y c o m p a n i e s pe r fo rm ing work assoc ia ted wi th th e d e v e l o p m e n t o f nuc lea r ene rgy fo r d e fense - re la ted pro jec ts du r i ng th e 1 9 4 0 s . Th is work, c o n d u c te d u n d e r g o v e r n m e n t c o n tract to th e M a n h a tta n E n g i n e e r District ( M E D ) a n d th e A tom ic E n e r g y Commiss i on ( A E C ) , i n c l uded th e p r o c u r e m e n t, s torage, a n d p rocess ing o f u r a n i u m ox ides , salts, a n d m e tals, a n d th e s u b s e q u e n t mach i n i ng o f th e s e p r oduc ts. A s a resul t o f th e s e activit ies, e q u i p m e n t, bu i ld ings , a n d l and a t s o m e o f th e si tes b e c a m e rad io log ica l l y c o n ta m i n a te d resu l t ing in l ow leve ls o f c o n ta m i n a tio n o n th e proper t ies . A t c o n tract te rm ina tio n , s i tes u s e d by c o n tractors we re d e c o n ta m i n a te d in a cco rdance wi th th e s tanda rds a n d su rvey m e th o d s in u s e a t th a t tim e . S ince th e o r ig ina l a s sessmen ts, rad io log ica l cr i ter ia a n d gu ide l i nes fo r th e re l ease o f such si tes fo r unrest r ic ted u s e h a v e b e c o m e m o r e str ingent. In s o m e ins tances, reco rds d o c u m e n tin g d e c o n ta m i n a tio n e fforts c a n n o t b e fo u n d , a n d th e fina l rad io log ica l cond i t i ons o f th e si te c a n n o t b e a d e q u a te ly d e te r m i n e d . A s a result , th e Former l y U t i l ized S ites R e m e d i a l A c tio n P rog r am ( F U S R A P ) was es tab l i shed in 1 9 7 4 to i d en tify th e s e fo rmer l y u s e d si tes a n d to reeva lua te the i r rad io log ica l status.’
T h e rad io log ica l su rvey d e ta i l ed in th is repor t was pe r f o rmed u n d e r th e F U S R A P p r o g r a m a t th e si te o f th e fo rme r C h a p m a n Va l ve M a n u fac tu r ing C o m p a n y . C h a p m a n Va l ve was a p r inc ipa l supp l ie r o f r egu la r a n d spec ia l va lves a n d m a n i fo lds fo r th e M E D a n d th e A E C . Reco rds a l so ind ica te th a t C h a p m a n Va l ve , u n d e r c o n tract wi th B rookhaven L a b o r a tory, m a c h i n e d u r a n i u m m e ta l du r i ng th e pe r i od Janua r y th r o u g h N o v e m b e r 1 9 4 8 . In a letter d a te d Janua r y 9 , 1 9 4 8 , s h i p m e n t o f app r ox ima te ly 2 6 to n s o f ex t ruded rods was d i rec ted to a C h a p m a n Va l ve faci l i ty in In d i a n O rchard , M a s s a c h u s e tts. Mach i n i ng o p e r a tio n s m a y n o t h a v e star ted u n til M a y 1 9 4 8 . O n e A E C m e m o r a n d u m ind ica tes th a t C h a p m a n Va l ve m a y a l so h a v e c o n d u c te d ro l l ing o p e r a tio n s o n th e u r a n i u m m e tal. T h e hea l th a n d safety p r o g r a m fo r th is work a t th e C h a p m a n Va l ve faci l i ty was set u p by th e A E C .2
The re was a f ire in th e restr ic ted a r ea o f th e A E C project , p r obab l y in J u n e 1 9 4 8 . T h e exact n a tu re o f th e f ire a n d extent o f th e d a m a g e is u n k n o w n . T h e i nvo l vemen t o f u r a n i u m m e ta l in th e f ire is s u g g e s te d by a C h a p m a n Va l ve letter d a te d Janua r y 1 9 , 1 9 4 9 .2
*The su rvey was pe r f o rmed by m e m b e r s of the M e a s u r e m e n t App l i ca t ions a n d D e v e l o p m e n t G roup o f the Hea l th a n d S a fe ty Resea r ch Div is ion a t O a k R i d g e N a tiona l Labora to ry unde r D O E contract D E - A C O S - 8 4 0 R 2 1 4 0 0 .
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After the contract work was completed, Chapman Valve had in their possession over 27,000 pounds of metal scrap, oxides, and sweepings. Termination of these operations is indicated in a Chapman Valve letter dated November 8, 1948, which requested termination of AEC film badge services. All radioactive residues and contaminated materials were surveyed by the Brookhaven Medical Group and shipped off-site. The actual shipment date is unknown, but the shipment probably took place in December 1948.2
A former Chapman employee recalls that in 1947 Chapman set aside approximately one-third of Department No. 40 at the Chapman site, 203 Hampshire Street, Indian Orchard, Massachusetts, for the machining of uranium rods for Brookhaven Laboratory. The “set aside” portion of the building measured approximately 200 by 60 ft and was separated from the remainder of the building by a floor-to-ceiling wooden partition, which has since been removed. Chapman became part of the Crane Company in 1959. The building that contained the uranium operations has been vacant since Crane discontinued all manufacturing at Indian Orchard early in 1987.3
In August 1991, a radiological survey was conducted at the former Chapman Valve Manufacturing Company by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory (ORNL) at the request of the U.S. Department of Energy (DOE). Th e survey and sampling at this site covered selected areas outdoors and accessible areas inside Building 23 (formerly Department No. 40, Fig. 1, p. 10). Survey emphasis was on interior floors, walls, and overhead beams.
SCOPE OF THE SURVEY
The radiological survey included (1) a surface gamma scan of the floor and walls in all accessible areas inside the building and a gamma scan of the ground surface in selected areas outdoors; (2) measurement of surface and l-m gamma exposure rates at the center of the north and south sections of main-bay survey blocks; (3) a beta-gamma scan of dose rates in accessible areas of the floors and walls inside the building; (4) measurement of alpha activity levels at selected locations; (5) collection and radionuclide analysis of 26 dust and debris samples from overhead beams, 1 from a high-wall window sill, 1 from floor debris, and 2 from a concrete floor anchor; (6) measurement of direct and removable alpha and beta-gamma levels at 31 locations inside the building; (7) collection and radionuclide analysis of 2 soil samples outside the building. It was judged unsafe to conduct a survey of the deteriorating roof.
SURVEY METHODS
A comprehensive description of the survey methods and instrumentation used in this survey is given in Procedures Manual for the ORNL Radiological Survey Activities (RASA) Program, ORNL/IU-8600 (April 1987).4
To facilitate reporting of results, the east-west support columns and overhead beams in Building 23 were numbered 1 to 31 (Fig. 2, p. ll), and the north-south columns were
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labeled AA, A, B, and C, dividing the building into a series of survey blocks. The northwest corner of each survey block was designated as the grid block identifier.
Using a NaI scintillation probe connected to a Victoreen ratemeter, surface gamma levels were recorded for accessible areas of the floor and walls inside the building and in selected areas outdoors. The detector was held approximately 2 in. above the floor/ground surface, and measurements were recorded and then converted to m. Using a Geiger- Mueller pancake detector, beta-gamma levels were recorded and then converted to mrad/h. Alpha levels were measured at selected locations with a Bicron ratemeter connected to an ORNL ZnS scintillation probe and were then converted to dpm/lOO cm2.
Dust and debris samples were collected inside the buildin from areas where residuals may have been deposited; these samples were analyzed for ‘4a =%I’h and =U. Smears were obtained from selected surfaces to establish transferable alpha and beta-gamma activity levels. Soil samples collected outdoors to depths of 15 cm were analyzed for 226Ra, 232Th, 23&T
U.
