ML20059L643
| ML20059L643 | |
| Person / Time | |
|---|---|
| Site: | 07001193 |
| Issue date: | 08/31/1990 |
| From: | Berger J, Friedman L OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20059L638 | List: |
| References | |
| CON-FIN-A-9076 ORU-90-1-27, ORU-90-1-27-DRFT, NUDOCS 9009270205 | |
| Download: ML20059L643 (142) | |
Text
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]'TwA w.d CONFIRMATORY SURVEY OF THE l UUAr CIMARRON CORPORATION
! conALs MIXED OXIDE FUEL FABRICATION PLANT CRESCENT, OKLAHOMA Sponsored by I
Divisionof 5
Industrialand Medical Nuclear Safety L. F. FRIEDMAN AND J. D. BERGER I
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I Environmental Survey and Site Assessment Pro 0 ram Energy / Environment Systems Division DRAR REPORT AUGUST 1990
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CONFIRMATORY SURVEY i
OF THE l
I CIMARRON CORPORATION MIXED OXIDE FUEL FASRICATION PLANT CRESCDG, OKIAHOMA I
Prepared by L F. Friedman and J. D. Berger Environment.al Survey & Site Aan===aat Program l
I Energy / Environment Systems Division l
Oak Ridge Associated Universities Oak Ridge, TN 37831 0117 I
e S.F. Barnett A.T. Payne I
O.R. Foltz J. L Payne R.C. Oosslee R.C Rookard MJ. laudeman C.F. Weaver S.A. Wical I
Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Comminaion I
Region III Office DRAFT REPORT August 1990 I
1 i
'Ihis report is based on work performed under Interagency Agreement (NRC Fin. No. A 9076) u between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge I-Associated Universities performs complementary work under contract nuruber DE.AC05 760R00033 with the U.S. Department of Enerty.
'Ihis draft report has not been given full review and patent clearance, and the dissemination of its information is only for official use. No release to the public shall be made without the approval of the Of5cc of Information Serviccs, Oak Ridge Associated Universities.
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TABLE OF CONTENTS PAGE l
IAt of Fi 11 3
I i
IJst of Tables..............................................
vi I
l introduction and Site imry...................................
1 j
i Facility Description..........................................
1 I
,ro.edur.................................................
2 Pindings and Results.........................................
5 Comparison of Survey Results with Guidelines.......................
8 I
i Suennary.................................................
10 References................................................
119 A,a w ":
Appendix A: Major Sampling and Analytical Equipment Appendix B: Measurement, Sampling, and Analytical Procedures j
' Appendix C: Guidelines for Decot.tamination and Decomminalaning of the Cimarron Corporation Mixed Oxide Fuel Fabrication Plant L
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l I
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IJST OF FIGURES i
F.AG.E FIGURE 1:
Map Indicating Location of the Cimarron Corporation Mixed Oxide P1 ant...................................
11 FIGURE 2:
Plot Plan of the r'irurron Corporation Plant Site................. 12 FIGURE 3:
Locations of Background Radiation Measurements and Baseline Samples....................................... 13 FIGURE 4:
Mixed Oxide Plant Indicating Orid System for Reference of Exterior Measurements and Sampling......................... 14 FIGURE 5:
Room 100 and Vestibule Moor Plan Showing Measurement locations............................................. 15 FIGURE 6:
Room 101 Moor Plan Showing Measurement locations............. 16 FIGURE 7:
Room 102 Floor Plan Showing Measurement locations...
17 FIOURE 8:
Room 103 Floor Plan Showing Measurement locations..
18
=
FIGURE 9:
Room 106 (Laundry Room) Floor Plan Showing Measurement locations................................... 19 FIGURE 10:
Room 108 (Instrument Room) Showing Measurement locations....... 20 FIGURE 11:
Rooms 104 and 107 Moor Plan Showing Measurement locations...... 21 FIGURE 12:
Room 105 (Women's Room) and Room 111 (Airlock) Boor Plan Showing Measurement locations............................ 22 FIGURE 13:
Room 109 (Health Physics) Floor Plan Showing Measurement locations.
23 FIGURE 14:
Room 110 Floor Plan Showing Measurement locations............
24 FIGURE 15:
Room 112 Boor Plan Showing Measurement Locations............. 25
-)
FIGURE 16:
Room 113/115 (North / South Corridor and Airlock) Floor Plan Showing Measurement locations........................
26 U
)
5 s
LIST OF FIGURES (Cestinued)
FAGE FIGURE 17:
Room 114 (Decon Room) Floor Plan Showing L
Measurement Locations..................................
27 FIOURE 18:
Room 116 (Maintenance) Floor Plan Showing Measurement
~
fanath............................................
28 I
FIGURE 19:
Room 117 (Machanlaal Room) Floor Plan Showing Measurement L~^h...........................................29 i
MOURE 20:
Room 118 (East / West Corridor) Floor Plan Showing Measurement tana*6............................................
30 FIGURE 21:
Roonr.119,120,121 br Plan Showing Measurement L~~h...........................................31 FIGURE 22:
Pit Room 121 Floor Plan Showing Measurement Locations.........
32 FIGURE 23:
Room 122/123 Ploor Plan Showing Measurement locations.........
33 FIOURE 24:
Room 124 Nr Plan Showing Measurement Locations............
34 FIOURE 25:
Room 125 (Corridor) Floor Plan Sowing Measurement Locations............................................
35 FIGURE 26:
Room 126 (Vault) Nr Plan Showing Measurement locations......
36 FIGURE 27:
Room 127 Floor Plan Showing Measurement Locations............
37 FIGURE 28:
Room 128 Floor Plan Showing Measurement Locations............
38 FIGURE 29:
Room 129 (General Lsb) Floor Plan Showing Measurement locations............................................
39 FIOURE 30:
Room 130 Floor Plan Showing Measurement locations............
40 FIOURE 31:
Room 131 Floor Plan Showing Measurement locations............
41 FIOURE 32:
Room 132 Floor Plan Showing Measurement locations............
42 FIGURE 33:
Room 133 Nr Plan Showing Measurement Locations............
43 ill
LIST OF MGURES (Centissed)
PAGE
(
MOURE 34:
Room 134 Moor Plan Showing Measurement locations............. 44 MOURE 35:
Room 135 Moor Plan Showing Measurement locations............
45 MOURE 36:
Room 136 Floor Plan Showmg Measurement locations............
46 MOURE 37:
Room 137 Floor Plan Showing Measurement locations............. 47 MOURE 38:
Room 138 Floor Plan Showing Measurernent locations............. 48 MOURE 39:
Room 139 Moor Plan Showing Measurement locations............
49 MOURE 40:
Room 140 Floor Plan Showing Measurement locations............. 50 MOURE 41:
Room 141 Floor Plan Showing Measurement locations............. 51 MOURE 42:
Room 141 Air Exhaust Vent Showing Measurement locations........ 52 MOURE 43:
Room 142 Moor Plan Showing Measurement locations............. 53 FIGURE 44:
Room 143 Floor Plan Showing Measurement locations............. 54 MOURE 45:
Cotridor Between Rooms 138 and 143 Showing Measurement l
locations............................................. 55 MOURE 46:
Room 201 (Exhaust A) Floor Plan Showing Measurement locations............................................. 56 FIGURE 47:
Room 202 (Supply Air Fan Room) Floor Plan Showing Measurement locations................................... 57 FIGURE 48:
Room B1A Moor Plan Showing Measurement locations............ 58 FIGURE 49:
Room B01 Floor Plan Showing Measurement locations............ 59 ROURE 50:
Room B02 Floor Plan Showing Measurement locations............ 60 MGURE 51:
Tunnel Moor Plan Showing Measurements locations.............. 61 MOURE 52:
Vault Roof Cold Chemical Storage Room Floor Plan Showing Measurement locations................................... 62 iv
LIST OF MGURES (Continued)
PAG.E L
MGURE $3:
Vault Room Ledge Showing Measurement locations.............. 63 MGURE $4:
HP Corridor Moor Plan Showing Measurement Locations..........
64 MGURE $5:
LWlag Dock Moor Plan Showing Measurement Locations.......... 65 MOURE 56:
Leading Dock Dockboard Recess Showing Measurement locations............................................
66 MOURE 57:
Buikling Exterior (East Side) Showing Measurement locations............................................
67 MOURE 58:
Building Exterior Showing Measurement locations on the Building, Walkways and Miscellaneous Surfaces.................. 68 M O U R E $9:
Measurement locations Along the Sanitary Drain System........... 69 MGURE 60:
Sampling Locations from Areas Identified by Gamma Scans.......... 70 MOURE 61:
Locations of Shallow Boreholes for Subsurface Soil I
Sam pling............................................
71 MOURE 62:
Sampling locations from Surface Drainage Outfalls............... 72 V
Litri OF TABLES PAGE TABLE 1:
Background Radiation levels and Baseline Radionuclide Concentrations in Soil...................................
73 l
TABLE 2:
Summary of Surface ActMty Measurement at Locations 1
Initially Exceeding Guidelines..............................
74 l
TABLE 3:
Summary of Final Building Interior Surface Activity i
Measurements......................................... 83 j
TABLE 4:
Radionuclide Leveb in Interior Paint and Concrete
)
Sam plea............................................
99 j
TABLE 5:
Radionuclide Concentrations in Soil Samples from Excavations l
Inside the Building...........................
.... 103 l
TABLE 6:
Radionuclide Concentre.tions in Samples from Barrels of l
Excavated Soil.............................
106 TABLE 7:
Summary of Locations of Elevated Gamma Exposure Rates........ 107 TABLE 8:
Uranium and Plutonium Concentrations in Soil Samples.......
108 l
TABLE 9:
Drainage Outfall Samplea and Measurements.............
114 TABLE 10:
Summary of Surface Activity Measurements on the Building Exterior, Walkways and Miscellaneous Surfaces................ 115 TABLE 11:
Radionuclide Concentrations in Minellaneous Exterior l
Sam ples..................
117 TABLE 12:
Summary of Surface Activity Measurement at locations in the Sanitary Drain System........................
.118 l
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CONFIRMATORY SURVEY 3
OF DM CD4ARRON CORPORATION r
MDED OXIDE FUEL FABRICATION PIANT CRESCENT, OKLAHOMA 1
INTRODUCI10N AND SITE HISTORY The Cimarron Corporation Plant, formerly known as the Sequoyah Fuels Corporation Cimarron l
Plant, in Crescent, Oklahoma, was operated by Kerr McGee for the manufacture of slightly (about 3%) enriched uranium and mixed oxide (uranium and plutonium) reactor fuels. De plant consisted of two major facilities - the Uranium Plant and the Mixed Oxide Plant. De Mixed Oxide Piant was in operation from 1970 until 1975, under AEC/NRC License Number SNM 1174, Docket Number 701193. De pnaammalan limits of special nuclear, byproduct, and source materials authorised for the Mined Oxide Plant were 360 kg of plutonium in any form (including associated americium), 2 g of Pu 238 as a sealed calibration source, and 700 kg of natural uranium in any form.
I Decommissioning of the Mixed Oxide facility began in 1979. All process equipment was removed and decontamination initiated. De decontamination and followup radiological surveys were I
completed in mid 1989 and a report, describing the activities and the final radiological status of the facility, was provided to the Nuclear Regulatory Commission (NRC). At the request of the NRC, I
Region III Office, the Environmental Survey and Site Assessment Program of Oak Ridge g
Associated Universities conducted a survey of the Mixed Oxide Plant to confirm that the facility B
meets the guidelines established for decommissioning.
FACILIIY DESCRIITION
%e plant is located on an approximately 450 hectare site in Logan County, Oklahoma, about 8 kilometers south of the town of Crescent (Figures 1 and 2). De Mixed Oxide Plant occupies an 2
area of approximately 0.8 ha, surrounded by a chain-link security fence. There is one 2400 m building, which consisted of manufacturing, maintenance, office, and laboratory areas. Building construction is of precast concrete exterior roof and wall panels with a poured concrete floor.