SURVEY RESULTS
DOE guidelines are summarized in Table 1 (p. 30). Typical background radiation levels for Massachusetts are presented in Table 2 (p. 32). These data are provided for comparison with survey results presented in this section. All direct measurement results presented in this report are gross readings; background radiation levels have not been subtracted. Similarly, background concentrations have not been subtracted from radionuclide concentrations measured in soil, dust, and debris samples. Removable radioactivity levels (smears) are reported as net disintegrations per minute (dpm) with background subtracted.
Current photographs of the site are shown in Figs. 3 and 4 (p. 12).
GAMMAEXPOSURERATEMEAS-
Results of gamma exposure rate measurements at Building 23 are shown in Figs. 5 and 6 (pp. 13 and 14). Gamma exposure rates at 1 m above the floor in the center of the north and the center of the south sections of grid blocks Al through A30 (Fig. 5, p. 13) ranged from 5 to 11 a/h; surface exposure rates at the same points ranged from 5 to 13 m. A gamma scan (Fig. 6, p. 14) of accessible floor and wall surfaces showed that, generally, highest gamma levels were associated with bricks, concrete, and other such naturally radioactive materials used in paving and building construction. Gamma levels in the east end of the building were near typical background levels for Massachusetts (Table 2, p. 32); however, some gamma exposure rates in the west end of the building were definitely elevated: 30 a/h on the north side of the west entrance, 32 IcRlh in grid block Al, and 26 m in grid block A5.
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BETA-GAMMA DOSE RATE MEASUREMENTS
Ranges of beta-gamma dose rates measured in grid blocks at Building 23 are shown in Fig. 7 (p. 15). Highest beta-gamma levels were 4 and 2.9 mrad/h found in grid blocks Al and A2, respectively. Beta-gamma dose rates exceeded background levels of 0.02 to 0.08 mrad/h in grid blocks Al through A6, A8, A9, All, A13, Bl, B2, and B5.
DIRECT AND REMOVABLE ALPHA AND BETA-GAMMA RADIOACIWITY
Direct alpha and beta-gamma activity levels were measured at 30 locations in grid blocks Al through A17. Results are given in Table 3 (p. 33). Directly measured alpha activity ranged from below the minimum detectable activity (MDA*) to 2900 dpm/lOO cm2 with 15 locations showing measurable alpha activity. One measurement exceeded 1000 dpm/lOO cm2. Directly measured beta-gamma activity ranged from 0.02 to 4 mradh with 15 locations showing measurable beta-gamma activity. Four measurements exceeded the DOE guideline of 1.0 mrad/h in a loo-cm2 area.
After recording the direct measurements, the locations were smeared to determine if removable activity was present. Results from smear analyses (Table 3, p. 33) indicate no removable beta-gamma activity above the instrument-specific MDA*; removable alpha activity was above the instrument-specific MDA in 4 of the 30 smear samples.
SOIL AND INDOOR DUST AND DEBRIS SAMF’LES
Radionuclide analysis was performed on 2 outdoor soil samples and 32 indoor dust and debris samples. Samples locations are shown on Fig. 8 (p. 16) and analytical results are listed in Table 4 (p. 36). Soil concentrations of 226Ra (0.3 and 1.0 pCi/g), =2Th (0.4 and 1.4 pCi/g), and mu (< 1.4 and 1.9 pCi/g) were similar to typical background concentrations for Massachusetts (Table 2, p. 32).
Concentrations of 226Ra, 232Th, and usU in dust and debris samples ranged from 0.16 to 0.75 pCi/g, 0.11 to 0.8 pa/g, and 6.0 to 36,000 pCi/g, res ectively.
P (Elevated
concentrations of uranium sometimes mask the true concentration of %Ra; in these cases, concentrations of 226 Ra are reported as less than (<) the minimum concentration that can be detected by the analytical procedure in the presence of elevated uranium.) Highest concentrations of 23s U (36,000 pCi/g) were found in dust deposited inside a concrete floor anchor located underneath the wooden flooring of grid block A5. Uranium-238 concentrations of 240 and 120 pCi/g were found in floor debris samples (Ml1 and M31); chips from the brick facing of column B2 (M32) contained 900 pCi/g usU. Uranium-238 concentrations in dust samples from overhead beams were converted from pCi/g to dpm/lOO cm2 in order to compare these values with DOE guideline values for removable
*The instrument-specific minimum detectable activities (MDAs) for directly measured and removable alpha radiation levels are 25 and 10 dpm/lOO cm2, respectively. For directly measured and removable beta-gamma radiation levels the MDAs are 0.01 mrad/h and 200 dpm/lOO cm2, respectively.
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surface contamination (Table 1, p. 30). Table 5 (p. 38) shows that 17 of 23 dust samples from overhead beams contained mu at concentrations 2100% of the DOE guideline of 1000 dpm/lOO cm2 for removable surface contamination (Table 1, p. 30).
Two dust samples, Ml0 and M31, were selected for uranium isotopic analysis to determine if the uranium content was normal or enriched. Normally, uranium contains 0.711% usU. Uranium in which the 235 isotope concentration has been artificially increased above the normal level is called enriched uranium. Sample Ml0 contained the normal percentage of 235U; sample M31 had been slightly enriched to 2.16% =‘U.
Radiation measurements prior to and after collection of dust and debris samples are given in Table 6 (p. 39). Frequently, alpha radiation levels, and in some cases beta-gamma radiation levels, remained elevated after sample collection, showing that scraping away the dust or debris did not completely eliminate all contamination.
DISI’RIBUTION OF CONTAMINATION
Radiological contamination in Building 23 was concentrated in the westernmost 15 grid areas, primarily in grid blocks Al through A15. This central area of the building was relatively free of debris and clutter, allowing good access to the area. Only a few spots of contamination were found on the floors and walls, but overhead beams and horizontal surfaces were consistently elevated. Some contamination was evident in the westernmost B grid blocks, but clutter and debris in this area prevented a thorough survey. Anomalies identified in this area (Fig. 7, p. 15) included a radiator on the south wall of grid block Bl with beta-gamma dose rates of 0.1 to 0.4 mradih; a spot on the floor at column C2 with beta-gamma dose rates of 0.2 mrad/h; elevated beta-gamma dose rates in the northwest corner of grid block B2; and a circular area on the floor near the southeast corner of grid block B5 with beta-gamma dose rates of 0.3 mrad/h. No anomalies were identified in grid blocks AA1 through AAlO. Highlights of the survey of the central part of the building are presented in Figs. 9 through 19 (pp. 17 through 27).
Grid Block Al and Building Exterior
On the west end of the building, contamination was identified on the building exterior surface, underneath a former window approximately 4 ft south of the main entrance and 1 ft above the ground. At this location (Fig. 20, p. 28) beta-gamma dose rates measured 0.7 mrad/h and maximum alpha activity reached 2900 dpm/lOO cm2. Smear 17 from this area demonstrated that the contamination was not removable (Table 3, p. 33).
Other details of the survey of grid block Al are diagramed in Fig. 9 (p. 17). (Solid lines represent the floor area; extended dashed lines represent the walls.) North of the concrete ramp immediately inside the main entrance, an elevated area (Fig. 21, p. 28) contained gamma exposure rates of 32 a/h and beta-gamma dose rates up to 1.3 mrad/h. Debris sample M31 collected at this location was slightly enriched (2.16% 235U) and contained 120 pCi/g mu (Table 4, p. 36). Beta-gamma dose rates of 1.5 mrad/h were found on the wall and on a ledge just north of the main entrance (Fig. 22, p. 29). The west wall south of
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the main entrance had beta-gamma dose rates up to 4 mrad/h and alpha levels of 650 dpm/lOO cm2. Smear 11 (Table 3, p. 33) from this area showed that 36 dpm/lOO cm2 of the alpha activity was removable. Beta-gamma levels near column B2 reached 2.9 mrad/h. Beta-gamma dose rates in grid block Al consistently exceeded the DOE guideline of 0.2 mrad/h averaged over not more than 1 m2 and 1.0 mrad/h in any lOO-cm2 area (Table 1, p. 30). Dust samples from overhead beams (M3-M6, Table 5, p. 38) contained 170 to 340 pCi/g (2000 to 5300 dprn/lOO cm 2 %IJ, which is 2 to 5 times the DOE guideline for ) residual removable surface contamination (Table 1, p. 30).