1
Dere is a basement section in the fuel processing area (north end of building) and a penthouse section, containing HVAC equipment and other utilities and services, above the central portion of the building. The main floor of the facility is basically single story to story-and a half with an above ceiling space for services. Equipment has been removed and surfaces washed, scraped, stripped, chipped, and/or scrabbled. Some inner walls and sections of Dooring have been removed.
SubGoor drains were also removed and soil excavated, where appropriate.
he below-ground liquid waste collection system has been removed, along with associated piping.
~
PROCEDURES Ohlective 3
ne objective of the survey was to confirm that the decontamination and decommissioning efforts by the licensee were effective in satisfying the established project guidelines and that the
[
supporting documentation developed by Cimarron Corporation provides an accurate and complete description of the radiological status of the site.
Docuasent Review As part of the confirmatory activities, ORAU reviewed the survey reports and other supporting B
documentation prepared by Cimarron Corporation for the Mixed Oxide Plant.1 Data and survey results presented in these reports were compared to the established release guidelines.
m Surver Procedures I
During the periods of August 25-31, 1988, and October 12-31, 1989, the Environmental Survey and Site Assessment Program (ESSAP) of ORAU conducted an independent radiological survey of the site. He survey was performed in accordance with a plan, developed by ORAU and submitted to the NRC for NMSS and Region III approval.
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J Background Measurement Six background locations (Figure 3) were selected in the vicinity of the plant during the visit in August 1988. Exposure rate measurements one meter abcm the ground were taken at each location with a pressunzed ionization chamber (PIC). Surface soil samples were taken at each of the six sites and analyzed for uranium 235 and 238, plutonium 238 and 239/240, and I
Oridding The existing ten meter exterior reference grid was extended to include areas outside and adjoining the fence. A one-meter grid was installed on the Doors end lower walls inside the building. 'Ihe I
exterior grid is shown on Figure 4; interior grids are indicated va Figures 5 to 56.
Building surfaces were scanned using gas proportional and ZnS scintillation alpha detectors and thin Nal(TI) (low energy) gamma scintillation detectors. Floors and lower walls received 100%
scans; upper walls, ceilings, and other overhead sarfaces were randomly scanned with efforts concentrated at locations of highest contamination potential and suspect surfe:es, as determined as the survey progressed. Scans of outside soil areas were performed using gamma scintillation detectors; outside paved areas and exterior building surraces at exits were scanned with alpha scintillation detectors. Locations of elevated activity levels were noted for further investigation.
Exposure Rate Measurements Ten exposure rate measurements were made inside the facility with a pressurized ionization chamber (PIC). Exterior exposure-rate measurements were made at each location where a soil sample was taken using a Nal(TI) detector, which had been cross cahtrated with a PIC.
3
Measurement of Surface Activity Measurements of activity on interior building surfaces were performed in randomly selected grid blocks on the Doors and lower walls. Measurements for total alpha and beta-gamma activity were performed systematically at the center and four points midway between the center and corners of 1
the block. Smean for removable activity were performed at the location in each grid block where the highest direct reading was obtained. Single point measurements for total r.mi removable alpha 1
and beta gamma activity were performed on upper walls, ceilings and other overhead surfaces, equipment and at locations identified by surface scans. Surface methity was also measured r* 71 locations on exterior surfaces (Figures 57 to 59).
Where surface activity levels wM B
2 100 dpm/100 cm 03 single-point measurements the area surrounding the measurement was 2
scanned to determine the contamination level when averaged over 1 m.
I Measurement of Radionuclide Activity in Soil
.I Seventy-three surface soil samples were systematically collected at the intersection of the exterior grid lines. Three soil samples were also taken at locations of elevated gamma activity identified by scans (Figure 60). Fifter.n shallow (to about 1.5 m) boreholes were drilled (Figure 61) and 62 samples were collected from these boreholes. Soil samples were collected at outfalls of surface drainage systems (Figure 62).
Miscellaneous Samples Thirty-seven soil samples were taken from sub-Door excavations within the building and from drums of excavated soil stored within the building. Forty samples of paint from walls, thirteen samples of concrete from exterior walls and sidewalks, scrapings of surface material from several exterior surfaces, and three samplu of roof gravel were also collected.
4
s Sampic Analysis and Interpretation Smears were analysed for gross alpha and gross beta activity. Paint and concrete samples were analysed by alpha spectroscopy to determine the concentrations of uranium and plutonium isotopes. Soil and nadi-at samples (interior and exterior) were analysed by gamma spectroscopy
+
for uranium and americium 241. The latter was used as an indicator for further investigation, because it is frequently associated with plutonium. Soil samples were also composited, by room (interior) or area (exterior), and analyzed for plutonium. Exterior surface scrapings were analymed I
by alpha spectroscopy. Gravel samples from the roof of the building were analyzed for uranium and plutonium isotopes. Additional information concerning major instrumentation, sampling I
equipment, and analytical procedures is provided in Appendices A and B.
Results of the independent measurement were compared to the NRC guidelines (Appendix C).
I FINDINGS AND RESULTS Document Review he hentation developed by the licensee was thorough and adequately described in the post decontamination status of the facility. Radiological data demonstrated that the residual activity levels satisfied the established decommissioning guidelines, ladependent harwr Background and Baseline Levels Background exposure rates and baseline soil concentrations from the vicinity of the Mixed Oxide facility are presented in Table 1. Exposure rates ranged from 9 pR/h to 10 pR/h, at 1 m from the surface. Radionuclide concentration ranges were: U 215, <0.1 to <0.2 pCi/g; U 238, <0.3 to 0.9 pCi/g; Pu 238,,
- to
- pCi/g; Pu-239/240, _ to, *_ pCi/g; and Am 241, <0.1 pCi/g. Dese levels are typical of radiation rates and radioactivity concentrations normally occurring in the environment.
(* - To be added later) 5
Budding Interior Survey Surface scans of buikling interior surfaces identified areas of residual activity exceeded guideline levels in 24 rooms. With esception of a wall common to Rooms 110,123,and 124, these areas were small and isolated and the licennae conducted additional decontamination without significant effort. The wall required more extensive attention and the residual contamination was climinated by complete demolition of the wall. Table 2 lists these locations of elevated activity levels and the initial and followup measurement resulta. In each case the further remediation was effective in reducing the levels to within the guideline values.
e Final activity measurements on surfaces are summarized in Table 3.
Total alpha activity 2
2 measurements ranged from <13 to 230 dpm/100 cm ; average 1 m grid block alpha actisity ranged 2
from 13 to 70 dpm/100 cm. Beta-gamma activity levels were not measured at most locations because the nature of the anticipated contaminants was such that the alpha actisity would be the controlling factor and gamma scans did not identify elevated gamma radiation levels. For those 2
locations which were measured, the highest beta gamma activity level was 880 dpm/100 cm with 2
212 dpm/100 cm removable. (The Loading Dock area was considered an exterior surface and is discussed later).
Exposure rates within the facility ranged from 7.5 to 11.6 pR/h; these levels are in good agreement with the range of background gamma exposure rates (9 to 10 gR/h).
2
.R Activity levels in interior paint and concrete samples are presented in Table 4. Ranges of actisity were: U 234,1.3 to 44.4 pCi; U 215, 0.1 to 3.5 pCi; U 238, <.6 to 20.0 pCi; Pu-238, <0.1 to 2.9 pCi; and Pu-239/240, <0.1 to 12.7 pCi. Maximum levels of total uranium and plutonium in a
these samples are 63.8 pCi and 13.6 pCi, respectively.
Radionuclide concentrations in soil samples from subfloor excavations are summarized in Table 5.
U-235 concentrations ranged from 0.1 to <0 5 pCilg, U 238 fwm <0.1 to 1.6 pCi/g, and Am-241 from <0.1 to 10.0 pCi/g. Plutonium 239/240 levels in individual or composited samples ranged 6
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from 0.006 to 2.04 pCUg. Samples from barrels of sou in Room 124 contained U 235 levels of 0.1 pCi/g, U 238 from 0.4 to 0.7 pC1/, and Am 241 from <0.1 to 231 pCi/g (Table 6). The 3
aample with a posithe level of Am 241 was also analyzed for plutonium and found to contain 50.3 pCW of Pu 238 and 458.9 pCi/g of Pu 239/240.
Exterior Survey Gamma scans of the czterior property identl5ed two isolated locations of elevated contact gamma g
B radiation. 'these locations, shown on Figure 60, were loside the escavation made for the purpose of removing piping to the liquid collection tank system. Results of ganima measurements and soil sampling are presented in Table 7. The liaan~* performed further remediation and the followup sampling indicated residual plutonium 238 and phitonium 239/240 activities of 10.4 pCi/g and 99.3 pCi/g, respectively.
Radionuclide concentrations in soil samples from grid intersections and random borehole locations are presented in Table 8. Ranges of concentrations were: U 235,0.1 to 1.5 pCi/g; U 238,0.2 to 7.7 pCi/g; Pu-238, 0.005 to 0.02 pCi/g (composite); and Pu 239/240, 0.005 to 0.09 pCi/g (composite).
I Table 9 summariam the results of measurements and sampling at surface drainage outfalls. Total 2
2 alpha and beta-gamma su. lace activity levels ranged to 60 dpm/100 cm and 1900 dpm/100 cm,
2 respectively; removable alpha and beta activity was a maximum of 3 dpm/100 cm and 8 dpm/100 2
cm, respect vely. Osmma radiation was 8 to 10 gR/h. Samples from the outfall contained U 235 levels from 0.1 to 0.8 pCi/g, U 238 from 1.4 to 5.0 pCi/g, Am 241 from <0.2 to <0.3 pCi/g, Pu-238 from 0.01 to 0.06 pCi/g, and Pu 239/240 from 0.01 to 0.7 pCi/g.
Direct measurements on the budding exterior and other outside surfaces identified areas of elevated total alpha and beta activity. One of these areas was on the loading Dock; this area was remediated and final measurement (see Table 3) indicated total alpha and beta-gamma levels cf 2
2 220 dpm/100 cm and 1100 dpm/100 cm, respectively. Table 10 presents the results of direct 7
a h.
2 measurements at other outside locations. Alpha activity ranged to 6500 dpm/100 cm ; beta gamma 2
2 activity ranged to 3500 dpm/100 cm.' Maximum reumable levels were 58 dpm/100 cm alpha and -
I 2
15 dpm/100 cm beta. -Because the activity was suspected to be windblown uranium from the adjamat; Uranium Plant, several samples of surfaces with elevated direct measurements were 8
analysed for uranium and plutonium content. 'Ibe results, pres ~.ed in Table 11, confirm that the rativity iB Prhinantly uranium.
. Measurements inside the sanitary drain system are presented in Table 12. Maximum total alpha-2 2
~ and beta gamma actMty levels' were 30 dpm/100 cm and 560 dpm/100 cm, respectively.
2 2
' Rem-able activity ranged to 7 dpm/100 cm alpha and 78 dpm/100 cm beta. No elevated gamma levels were noted.
Exposure rates at 1 m above the surface throughout the Mixed Oxide Facility property ranged-from 7 to 11 gR/h.
COMPARISON OF SURVEY RESULTS WITH GUIDELINES I
Appendix C presents thr general NRC surface contaraination guidelines for :elease of formerly licensed' facilities fr r r arestricted use. Plutonium has been identified as the major potential-contaminant on buiv.g iterior surfaces, the guidelines applicable to plutonium are:
- I 2
2 100 alpha dpm/100 cm, averaged over.1 m,,,,
2 2
300 alpha dpm/100 cm, maximum in a 100 cm area 2
200 alpha dpm/100 cm, removable 2
All individual final' measurement were below the 300 dpm/100 cm maximum level and there was 2
no removable activity in escess of 20 dpm/100 cm. Several single measurements were noted to 2
have activity levels between 100 and 300 dpm/100 cm ; however, the surface areas of these 2
locations were small and averaging throughout the contiguous 1 m results in activity levels below 2
the 100 dpm/100 cm guideline.