Grid Bkxk A2
Beta-gamma dose rates in grid block A2 (Fig. 10, p. 18) reached 2.9 mrad/h on the brick facing of column B2 (Fig. 23, p. 29); alpha levels were 300 dpm/lOO cm2. Radiological analysis of chips of the brick facing material (M32, Table 4, p. 36) demonstrated the presence of 900 pCi/g 238U. Smear 13 (Table 3, p. 33) from this area showed that 32 dpm/lOO cm2 of the alpha activity was removable. Dust from a high-wall window sill located between columns B2 and B3 contained 1300 pCi/g (M30, Table 4, p. 36). Dust from an overhead beam in grid block A2 also contained 1300 pCi/g mu (1400 dpm/lOO cm2, M29, Table 5, p. 38), which was 1.4 times the DOE guideline for removable alpha activity (Tables 1 and 5, pp. 30 and 38).
Other areas of elevated beta-gamma radiation were observed around column B3 (>0.2 mrad/h), column A2 (1.4 and 1.9 mrad/h), and column A3 (~0.2 mrad/h). Spots on the floor measured 1.2 mrad/h (beta-gamma) and 28 dpm/lOO cm2 (alpha).
Grid Block A3
In grid block A3 (Fig. 11, p. 19) columns B3 and B4 showed beta-gamma dose rates of 0.4 and 0.1 mrad/h, respectively. Beta-gamma dose rates on the radiator and behind the radiator on the north wall reached 0.8 mrad/h; alpha levels reached 120 dpm/lOO cm2. Smears 14, 15, and A3 from these areas (columns B3, B4, and the north wall) did not contain removable radioactivity (Table 3, p. 33) above the instrument-specific MDA Beta- gamma dose rates of 0.2 mrad/h were measured on top of an electrical box and in an elevated area near the base of column A4; dose rates of 0.6 mrad/h were measured on the wall below the radiator near the floor. Dust samples from overhead beams (M7-M9, Table 5, p. 38) demonstrated the presence of al-l at concentrations of 48 to 130 pCi/g (1500 to 4000 dpm/lOO cm2), which is 150% to 400% of the DOE guideline for residual removable surface contamination (Table 1, p. 30).
Grid Block A4
On the north wall of grid block A4 (Fig. 12, p. 20), beta-gamma dose rates on the brick behind the radiator reached 0.1 mrad/h; alpha radiation levels measured 110 dpm/lOO cm2. Beta-gamma dose rates of 0.2 mrad/h were measured at several places on column A5 and at the floor and column join of column B5. Smear A5 (Table 3, p. 33) from column A5 did not exhibit removable radioactivity above the MDA
Grid Block A5
-
,-
I-
C
In grid block A5 (Fig. 13, p. 21), a spot on the floor near column A5 showed gamma exposure rates of 14 to 26 m, alpha activity levels of 2900 dpm/lOO cm2, and beta-gamma dose rates up to 0.2 mrad/h. Beta-gamma levels on the radiator on the north wall ranged from 0.2 to 0.5 mrad/h; three spots near column A6 measured 0.4 mrad/h, and a contaminated region at column A6 ranged from 0.05 to 0.2 mrad/h. Smear A5 from the north wall and smear 16 from column B5 (Table 3, p. 33) did not contain removable radioactivity above the MDA
used Samples Ml and M2 mark the location of a concrete floor anchor that was probably to anchor machinery. Dust collected from this location (Ml, Table 4, p. 36) contained
36,000 pCi/g =LJ. Dust from two overhead beams (MlO, M14, Table 5, p. 38) contained 25 and 35 pCi/g (1000 and 1200 dpm/lOO cm2) =U, which is 100% and 120% of the DOE guideline for residual removable surface contamination (Table 1, p. 30).
Grid Block A6
Grid block A6 (Fig. 14, p. 22) showed elevated beta-gamma levels on the north wall. Contaminated spots on column A6 and around the radiator ranged from 0.2 to 0.6 mrad/h. The brick behind the radiator ranged from 0.02 to 0.1 mrad/h. Smear A6 (Table 3, p. 33) from the wall behind the radiator contained 90 dpm/lOO cm2 removable alpha activity. Firebrick in the center of the floor exhibited beta-gamma levels of 0.02 to 0.1 mrad/h. Dust samples Ml2 and Ml3 (Table 5, p. 38) from overhead beams contained 330 and 60 pCi/g (9000 and 2600 dpm/lOO cm2) 238 U, which is 9 and 2.6 times the DOE guideline for residual removable surface contamination, respectively.
Grid Block A7 and A8
Elevated gamma exposure rates of 12 and 16 &/h in grid block A7 and A8 (Figs. 15 and 16, pp. 23 and 24) are typical of naturally occurring radioactive substances present in bricks, concrete, and other such materials used in building construction. Beta-gamma dose rates in these grid blocks generally ranged from 0.02 to 0.08 mrad/h on the walls and floor. Alpha activity measured less than the MDA (~25 dpm/lOO cm2) on low walls. Smears A7 and A8 contained no removable radioactivity above MDA Dust sample Ml5 (Table 5, p. 38) from an overhead beam contained 350 pCi/g (12,000 dpm/lOO cm2) 238U, which is 1200% of the DOE guideline for residual removable surface contamination (Table 1, p. 30).
Grid Block A9
In grid block A9 (Fig. 17, p. 25), an area of contamination on the floor near column BlO showed beta-gamma dose rates of 0.02 to 0.5 mrad/h and alpha levels of 43 dprn/lOO cm2. Cozosite floor debris collected at this location (Mll, Table 4, p. 36) contained 240 pCi/g U. Two additional spots of slightly elevated alpha activity were noted on the floor (57 and 77 dpm/lOO cm2). Beta-gamma activity on the floor ranged from 0.02 to 0.08 mrad/h, and gamma levels reached 16 pR/h in an area where firebrick was present. Dust samples (M16, M17, and M18, Table 5, p. 38) collected from overhead beams
8
contained 16, 57, and 65 pCi/g (900, 1300, and 2800 dpm/lOO cm2) 238U, which is 90%, 130%, and 280%, respectively, of the DOE guideline for residual removable contamination (Table 1, p. 30).
Grid Block All
An area with spots of elevated surface beta-gamma activity ranging from 0.1 to 0.8 mrad/h was identified in grid block All (Fig. 18, p. 26) on the west side of the furnace (Fig. 4, p. 12). Similar spots on the east side of the furnace ranged from 0.1 to 0.2 mrad/h. Overhead beams in the block showed beta-gamma activity of 0.1 mrad/h, and an electrical conduit on the north wall measured 0.3 mrad/h.
Grid Block Al3
Surface gamma exposure rates, beta-gamma dose rates, and alpha activity levels for the floors and lower walls in grid block Al3 (Fig. 19, p- 27) were near typical background levels for Building 23. Dust sam le Ml9 (Table 5, p. 38) from an overhead beam contained 50 pCi/g (1400 dpm/lOO cm f ) 238U, which is 1.4 times the DOE guideline residual removable surface contamination (Table 1, p. 30).
SIGNIFICANCE OF FINDINGS
Radionuclide analysis of soil, dust, and debris, and analysis of smear samples collected at Building 23 from the former Chapman Valve facility, Indian Orchard, Massachusetts, indicate that residual 238 U attributable to former AEC-supported operations is present at this site. Elevated levels of radioactivity were particularly evident on the floors and walls in the western part of the central area of the building (grid blocks Al through A6 , but contamination on overhead beams was not limited to this area. Concentrations of 2 3i U in dust samples collected from overhead beams exceeded DOE guidelines in grid blocks Al through Al4 and remained elevated but below guidelines in grid blocks Al5 through A19. Dust on a movable overhead crane in grid block A23 was well above the guideline, probably because the crane had at some time been located further west. A floor debris sample collected just north of the main entrance in rid block Al contained uranium that had been slightly enriched (from 0.711% to 2.16% 2&i U). Some contamination was evident in grid blocks Bl through B5, but clutter and debris in this area prevented a thorough survey. No anomalies were identified in grid blocks AA1 through AAlO.
9
REFERENCES
1. U. S. Department of Energy, A Background Report for the Formerly Utilized Manhattan Engineer District/Atomic Energy Commission Sites Program, DOE/EV-0097, September 1980.
2. Historical information on Crane Company (Former Chapman Valve Manufacturing Company), 203 Hampshire Street, Indian Orchard, Massachusetts, compiled by Roy E Weston, Inc., for Division of Off-Site Programs, Office of Eastern Area Programs, Office of Environmental Restoration, U.S. Department of Energy, Washington, DC, 2 pp. (no date).
3. T. J. Ungerland, Associate General Council, Crane Company, New York, NY, letter (with attachments) to J. J. Fiore, U.S. Department of Energy, Washington, DC, December 1987.
4. T E. Myrick, B. A Berven, W. D. Cottrell, W. A Goldsmith, and E E Haywood, Procedures Manual for the OWL Radiological Survey Activities (RASA) Program, ORNL/TM-8600, Martin Marietta Energy Systems, Inc., Oak Ridge Nat]. Lab., April 1987.
ORNL-DWG 92-6727
MOXON STREET
FEET
:* Nh MmRs
FORMER CHAPMAN VALVE MANUFACTURING COMPANY
L I
MANSFIELD PAPER COMPANY
PINE VALE STREET
__--- ___-. ____- _____ _____ ---------- __--- __--- ___.- _____ -====_ _____ __.-- ___-- _____ ____. __.-- ___.- _____ _-_-- _ _ _ _ _ _ - _ _ _ _ _ - - ___---- ___.--- _-_____ _ _ _ . . - -
~
__--___ ___- ____ _ _ _ _ _ - - ___--_-- _--__-- _--_--- - _ _ _ _ . - - _ _ _ _ _ -. _ _ _ _ _ _ . _--__.. __-__.. _--____ _ _ _ - - - - _ _ _ . . - - _--__.. __-__.. _ _ _ - . - - __-__-. __--___ _ _ _ _ _ - - _ _ _ . . - - _ _ _ - - - - _ _ _ _ _ _ . _--_--- _ _ _ - . - -
,BUILDING 23
Fig. 1. Location of Building 23 (Department No. 40) at the site of the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts.
z+-- 32 L i
if2 W
k! L >
00
Ll
I I
i? --
: --
E --
d- cu --
2 --
s --
03 __ 7
+ + + + + + + + + + + + : l
I CL) c-
d- __
7 C-J __
T 0 --
I--
al --
CD --
-e --
cu --
3 5 3 2 3 z ‘3 i; F Q)
5 3 G
d g zi -0 3%
3’” a Ki 34 E 9 2 al
) g+j ge ~~ -fi 8s 23 aA2 q 3%
‘: t: 38 sa W
C a* 1%
E” o;? 20 $2 19, $9 Lla Y 3%
I!$ lEIE d B 3s $5 ‘j; 8 o” 5%
(d s2 zg 3: Zk 1 “; 22 8
ORNL-PHOTO 1140-92
Fig. 3. View looking east at the main entrance to Building 23 at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts.
ORNL-PHOTO 1141-92
Fig. 4. View inside the main entrance looking east at grid blocks Al through A30 in the center of Building 23 (Indian Orchard, Massachusetts). Columns labeled B are on the right; those labeled A are on the left. Dust samples were collected from overhead beams visible at the top of the photo.
z --
: --
s --
2 --
N CA --
z --
03 __
7
+ +
+ wIb
+ +
+ da
+ rnlw
+ -lb
t ata
+ do
+ +-O
+
ala +
+ + i
dw
+ + + r-b
+ + + 00 _I.-
A2
mlm
Or3 -I.-
+ r-lb
a+
car-
+-
QIW
WIW
do
+ + da
4r-
+--
4W
4w
+ +-- +
f+
da
4W
/ I I
WI@
da +m
i+
I I
I I
b/b
+ +
+-
da
+ da
da
a+
P.W
+ I 1
4~ +
i- m
a3 I I
$I 2 *rl e n # L s t 8 2 1 a ‘6 %
3 3 s a i : 1 9 i d ‘il t3Ej z 3;; :# $g @
-s $1 Vh 32 z; Q
) 2P BE g$ b 5 Fp 32 Q
a%
A* da s3 0 d d 31 v1a 8 G
O
.3 g r& ‘- x
14
ORNL-DWG 92-6730
AA
A
7-30 (HoRlli SIDE
ouTsoE DOOR)
B - ENCLOSED OFFICE -
c -
GRID BLOCK r-l
I.D. -
FEET 0 50 0 15
METERS
2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I I 1 I I
11 10 10 9 9 10 IO 10 10 10 6 6 MUCH DEBRIS a STANDlNo WATER
19-13) (6-13) (S-12) (7-10) (7-10) (4-7) (4-6) FREBRCK FURN4CE BED - 13-16
I I I I I I I I I I I I I I I I I I 1 1 I I I I I r I I 1 I I I I I ++++++++++++
8 9 9 9 9 9 9 9 9 0 8 8 7 7 7 6 6 6
(7-X) (7-12) (7-12) (7-12) (5-26) (7-12) (S-12) (5-12) (5-14) (7-11) (4-11) (4-11) (s-12) (5-6) (5-12) (4-12) (5-7) (4-D)
HICHEST GAMMA LEVELS AT BRICK WALLS MD OMR FIREBRICK FLOOR
NosuRvEY ROOU LOCKED
+ I I I I I
+ + + r : I I I I I I I I I I I
I I 12 + I L I I 1 I I I I 1 I I 1
0 0 9 8 0 13 9 9 9 BRtCK
, El Tzz
9 9 9
MAX 10 MAX 10 M 11 UAX 12 u&x 12 WALLS
I I I Mu 13 MAX 13 I I I I I + I
---- Yuca4 DEBRIS VtLIKh SMALL Roou WllH oNFLooR BRICK WN.L!j
MUCH DEBRJS
Fig. 6. Average surface gamma exposure rates @R/h) measured in grid blocks at Building 23, Indian Orchard, Massachusetts. Ranges are given in parentheses.
FL k- I u-3
64 CL
ti W
G
L >
00
dl
z 2 CL> cd
XJ
Ri
%
co 7 co 7 d- T--
cl 7 0 T--
co
CD
d-
N
4 P B 6 4 ? 8 d 4 ‘: .
8 d
.
4 B -
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L
+ + + + + + + + + + + + t
$3 66 I 88 dd
I !28 dd I Ei8 66
&s dd I 8c-d
dd
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I g4) do I s:$ dd I 8 66 f gc-4 dd I !28 dd I 8- 66 I 80 6: I 2N 66
sa3 6.5
+ I s;s dd I 8s d-5
p ~~
--G+ . .