L8; 8;
8 LB
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Contamination levels on some exterior surfaces M the plutonium guideline levels. Further analyses indicated that the contaminant was predominantly uranium - likely windblown from the' adjacent Uranium Plant. 'Ibe NRC gn*H= for uranium are:
2 2
5,0C0 dpm/100 cm, averaged over 1 m,,,,
2 2
15,000 dpm/100 cm, maximum in a 100 cm,,,,
2 1,000 dpm/100 cm, removable Activity levels on exterior surfaces satis 6ed these gnall-Exposure rates throughout the site were typically in the range of background levels. *1he nighest caposure rate measured at 1 m above the surface was 13 gR/h, which is 3 pR/h above the range I
- (9 to 10 pR/h) in background rates. Exposure rates are therefore well within the guideline value of 10 pR/h above background (see Appendix C).
. Residual soil activity gulttalinas for this site are:
Total uranium 30 pCi/g Total plutonium 25 pCi/g -
Total Americium.241 30 pCi/g One drum of excavated soil (#124 5) contained total plutonium and Am.241 concentrations in enocas of these guideline values; however, samples of residual subGoor soil were well below the guideline levels. Outside the building, one sampic from the piping excavation contained residual total plutonium activity of approximately 110 pCi/g. A nearby sample from that same excavation l
and samples from,10 m grid intersections and random boreholes were well witlh the guideline plutonium'value, thus averaging would result in meeting the guideline. Assuming an activity ratio l
for U 234/U.235 of 21 (typical for low enrichment uranium) a U-235 concen' ration above 1.36 pCi/g would indicate that the total uranium erre~k the 30 pCi/g gedalim Samples from grid locations 20E,212N (2) and 30E,220N (1) contained U.235 concentrations abe 1:n pc:,';
(1.5 pCi/g and 1.3 pCi/g, respectively). Using the activity ratio of 21, the total uranium (U.234, 9
1 37 a
f 5
-h
< U 235, and U-238) in samples from these locations is estimated as:
2 20E, 212N (surface).
37.3 pCi/g (30 45 cm)_
37.6 pCi/g 7
30E, 220N-36.3 pCi/g
- Although these levels are slighdy above the guideline value, other samples from the adjacent areas contain much lower concentrations, and the average levels are therefore==~ t~l to be well within the g= W b L
SUMMARY
At the request of the U.S. Nuclear Regulatory Commission, Region III, Environmental Survey and Site Assessment Program of Oak Ridge Associated Universities conducted an independent
' radiological survey of the Mixed Oxide Facility at the Cimarron Corporation Plant. The survey included. surface alpha, beta gamma, and gamma scans. measurement of direct and removable contamination levels, exposure rate measurements, and determination of radionuclide
=_
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concentrations in soil, concrete, and paint samples.
l Initial measurements identified several areas of residual surface activity mading guideline levels.
'Ihese areas were addressed by the licensee, and resurveys indicated that the additional cleanup
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was effective in meeting the established limits. Based on the results of the confirmatory survey it
-is ORAU's opinion that the decontamination efforts 1 me been successful in satisfying the guideline levels and that the licensee's documentation' adequately. and accurately describes the final' radiological status of the site.
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--n--
. ~ _.
' srC23 i
- .7 -
h.'
~
it i
l E
-,OPEN,
{
-g 13 l
. 12 7
I E
i
~~
,3
/,
8 g
j 7
lt f;
@Z 3
2 MEASUREMENT
[
LOCATIONS 1
A BC D E F G GRID DLOCKS UPPER WALLS g AND CEIUNG I
N H
I
+
'I FEET 0
12 I
METERS E
I FIGURE 52: Vault Roof Cold Chemical Storage Room Floor Plan l
Showing Measurement Locations lt
.ar,--
,,-m e--
a, -,,,
--,n,-.,,
g srca2 G
'I g
e-I l
a I
l I
~
O I
I e== '
e 8
n I
e a
FEET 0
6 I
m METERS I
I
.g m
FIGURE 53: Vault Room Ledge Showing Measurement Locations 63
fm src21 I
I E
h\\
i f
E r y, 7;
I
~
l.VA A
e c
o e
F c
H MEASUREMENT LOCATIONS GRID BLOCKS l
/7/
///
d UPPER WALLS
/L/
L
/?
J L I
T A
FEET o
6 l
2 ueTERs I
I FIGURE 54: HP Corridor Floor Plan Showing I
Measurement Locations I
e4
)
SFC25';-
I 1
l-t I'
,: ~:
i..
m 1
c o
,N
.,,y
'3N U'l
~5 BLED M
^"'^
(
L 2N 1
DOCK 80ARD
.,/
'2 RECESS
/
IN CRANE I
I I
a ON OE 1E 2E~
3E 4E SE
.6E 7E 8E.
9E 10E 11E 12E 13E
., )
MEASUREMENT LOCATIONS
~
CRID OLOCKS i
@ rtoon
'l h
65 h
FEET 0
L 6. METERS I
lE p nz FIGURE 55: Loading Dock Floor Plan Showing D1 Measurement Locations u,
- r,.
i
- l -
< at I.SFC26
'j)p, ;< qf;;ll'
,lz
-i
'5
.~.
.c I
3 I
e r
is k
MEASUREMENT a
LOCAT!ONS 2 GRID BLOOP,S h
1 1
g; FEET-0 3
6 METERS LI>
Fh,URE 56: Loading Dock Dockboard Recess Showing I,
Measurement Locations i
U+ r L -
-g' -
$ isrc754
-a w.
j4p
-,3, 1 (- (
l k
k:
I I
't i.,
[
h 1
INTAKL h
5 u
Uhh h
@b A[
WALL u
- f
[
b
@@8 g
p l(t
~ 6~
M 55 g
w -
lt B
g MEASUREMENT.
l LOCATIONS N
X NOT 'TO SCALE m
st',
s FIGURE 57: Building Exterior (East Side) Showing-Measu're~ ment Locations 1
67
,. S C17c" g
g-G
'890N n
y g u y
I
.e.
x-x 3r.
L280N
,c.
COOUNG g..
270N TOWER x
'l x
EXCAVATION 260N em.t% pf5 Yg x
- I..'
. 250N
.E na n
f p i) @g @
x x
240N b
x PLUTONIUM b 58 d
BUILDING
^230N 5
x
@-o
[]:,
c o
e x
h
~
.220N
- a
-l x
~
210N u
b g
p s -eq 3
e e- --
x
'/ c-- o e g
...o x
Q:.fgV g
q 4,,
x.