+p$-j+ I G
C
+-F-+- 8s dd
+I +
ZkG
dd r
8s dd
I3
ss 8:: ‘Ts 88 dd
I 1
I
L---t I? d
m
0
16
ORNL-DWG 92-6732
M = DUST & DEBRIS SAMPLES
S,B = SOIL SAMPLES
GRID BLOCK
I.D. 0 15 METERS
2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 AA I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
I I I I I I I 1 I I I I I 1 I I I I I I 1 1 I I I I I I I
I I
A I I I I I I I I I I I I I I I I I I I I I I I I I I I I r I
l M13 Mi6
1 I I I ++++++++
’ M3 l M8 .M’ M31
M2 M6 M7 V’
M! 4 *Ml0 .M15 M! 8 M260 l M27 M28
l
A
Sl l
B
C
M29 l M5 Ml7
.M9 0 Ml1
/c\ + I I +
M32 M30 I I I 1 ,+
Ml9 M21 a M;O
M25 l
M23
tvY22 0
M.24 0
+ + L ‘i
(OVERHEAD CRANE) I I I I I I I I I I 1 I I I I I I I I I I I I I
+ + + +
Blo
Fig. 8. Locations of soil, dust, and debris samples collected at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts.
17
ORNL-DWG 92-6733
a-
,-
RADIATOR AVG 0.05-o. 1 p-7
---------- ~.-E -
RADIATOR
*OVERHEAD BEAM
o”.; p-y, 5 y
0.2 P-r
ENTRANCE + OVERHEAD BEAM
0.5 p”̂ : 47
SMEAR 17 BUILDING EXTERIOR A SPOTTY 4 FT S OF MAIN ENTRANCE 0.08-4 p-7
1 FT ABOVE GROUND
0.7 B-7 WHOLE WALL 550 a
2900 MAX a SMEAR 11
4 B-r l
650 a ----------------------.
0
OBSCURED BY - SHELVING
.
0.04-0.08 p-y
B-16 y
OVERHEAD BEAM M5 0.4 6-y 6~
<25 a . -‘; PLYWOOD
N
0 1 3 METERS
42 ‘.46-y
a = dpm/lOO cm* P-y = mrad/h
y = ,b’h
I I I I NORTH I ? WALL ----I
F L GRID
WEST 0 BLOCK WALL 0 ID
R ----I ~ Y- z:LT
IVERHEAD 3EAM
?3 p-y 4 7
0.8-2.9 ~-y
\ SMEAR 12 0.8 8-y 33a
Fig. 9. Surface gamma exposure rates (a/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block Al.
__---- .,..__.. - - -~- ..-~.- ~~~--
AREP
A2 7
/ SMEAR Al
1.4p-y 35 a
/ 28a
ROOF VENT - 0.02-0.05 P-y
OVERHEAD /
SPRINKLER PIPE 0.1-0.2 p-y
82 /
SMEAR 12 0.8 /3-y
TOP OF ELECTRICAL BOX
0.2 P-r\
ao.2 P-r
m 1.9 p-y AREP
150 a
0
//’ . I.429
OVERHEAD BEAM 0.6 P-y
FLOOR.
0.02-0.08 P-y 7-12 Y
AVG 8-9 Y
I 1 I I I I I I I I I I I
‘9 I I
?
18
A3
>0.2 p-y
330s AdEA >0.2p-Y AREA 10.2 P-7
83 ‘SMEAR 14
125 a 0 4 P-r
ORNL-DWG 92-6734
FEET 0 a
0 1 3 METERS
a = dpm/lOO cm 2 P-7 = mrad/h
Y = p R/h
+
F L
0 0 R
L NORTH WALL
GRID BLOCK
ID
q SUPPORT COLUMN
Fig. 10. Surface gamma exposure rates (s/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A2.
- -. I I ---- _
19
0.2 P-y- ON TOP OF ELECTRICAL BOX
AZ
OVERHEAC BEAb
0.2 a!*
5 ’
BXa I
r SMEAR A3 120 a 0.2-0.8 P-v
I I I I I I i I I I
b
+
7-12 y
AVG 8-9 y
I SMEAR 14 ~25 a
0 4 P-r
ORNL-DWG 92-6735
FEET
II 0 1 3
METERS
0.8 P-r
0.2 P-r
2 cx = dpm/lOO cm
P-7 = mrad/h 44
y = P R/h IVERHEAD 3EAM 18 1.06 P-y
1 Y
OVERHEAD BEAM M9 0.2 p-y 5Y
SMEAR 15 <25a 0.1 P-y
84
+
F L 0 0 R i
NORTH - WALL
GRID BLOCK
IO
q SUPPORT COLUMN
Fig. 11. Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A3.
20
FINNED RADIATOR LINES
\
BRICK WALL - 0.08-0.1 p-7
A4
SMEAR 15,
\ 84
PARTIALLY OBSCURED / DUE TO HEAVY WORK BENCH
0.1-0.2 @-- COLUMN FACE
\
\ - 1lOa
0.08-0.2 p-7 29 a ON COLUMN
0.02-O 05 p-y FLOOR
7-12 y HIGHER AT BRICK WALLS
43 a
0.2 p-y BEHIND SUPPORl
’ BEAM
0.1-0.2 p-y ‘ON FACE OF SUPPORT BRICK COLUMN \ SMEAR A4 0.2 p-y 63 a
jo.2 P-r AT FLOOR AND COLUMN JOIN
- WOOD 0.02-0.05 P-y
1 METAL SCREEN WITH CROSSBARS
ORNL-DWG 92-6736
A!
t
FEET
+
II 5
0 1 3 METERS
a = dpm/lOO cm2 P-y = mrod/h
Y = .R/h
I I I ’ F L
L 0 0 R
j 4
NORTH WALL
rl
GRID BLOCK
ID
SOUTH WALL
Fig. 12. Surface gamma exposure rates (IrR/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A4
--
21 --
em
I-
“-
A5
2900 a /
14-26 7
OVERHEAD BEAM
Ml4 0 08 p-y
4-r
85
SMEAR 16 ’ 0.2 8-y t25 a
RADIATOR / 0.2-0.5 p-7 4 11111111111111111111 t: .-
\\ 1 ‘0.1-0.2 0-y
ON FLOOR
Ml 01.1 M2
0.02-0.05 8-7
5-12 y
AVG 8-9 7
WOOD - 26’a
ORNL-DWG 92-6737
N
A FEET
:ucAR A5 J.-t p-7 0 1 3
<25 a METERS
I.4 f9-7 _
0.05-0.2 p-7 a = dpm/lOO cm‘
P-y = mrod/h r6 0.4 p-7
-Y
VERHEAO EAM 110 1.05 p-7 17
86 0.02-0.05 0-y
> METAL SCREEN WITH CROSSBARS
i NORTH ? WALL
F L
!
0 0 R
SOUTH +- WALL
I GRID BLOCK
ID
Fig. 13. Surface gamma exposure rates @R/h), beta- gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A5
22
0.2-0.3 @-; ON \ COLUMN
A6
0.02-0.1 p-y / ON BRICK
B6
GLASS AND WOOD 0.5 p-y
0.3 p-y ON WALL BEHIND RADIATOR
r---------l I FIREBRICK I I 0.02-0.1 p-y :
; 7-12 y : ’ LL---___-;
AVG 8-9 7
0.02-0.05 p-y FLOOR
OVERHEAD BEAM
Ml2 0.2 8-r I
+
WOODEN WALL AND METAL SCREEN
SMEAR A6 R 28~
0.4 6-y ‘ON WALL 47 BEHIND
RADIATOR
\ OVERHEAD BEAM Ml3 0.03 8-y 57
87
_ OPENING
ORNL-DWG 92-6738
FEET FEET
0 1 0 1 3 3 METERS METERS
a = dpm/lOO cm’ P-7 = mrod/h
Y = P R/h
1 1 I I NORTH i +r WALL
w
GRID BLOCK
ID
/R/
Fig. 14. Surface gamma exposure rates (a/h), beta- gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm*) in grid block A6.
_... - .~ . . . . .._...._ -.. ._- ..__ ““._
23 ,*“.
e-5
*-
em
.-
I-
.-
I-
.“-
A7
NOOD AND dETAL
SMEAR A7 <25 a
FIREBRICK /
0.02-0.08 8-7
5-12 y
AVG 8-9 Y
. <25 o1 OPENING TO
BRICK OVERHE. CRANE
3.o:p~oy.o5 BAY
OPENING
48
88
ORNL-DWG 92-6739
N A FEET
-I- JL II -- 5 II 0 1 3
METERS
2 a = dpm/100 cm
P-r = Y =
I / 4
F L 0
[
0 R
i 4
mrad/h
,u R/h
NORTH - WALL
m
GRID BLOCK
ID
SOUTH - WALL
Fig. 15. Surface gamma exposure rates (&/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm*) in grid block A7.
30
OVERHEAC BEAM
Ml5 0.2 p-y
5Y
PLYWOOD AND GLASS
/
/ SMEAR A8 <25 a 0.02-0.08 p-y
FIREBRICK
UP TO 16 ,. ----_--__--.
-LOORS AND WALLS
0.02-0.08 p-y
5-12 y
AVG 8-9 Y
. <25 a
24
49
39
ORNL-DWG 92-6740
Iv
f
FEET
+
0 5
0 1 3 METERS
a = dpm/lOO cm2
P-y = mrod/h
Y = I-L R/h
GRID BLOCK
ID
I SOUTH 1 7 WALL
F ig. 16. Surface gamma exposure rates (m), beta- gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm’) in grid block AS.
- .” ..-. -..... ..-.. .-. -. ..--_l_l . -. .
25
ORNL-DWG 92-6741
I-
I”-
.-
A9
OVERHEAC BEAk
MlE 0.02 p-7
41
<25 a
OVERHEAD BEAM
Ml7
0 1 P-r \
4Y
El9
FIREBRICK
UP TO 16 Y
0.02-0.08 P-y
5-14 y
AVG 8-9 Y
77 a
i
0.02-0.05 /3-y
410
57 a
IVERHEAD 3EAM Ml8 3.1 P-y 5Y
0.02-0.5 p-y 43 a Ml 1
BlO
FEET 0 a
0 1 3 METERS
2 a = dpm/lOO cm
P-y = mrad/h
y = p R/h
F L ! 0 0 R
i+
rl SOUTH WALL
GRID BLOCK
ID
Fig. 17. Surface gamma exposure rates (crR/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A9.
. .-
26
ORNL-DWG 92-6742
Al ’
OVERHEAD
BEAM ’
0.1 p-y
5Y
Bll
SMEAR Al <25 a 0.3 p-y ON . ELECTRICA CONDUIT
I 7
1 FURNACE 1 a.8 pr
j.2 p-y
1.2 p-y
~ 0.1 p-y
0.02-0.05 p-y
EXCLUDING
HOT SPOTS
-11 y
AVG 7-8 y
I I I I I I I I
1 I I I
i; I
1
i ,_I c--
.,
A12
3.2 0-y
0.1 p-y
\ OVERHEAD
BEAM
0.1 p-y
4Y
_ PIPE
CHASE
COVERING
812
FEE7 0 5 0 1 3
METERS
a = dpm/lOO cm2 P-y = mrod/h
y = f-Lw
I I I I NORTH I + WALL
F 1 L GRID
0 BLOCK
0 ID
L- R
Fig. 18. Surface gamma exposure rates @R/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block All.
. _ I_. _
27
,A-
.-
.-
.-
Al?
OVERHEAD BEAM /’
0.06 P-y
4Y
813
SMEAR Al3 0.02-0.05 p-7
l <25 a
OVERHEAC BEAM \ Ml9 0.06 p-7
3Y
0.02-0.05 /3-y
ON WALLS AND FLOORS
4-11 y
AVG 7-8 y
ORNL-DWG 92-6743
FEET
0 1 3 METERS
Al4
814
a = dpm/lOO cm2 ,8--y = mrad/h
y = p R/h
I I t ! NORTH 1 +- WALL
F
1
L GRID
0 BLOCK
0 ID
L--s R
Fig. 19. Surface gamma exposure rates (ccR/h), beta-gamma dose rates (mrad/h), and alpha activity levels (dpm/lOO cm2) in grid block A13.
ORNL-PHOTO 1142-92
Fig. 20. View looking east northeast at Building 23, Indian Orchard, Massachusetts. Contamination was identified on the exterior of the building in the vicinity of the arrow.
ORNL-PHOTO 1143-92
Fig. 21. View of contaminated area located north of the concrete ramp immediately inside the main entrance. The concrete entrance ramp is at the top of the photo; west wall of Building 23 is on the right.
. L
, C
*.-
a -
m. -
2 9 O R N L - P H O T O 1144 -92
Fig. 2 2 . V iew o f a r e a just n o r th o f m a in e n t rance with e leva ted b e ta - g a m m a levels o n th e wall , a l e d g e , a n d th e d o o r j a m b .
O R N L - P H O T O 1145 -92
Fig. 2 3 . V iew o f br ick fac i ng o n co l umn B 2 ( r ight s ide o f p h o to b e h i n d cab i ne t). Ch ips o f th e br ick fac i ng m a ter ia l c on ta i n e d 9 0 0 pCi /g 2 3 8 U .
-.--
30
“hble 1. Applicable guidelines for protection against radiation (Limits for uncontrolled areas)
Mode of exposure Exposure conditions Guideline value
Gamma radiation Indoor gamma radiation level 20 p.Rw (above background)
‘Ibtal residual surface contaminatior+
=lJ, z5U, U-natural (alpha emitters)
or Beta-gamma emitters”
Maximum Average Removable
15,000 dpm/lOO cm2 5,000 dpm/lOO cm2 1,000 dpm/lOO cm2
23?h, Th-natural (alpha emitters)
or ?Sr (beta-gamma emitter)
Maximum Average Removable
3,000 dpm/lOO cm2 l,ooO dpm/lOO cm2
200 dpm/lOO cm2
226Ra, 23oTh, transuranics Maximum Average Removable
300 dpm/lOO cm2 100 dpm/lOO cm2 20 dpm/lOO cm2
Beta-gamma dose Surface dose rate averaged rates over not more than 1 m2
Radionuclide con- centrations in soil (generic)
0.20 mrad/h
Maximum dose rate in any lOO-cm2 area
1.0 mradk
Maximum permissible con- centration of the following radionuclides in soil above background levels, averaged over a lOO-m2 area
z26Ra 9-h
5 pCi/g averaged over the first 15 cm of soil below the surface; 15 pCi/g when averaged over 15-cm-thick soil layers more than 15 cm below the surface
-.-. .----_---_.--_-I._-.. ._ .“__l -.--^ -l___ll.,,______ I .-_. ̂__._.“..-_.“.” .._..._ - ~..-..-_-_ _.
31 ,.-
.I-
>u
I.-
I*-
“-
Mode of Exposure
Table 1 (continued)
Exposure conditions Guideline value
Derived concentrations TJ Site suecifi&
The 20 @/h shall comply with the basic dose limit (100 mrem/year) when an appropriate-use scenario is considered.
‘DOE surface contamination guidelines are consistent with NRC Guidelines for Decontami- nation at Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By-Product, Source, or Special Nuclear Material, May 1987.