. f'*
l
/x y.
. x.
' 'n.
, =. f l'
. '$,Wf/4V///MM/4 x
NOW Sow 40w 30w 20W 10w 0
10E 20E
-30E g
,g g MEASUREMENT g
LOCATIONS g
CEMENT ASPHALT FEET 60 y
x xrENCE 2'O g
uETERS FIGURE 58: Building Exterior Showing Measurement Locations on the l
Building, Walkways and Miscellaneous Surfaces 68
\\t,
\\[SFC74I 1
+c t
c:
x x
x x
N 1
3:
lo ol I
)(
2000 EXCAVATED a
SEWAGE GAL. -
-AREA MGOON.
/
SEPTIC OPEN x
TANK PIPE M.H.
(
~
PLANT ~
0 X
a x
(
J' v
v v
v n-
"f-K
- g. g -g g
.-a.
d_
x_
jc v
x
- o
,H.
4 s
y j
/
i'B ~
-MEASUREMENT LOCATIONS -
X X
x FENCE
~
N.
I i
E I
n NOT TO SCALE i,
t.
. S l 'li:
- E,
+
FIGURE 59: Measurement Locations Along the Sanitory Drain System
- I g,
69
,B
'SFC17
.X X
X X
X X
X X
=
3r J280N 2< -
COOLING 270N TOWER ac x
3 260s
=
- (
. it E
250N EXCAVATION x
x 3C
.240N
)(
U BUILDING n "'
230N x.
x LJ.
lIlli
,4 a
.-- 2 20N
~
l
- e
')C
'210N L
200N f
- (
f, l
h f
y,x y.X
'3
. =.
,= s' u
/
/
.y u
-180N -
3
'60W.
50W
- 40W, 30W 20W.
10W 0
10E 20E 30E g
LOCATIONS OF 1
M ELEVATED CAMMA h.
RADIATION CEMENT ASPHALT FE O
60
" FENCE j
METERS FIGURE 60: Sampling Locations from Areas Identified by Gamma Scans 70
1 l-290N G.
X X
X X
X X
X X
X X
X
,- o
>c ac
'. O 3 e-280N
~O e
ic -
i n
COOUNG 2'70N
- TOWER x
- ' t Jc 260N x
U b'
x mTT1 in N
-250N EXCAVATION ac x.
u 240N O
2 9.
u BUILDING 230N n..
x.
- x LJ1
[].;
s'm u
220N
^
x 1
n O
210N a
s' j
- )ce
/
u 200N 7
}'
ff
=
l u.
/,y?')
g 1
=
}
.E-l.
. X. ').
,X
., X.
'/,x n.
f/
/
//
f/
/
ib au N.
180 6
=
i-
, 60W 50W 40W 30W 20W IOW 0
10E 20E 30E g
-l glBOREHOLE g
LOCATIONS CEMENT ASPHALT FEETL l
X X
X FENCE O
60 0
20 METERS l
FIGURE 61: Locations of Shallow Boreholes for l'
Subsurface Soil Sampling i
71
QSFC17o 290N x
x x
x x
x y
X x
280N
,s I
COOUNG 270N TOWER ac I
,c
- c 260N s =m
- (
250N EXCAVATION 3c I
240N
- (
230N mm.
- (
0
- c
~~
220N l
210N u
L 4.
200N
/g,r
_J' y
7L l
N 180N 60W 50W 40W 30W 20W 10W 0
10E 20E 30E g
m SAMPLING h
I W LOCATIONS
{ CEMENT l
[ ASi3 HALT FEET x FENCE 60 O
l METERS FIGURE 62: Sampling Locations from l
Surface Drainage Outf alls g
,2
W W
W W
G W
W W
W M
M M
M M
M M
M M
M TABLE 1 BACKGROUND RADIA110N IEVELS AND BASEINE RADIONUCLIDE CONCENTRATIONS IN SOIL MIXED OXIDE FACILI1Y CIMARRON CORPORATION PLANT CRESCENT, OKLAHOMA Exposure Rate ( R/h)
Radine= elide Cre:-:amtian foci /n1 at 1 m above Location" ground surface U-235 U-238 Pu-238 Pu-239/240 Am-241 1
10
<0.1 0.7 0.4
<0.1 2
9
<0.1
<03
<0.1 U
3 9
0.1 0.1 0.4 0.5
<0.1 4
10
< 0.2 0.9 0.2
<0.1 5
10 0.1 0.1 0.8 0.7
<0.1 6
10
<0.2
<0.5
<0.1 Range 9-10
< 0.1 - <0.2
<03 - 0.9
<0.1
" Refer to Figure 3.
'Uncertaintie represent the 95% wnfidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been propagtated into these data.
l
w-m
's
- r. v-i e
v
- TABLE 2 '
4r SupetARY OF SURFACE ACTIVITY 9EASUREMENTS AT LOCATIONS ~
' INITIALLY EXCEEDING GUIDELI8sES.
MIXED OKIDE FACILITY CIMARRON CORPORATION PLANT.
- CRESCENT. OKLAHOMA ROIOVA8LE CONT MINATION TOTAL CONTMINATION Initial Alpha {dpm/100 cm )-
Beta-Gemma (dpm/100 cm }
Alpha Range.,Deta Range.