‘Beta-gamma emitters (radionuclides with decay modes other than alpha emission or spontaneous fission) except WSr, 228Ra, 2URa, mAc, 1331, ‘=I, ‘%I, l”I.
dDOE guidelines for uranium are derived on a site-specific basis. Guidelines of 35-40 pCi/g have been applied at other FUSRAF’ sites. Source: J. L. Marley and R. E Carrier, Results of the Radiological Survey at 4 Elmhurst Avenue, Color&, New York (AL219), ORNLIRASA-871117, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab., February 1988, B. A. Berven et al., Radiological Survey of the Former Keller Research Facility, Jersey City, New Jersey, DOEIEV- 0005/29, ORNL-5734, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab., February 1982.
Sources: Adapted from U.S. Department of Energy, DOE Order 5400.5, April 1990, and U.S. Department of Energy, Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites, Rev. 2, March 1987.
32
Tenable 2 Background radiation levels and concentrations of selected radionuclides in soil for Massachusetts
lype of radiation measurement or sample
Radiation level or radionuclide concentration
Range Average
Gamma exposure rate at ground surface @R/h)
6-9 7
Concentration of radionuclides
&in:1 (pCi/g)” 9-h TJ
0.70-1.8 1.1 0.76-1.2 0.97 0.69-2.7 1.2
“Values obtained from six locations in the Beverly, Massachusetts, area. Source: W. D. Cottrell and R. E Carrier, Results of the Radiological
Survey at the Kim-on Site, BeverQ, Massachusetts, ORNLm-10053, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab., May 1988 and R. D. Foley and M. S. Uziel, Radiological Survey Results at 9 and 11 Congress Street, Beverb, Massachusetts (VBOO2), ORNL/RASA-91/13, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab., May 1992.
I t t i I i i i i i i i i i r ; 1 I I i I
Table 3. Alpha and beta-gamma measurements at Building 23 at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts
Removable radioactivityd Smear Directly measured radioactivity (smears) sample Location
ID” Alphab Beta-gamma’ Alpha’ Beta-gammd (dpm/lOO cm2) (mdh) (dpm/lOO cm2) (dpm/lOO cm2)
<200
<200
<200
<200
Block A8, high wall A8-9, -17 ft above floor
Block A8, wall B8-9
Block A6, high wall B6-7, brick -17 ft above floor
Block A6, high wall A6-7, metal vent on wall adjacent to A6, -17 ft above floor
<200
<200
<200
<200
<200
Block A6, high wall A6-7, inside metal vent on wall adjacent to A6, -17 ft above floor
Block A4, high wall B4-5 I=:
<200
Block A4, high wall A4-5, -17 ft above floor
Block A2, high wall A2-3, -17 ft above floor
Block A2, high wall B2-3, verticle window sill, contamination washed from horizontal surface
Block Al, west wall, 3.5 ft N of column Bl, 2 ft above floor
<200 Block Al, south wall, 1.5 ft W of column B2, 1 ft above floor
<200 Block A2, south wall, 1 A above floor at column B2
<200 Block A3, south wall, 1 ft above floor at column B3
<200 Block A3, south wall, 1 m above floor at column B4
<200 Block A5, south wall, on column B5
36 0.02-0.05
<25 0.024.05
~25 0.02+l.o5
~25 0.02-0.05
Cl0
<IO
<lo
<lo
6 0.02 <IO g
7 71 0.05-0.08
8 43 0.02~.08
9 57 0.05~.08
10 550 0.05-0.2
<lo
<lO
<lO
14
36 11 650 4
33 0.8 Cl0 12
32
cl0
<IO
<lO
13 300 2.9
14 ~25 0.4
15 <25 0.1
16 45 0.2
Table 3 (continued)
Smear Directly measured radioactivity Removable radioactivit# sample Location
ID” Alphab
(dpm/lOO cm2) Beta-gamma” Alpha’ Beta-gammd
@ad/h) (dpm/lOO cm2) (dpm/lOO cm2)
17 2900 0.7 Cl0 c200 Outside wall, 4 ft S of main (west) entrance, 1 ft above ground
Block Al, bottom corner of column A2
Block A2, bottom corner of column A2
Block A3,6 ft E of Column A3,2 ft above floor, behind radiator
Block A4, ledge at corner of column A5
Block A5, 13 ft E column A5,3 ft above floor
Block A6, north wall, 11 ft E of column A6, 2 ft above p” floor
Block A7, north wall, wood wall 6 ft E of column A7, 3 ft above floor
Block AS, wood wall 7 ft E of column A8,3 ft above floor
Block All, 12 ft E of column All, 6 ft above floor, metal box on wall
Block A12,9 ft E of column A12, 2 ft above floor
Block A13,8 ft E of column A13,2 ft above floor
Block A15,6 ft E of column A15, 1 ft above floor
Al
A2
A3
35
150
120
1.4
1.9
0.02-0.8
<lo
<IO
<IO
<200
<200
<200
A4 63
A5 <25
A6 23
0.2
0.4
0.4
Cl0
Cl0
90
<200
<200
<200
A7 ~25 0.024.05 <IO <200
A8 ~25 0.02-0.08 Cl0 <200
All ~25 0.3 <IO <200
Al2 ~25 0.02-0.05
Al3 ~25 0.02-0.05
Al5 <25 0.024.05
<200
<200
<200
<lo
Cl0
Cl0
I I I t 1 i i 1 1 i I i i
Table 3 (continued)
Smear Directly measured radioactivity Removable radioactivityd
sample ID”
Alphab Beta-gammac Alpha’ Beta-gammd Location
(dpm/lOO cm2) (mrad/h) (dpm/lOO cm2) (dpm/lOO cm2)
Al6 ~25 0.02405 cl0 <200 Block A16,6 ft E of column A16,2 ft above floor
Al7 28 0.02405 <lo <200 Block A17,7 ft E of column A17,3 ft above floor
“Some sample locations are shown on Figs. 9-19 (p. 17-27, Smear #). bInstrument-specific minimum detectable activity (MDA) level = 25 dpm/lOO cm2. ‘MDA = 0.01 mrad/h. dRemovable radioactivity reported as net disintegration rates. Background radiation levels have been subtracted. ‘MDA = 10 dpm/lOO cm2. fMDA = 200 dpm/lOO cm2. gNot measured.
36
Table 4. conCentrations of radionuclide in soil, dust, and debris samples collected at the site of the former Chapman Valve facility, Indian Orchard, h-lassachusetts
Sample” Location Radionuclide concentration (pCi/g)b
Z26Ra =vh 238v
SIC
Bid
Ml’
MF
M3
M4
M5
M6
M7
M8
M9
Ml0
Mllh
Ml2
Ml3
Ml4
Ml5
Ml6
Ml7
Ml8
Ml9
M20
Soil Samples
West of Bldg. 23 0.33kO.01
Southeast corner of 1.0 kO.03 Bldg. 23
Dust and debris samples
Concrete floor anchor, grid block A5
Concrete floor anchor, grid block A5
Overhead beam No. 1
Overhead beam No. 1
Overhead beam No. 1
Overhead beam No. 2
Overhead beam No. 3
Overhead beam No. 4
Overhead beam No. 4
Overhead beam No. 6
Composite floor debris, grid block A9
Overhead beam No. 7
Overhead beam No. 7
Overhead beam No. 5
Overhead beam No. 8
Overhead beam No. 9
Overhead beam No. 9
Overhead beam No. 10
Overhead beam No. 14
Overhead beam No. 15
~48 f
co.9
0.75* 0.1
co.8
<0.5
~0.8
0.43* 0.09
0.7 *0.07
0.6 kO.1
0.4 *0.07
0.6 iO.l
0.6 ~0.1
0.22kO.05
0.4 *0.06
0.4 *0.08
0.16kO.03
0.6 kO.08
0.20*0.04
0.6 kO.07
0.6 iO.l
0.4 kO.02
1.4 *0.06
f
0.76iO.2
f f
f co.3
0.5 *O.l
0.7 *O.l
0.3 io.l
0.6 kO.1
0.7 *0.2
0.23kO.07
0.5 *0.07
0.5 *O.l
0.11*0.03
0.4 *O.l
0.20*0.07
0.6 kO.1
0.7 *0.2
cl.4
1.9* 0.8
36,000 *400
220 f 10
250 f 50
340 +z 6
170 f 5
310 +z 6
130 f 5
48*5
95 f 2
25*7
240 i20
330 f 10
6oi5
35 f 5
350 f 50
16 * 4
57 f 10
65 +z 7
50 f 5
37 f 5
37
Table 4 (continued)
Sample” Location Radionuclide concentraation (pCl/g)b
=Ra Tll =IJ
M21
M22
M23
M24
M25
M26
M27
M28
M29
M30
M31h
M32
Overhead beam No. 16
Overhead beam No. 17
Overhead beam No. 18
Overhead beam No. 19
Overhead beam No. 20
Overhead beam No. 23
Moveable overhead crane, grid block A23
Overhead beam No. 26
Overhead beam, grid block A2
High-wall window sill, grid block A2
West door ramp, north comer
Chips from brick facing, column B2
0.6 kO.1
0.7 *0.08
0.7 io.08
0.6 kO.07
< 1.0
0.5 kO.03
0.2 *0.04
< 1.5
<5.0
<3.0
< 1.0
< 1.4
0.7 kO.2
0.8 kO.1
0.6 kO.1
0.7 kO.1
<l.O
0.6 iO.06
0.2 *0.04
f
f
f
< 1.0
f
35 f 2
20 f 5
20 f 2
19 f 1
10 f 3
6.0* 1.5
10 f 3
6.4* 0.3
1,300 *loo
1,300 f 50
120 f 10
900 *20
“Sample locations are shown on Fig. 8 (p. 16). bIndicated counting error is at the 95% confidence level (k2u). ‘Systematic soil sample (S) taken at location irrespective of gamma exposure
rates. Sample depth O-8 cm. dBiased soil sample (B) taken from area with elevated gamma exposure rates.
Sample collected 3 ft under edge of concrete slab. Sample depth O-15 cm. ‘Sample depth O-l cm. Not measured. gSample depth l-3 cm. hSample depth O-2 cm.
_.- --___..- --..~
38
Table 5. Comparison of =U concentrations in selected dust samples from overhead beams with DOE guideline value
for removable surface contamination
Sample” Location TJ Percent of
(pCi/g) (dpm/lOO cm2) guideline value
M3
M4
M5
M6
M7
M8
M9
Ml0
Ml2
Ml3
Ml4
Ml5
Ml6
Ml7
Ml8
Ml9
M22
M23
M24
M26
M27
MB
M29
Overhead beam No. 1
Overhead beam No. 1
Overhead beam No. 1
Overhead beam No. 2
Overhead beam No. 3
Overhead beam No. 4
Overhead beam No. 4
Overhead beam No. 6
Overhead beam No. 7
Overhead beam No. 7
Overhead beam No. 5
Overhead beam No. 8
Overhead beam No. 9
Overhead beam No. 9
Overhead beam No. 10
Overhead beam No. 14
Overhead beam No. 17
Overhead beam No. 18
Overhead beam No. 19
Overhead beam No. 23
Moveable overhead crane, grid block A23
Overhead beam No. 26
Overhead beam, grid block A2
250 5,300
340 3,600
170 2,0@3
310 3,500
130 4,~
48 1,500
95 2,800
25 Loo0
330 9,aocJ
60 2633
35 1200
350 12,ooo
16 900
57 1,300
65 u33-J
50 1,400
25 500
20 530
19 490
6 200
10 1,600
6
1,300
130
1,400
530
360
200
350
400
150
280
100
900
260
120
1,200
90
130
280
140
50
53
49
20
160
13
140
“Samples collected at the site of the former Chapman Valve facility, Indian Orchard, Massachusetts. Sample locations are shown on Fig. 8 (p. 16).
-.. ._.... ..-__ ___
39 a.-
“-
*-
. I
Table 6. Alpha, be&-gamma, and gamma radiation measurements at dust and debris sample locations at the former Chapman Valve facility, Indian Orchard, Massachusetts
Alpha Beta-gamma Gamma (dpm/lOO cm*) (mrad/h) wm
After Prior to After Prior to Sample” Location collection collection collection collection
Ml and M2’
M3
M4
M5
M6
M7
M8
M9
Ml0
Ml1
Ml2
Ml3
Ml4
Ml5
Ml6
Concrete floor anchor under wooden flooring, grid block A5
110 1 4 11 17’
Overhead beam No. 1
200 0.2 0.07
Overhead beam No. 1
170 0.5 0.5
5 lad
4
Overhead beam No. 1
300 0.4 0.3 6
Overhead beam No. 2
260 0.3 0.3 4
Overhead beam No. 3
43 0.2 0.2 5
Overhead beam No. 4
200 0.06 0.06 4
Overhead beam No. 4
400 0.2 0.4 5
Overhead beam No. 6
46 0.05 0.06
Composite floor debris, grid block A9
Overhead beam No. 7
43’ 0.02- f 0.5
320 0.2 0.06
4
f
4
Overhead beam No. 7
180 0.03 0.05
Overhead beam No. 5
210 0.08 0.2
Overhead beam No. 8
990 0.2 0.1
Overhead beam No. 9
300 0.02 0.09 4
“. .-_-
40
Table 6 (continued)
Alpha Beta-gamma Gamma (dpm/lOO cm*) (mradk) Mm
After Prior to After Prior to Sample” Location collection collection collection collection
Ml7
Ml8
Ml9
M20
M21
M22
M23
M24
M25
M26
M27
M28
M29
M30
Overhead beam No. 9
Overhead beam No. 10
Overhead beam No. 14
Overhead beam No. 15
Overhead beam No. 16
Overhead beam No. 17
Overhead beam No. 18
Overhead beam No. 19
Overhead beam No. 20
Overhead beam No. 23
Moveable overhead crane, grid block A23
Overhead beam No. 26
Overhead beam, grid block A2
High-wall window sill, grid block A2
65
200
f
160
180
220
65
65
140
110
55
0.10
0.1
0.06
0.06
0.05
0.06
0.03
0.04
0.03
0.03
0.05
C25 0.02
f 0.6
f 2
0.06
0.07
0.2
0.06
0.06
0.04
0.03
0.03
0.04
0.03
0.08
0.02
0.3
f
4
3
4
4
4
3
2
2
f
f
41
.-
Table 6 (continued)
Alpha Beta-gamma (dpm/lOO cm*) (mradih)
Gamma t-1
Sample@ Location After
collection Prior to
collection After
collection Prior to
collection
M31 West door f 0.2- f 32 ramp, north 1.2 corner
M32 Chips from brick facing, column B2
300 2.9 f f
“Sample locations are shown on Fig. 8 (p. 16). ‘Dust samples collected inside concrete floor anchor previously used to anchor machinery.
Hole was too small to accommodate measurement instruments. All alpha, beta-gamma, and gamma measurements taken at top of hole.
=Gamma measurement at 1 m prior to sample collection. ‘Gamma measurement on contact after sample collection. ‘Prior to sample collection. +Jot measured.
43
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25-27. R. E. Swaja 28-30. M. S. Uziel
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EXTERNAL DISTRIBUTION
44. J. D. Berger, Oak Ridge Associated Universities, E/SH Division, Environmental Survey and Site Assessment Program, PO. Box 117, Oak Ridge, TN 37831-0117
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