2 2
2 2
(dpe/100 ce ) (dpa/100 cm )
Location Follow-up N.E. Corner Initial 440 610-
<3
<6 ROOM 106
--.a
<3 '
<6 Follow-up 85 E+0.2,0.8,0.1 Initial 1700
<350
<3
<6 ROOM 109 Follow-up 40 ROOM 110 1900 3
<6 B,26.0.8 Initial 890 WALL REMOVED Follow-up N/S CORRIDOR #113 1500 3
8 AND AIRLOCK #115
. Initial
'910 A.20.0.5 FoIlow up
<24
<3
<6 B+.5,14.5,1.1 Initial 1500
<350
'3
'<6 Follow-up
<24
<3
<6 a
B+.5.12,1.7 Initial 2500 3600 117 21
<3
- <6 Follow up
. <24 ROON 116
- Init ial -
.3
<6 E.6 560 FoIIow up 50
_.;, n
^
M M
e em e
mW W~M M
M M
M ~m-W W
m M
r
_ TABLE 2 (Continued)
SLS844RY OF SURFACE ACTIVITY EASUREENTS AT LOCATIONS
- INITIALLY EXCEEDING GUIDELINES -
MIXED OXIDE FACIL11(
CIMARRON CORPORATION PLANT CRESCENT, OKLAHOMA TOTAL CONTAMINATION '
REMOVA8LE CONTM4INATION Initial Alpha (dpm/100 ca )
Beta-Ganna (dom /100 ca ):
' Alpha Range' - Beta Range Z
Z 2
2
- (W100 cm ) ' (don /100 cm )
Location Follow up I
-ROOM 118 C+.2.0,1 Initial' 800
_SIO
<3
<6~
Follow-up
<28
<3
<7 X.0 Initial' Follow-up 130 580
<3
<6 u
P.1 Initial Follow up 110 420
<3
<6 ROOM 120 N.W. Corner Initial.
470 Follow-up 62 ROOM 123 A.6,1
' Initial 530 470 3
<6 Follow-up 90
<350
<3
' <6 -
E,1 Initial
'420 530
<3
<6-5' (6
Follow-up 85 D,6
.Inittal 1500 4500 Door Handle Follow-up HANDLE REMOVED -
I
%i
3c-
.~
... ar J
' TABLE 2 (Continued)
SLM4ARY OF SURFACE ACTIVITY E ASUREMENTS AT LOCATIONS m.
INITIALLY EXCEEDING GUIDELINES MIXED OKIDE FACILITY CIMARRON CorJORATION PLANT CRESCENT,' OKLAHOMA TOTAL CONT MINATION REMOWABLE CONT MINATION Initial Alpha (dom /100 cm )
Beta-Gamune (dpm/100 cm )
Alpha Range Beta Range 2
2 (dpm/200 cm ). (dpm/100 ce?)'
2 Location
~Fo11 W
~.Lj ROOM 123 (Cont'd)
~<3 10 E+.8,9,0.1 Initial 1500
-1200 Follow up 53
<3
<6 E+.8.18&l9.0 Initial 5400 9400 Follow-up WALL RLMOVED ye E+. 8,7. 5,1. 8 Initial 580'
<350 128 17 '
Follow up
<28
<350 3.1
<6 ROOM 124
~-
'~
A,9,1 Initial 2200 3100 Follow-up WALL REMOVED A,18,1 Initial 5800 3200 Follow up WALL REMOVED F+.1.15,1
. Initial 12000 12000 Follow up WALL REMOVED F+.1,10,1 Initial-
-490.
1900
<3
.<6
' Follow-up
<24
<3
<6
W-Q<W
- TABLE'2 (Continued)
Supe #RY OF SURFACE ACTIVITY DEASURDENTS AT LOCATIONS INITIALLY EXCEEDING GUIDELINES NEXED OKIDE FACILITY
~CIMARRON CORPORATION PLANT z
CRESCENT. OKLAHOMA
'REMOYA8tE CONTAMINATION' TOTAL CONTAMINATION -
Initial Alpha (dpm/100 cm )'
Beta-c- (dpe/100 cm )
Alphe Range Beta Range-2 2
.(dpe/100 cm )L. (dom /100 ce?).
2 Location Follow-up ROOM 124 (Cont'd)
F+.1.9.1 Initial 1900 3300 7
<6 Follow-up 76
<3
<6:
F+.1.2.0
-Initfal 370 1100
<3 7
Follow up
<24
<3 14 y
w ROOM 126 A.10 Initial 2700 6400 7
<6 Follow-up 23
<420
<3
<6 ROOM 133 D.6.2.1.1 Inittal Follow-up
<24
<3
<6 l
0+.6.0.1.4
-Initial
<3
<6 Follow-up-68-ROOM 134 A+.8.3.5,1.3
-Initial
<3
<6 Follow-up 85 Inittal 420 1400
. <3 12 ROOM Bol A.0 Follocup 130'
~
tY
Ik ll
_~
G
~
ll$
~
~
TABLE 2 (Continued)>
Supe 4ARY OF $URFACE ACTIVITY pEASJREENTS AT LOCATIONS +
c;
. INITIALLY EXCEEDING GUIDELINES
' MIXED OKIDE FACILITY CIMARRON CORPORATION PLANT-CRESCENT, OKLAHOMA TOTAL CONTAMINATION REMOVASLE CONTAf4INATION-2 2
Inittal'-
Alpha (dpe/100 cm )
, Set 4 dassRa (dpe/100 cm ),
Alpha Range Beta Range 2
2 Location Follow-up
.(dpm/100 cm ) (dpm/100 cm )
ROOM B01 (Cont'd) 7+1,0,1 Initial 560
<350 3'
<6 Follow up 30 G.0 Initial 640 750
<3
' <6 Follow up 120 5
ROOM 802 A.7 Initial 29000 25000 5
<6 Follow-up 50 A.12 Initial 280
<350
<3
<6 -
Follow-up 80 A,6 Inittal 560 440-3
<6 Follow-up 40
<3 9-Ad Inittal 960 1500
<3
<6 Follow-up 40
<3
<6 C,0 Initial 1100 970
<3-
<6 Follow-up 110
TABLE 2 (Continued)
Sup044RY OF SURFACE ACTIVITY 9EASUREMENTS AT LOCATIONS INITIALLY EXCEEDING GUIDELINES MIXED OXIDE FACILITY CIMARRON CORPORATION PLANT CRESCENT, OKLAHOMA TOTAL CONTAMINATION REMOVA8LE CONTAMINATION Init ial Alpha (dpe/100 cm )
Beta-Gamma (dpe/100 cm )
Alpha Range Beta Range 2
2 2
2 Location Follow-up (W100 m ) (W100 m g l
{
ROOM B02 (Cont'd)
C1 Initial 380
<350
<3
<6 FoiIow-up 230 G.7 Inittal 720
<350
<3
<6 Foilow-up 150 H+.2,2,O Initial 1500 2400
<3
<6 Fol1ow-up (28 D,4 Initia1 1700
<350
<3
<6 Follow-up 50 F,5 Initial 1900
<350
<3
<6 Follow-up 190 RM. MECH.
TUNNEL DD,0,1 Initial 1500 640 9
<6 FoiIow-up 34
<3
<6 Y.0,.7 Init ial 490
<350 3
<6 Follow up
<24
<3
<6
7v
'.....e TAetE 2 (ContCnued)
StastARY OF SURFACE ACTIVITY EASUREENTS AT LOCATIONS
-INITIALLY EXCEEDING GUIDELINES._
MIXED OMIDE FACILITY:.
- CIMARRON CORPORATION PLANT CRESCENT, OKLAHOMA TOTAL CONTAMINATION RENDWABLE CONTmINATION 2
2 Initial Alpha (dpm/100 cm )
Beta-Gamma (dpm/100 cm )
. Alpha Range 8 eta Range;
. (dpe/100 ca.7) ' ~ (dpe/100 ce?)
Location follow up RM. MECH.
TUNNEL (Cont'd)
Q,1.8. 5 Initial 740' 610 5'
<6
-- <3
<6 Follow up 93 co 0.1.8. 5 Initfel 1100 (350 5
12 O
Follow-up 68 L.1.8. 4 Inittal 600
<350 C
<6 Follow-up 42
<3 8
K,1.8. 2 Initial 17000 23000 S
<6 Follow up 25
<3
<6 1.1.8. 5 Initial 85C
<350
<3
<6
<3
<6 Follow-up 25 HP CORRIDOR
~
530
<3
<6 G6.8,2.1.1 Initial
.550
<3
<6 Follow-up
<24 ROOM 201 K. 8.2 Initial Follow up.
<21
<3
<6
+
m M
' 3 g
yt nut f
~
i-~
i: -
~
~
~,
. TABLE 2~(Continued) 2
~~
c SupetARY OF SURFACE ACTIVITY EASUREENTS AT LOCATIONS INITIALLY EXCEEDING OUIDELINES MIXED OKIDE FACILITY CI944RPON CORPORATION PLANT CRESCENT, OKLAHOMA TOTAL CONTAMINATION REMOVASLE CONTAMINATION ~
z Z
Initial
. Alpha (dpm/100 ca )
Beta-Gausse (dpe/100 ce )
Alphe Range
. Bete Ray -
2 2
Location Follow-up (dpq/100 cm ) - (dpm/100 cm g ROOM 201 (Cont'd)
H+.5,0.1.8 Inittal Follow-up 42
- <3
-<6 A,7.5 5
Initial Follow-up 74
<3 '
<6 C+.S.11.3 Inittal Follow-up 21
-<3 7
F+.8.10.3 Initial
.3
<6' Follow-up 74 ROOM BIA (83) 8.0.0 Initial
<3
<6 Follow up
<24-S."I" BEAM Initial Foi)ow v 110
<3'
<6 S.*?" BEAM Initial
~-
<3 -
<6 :
Follow-up 25 ii g
, : 7.hV
~;.
.. + ;~
Y u-R
- ~~
~
"~
- 9 (..
r-
~
JTABLE 2 (Continued) '
y-Sup0WtY OF SURFACE ACTIVITY EASUREENTS AT LOCATI0stS l INITIALLY EMCEEDIteG GUIDELINES.
~ - -
MIXED OKIDE FACILITY' CIMARR0ff CORPORATION PLANT.
CRESCENT, OKLAHEMA TOTAL CONTMINATION REMDVASLE CONT mINATION 2
2 Initial Alpha (dps/100 cm )
Beta-Gemme (dpe/100 cm )
. Alpha Range-. Beta Range j.
2 2-
~
Location Follow-up (dpm/100 cm ) (dpm/100 cm )
ROON BIA (83)
(Cont'd)
C,1
'Inittal
<3
<6 -
Follow up
<24 to Initial C,3
<3
<6 Follow-up
<24 B,2 Init tal.-
. Follow-up
-<24
<3
<6-A,1,0.5
. Initial
<3
<6 Follow up
-<24 N."I" BEAM Initial Follow-up 68.
<3
<6 C,5.2,0 Initial Follow-up 25
<3
<6 abash indicates measurement not performed.
~u--- - _ - -
- U U :aW
. TABLE'3
-c- -
St# MARY OF FINAL BUILDING INTERIOR SURFACE ACTIVITY MEASUREMENTS NIXED OKIDE. FACILITY.
~
CIM'JtRON CORPORATION PLANT
~..;.
CRESCENT. OKLAHOMA humber of Number..of-1.
..to or "
Me :
TOTAL CONTAMINATION Measurements or Alpha 'Jpe/100 cm )
Beta-Gamme (dpun/100 cm )
REM M ABLE CONTAMINATION Grid Blocks' 2
2 Grid Blocks Highest P..id Range of Highest Grid Range of Alpha Range Beta Range Exceeding 2
2 Measurements.~(dpm/100 cm ): (dpa/100 cm ) Criteria Location Figure Surveyeda Block Avg.
Measurements Block Avg.
ROOM 100 &
VESTIBULE 5~
Floors and b
15 N/Ac
<24-34 N/A
_ N/A
<3-7
<6-12 0
g Lower Wells Upper Walls b
3
<24 N/A N/A
<3-3
<6 0
to and Ceiling b
6 ROOM 10l Floors and Lower Wa11s 8
N/A
<28-50 N/A N/A
<3-3
<6 0
b Upper Walls N/A-30
'N/A N/A
<3 7-0 b'
and Ceiling g
b ROOM 102 7
Floors and b
8 N/A
<28-90 N/A N/A
-<3
<6 0
Lower Walls Upper Walls and CeiIing I
N/A
<28 N/A!
N/A
<3
<6-0
~
b a-eY
-, -:..m :
w wa lg; :g' 'g M
g g [g\\ ~MT M 31M M
gl M i@: M_
M.
~
TABLE 3 (continued)'---
p.
z SupWAY OFl FINAL' 9UILDING INTERIOR SURFACE ACTIVITY IEASUPEMENTS MIXED OXIDE; FACILITY
~~
CIMARRON CORPORATION PLANT CRESCENT. OKLAHOMA Number of-Number of--
$bs _ - ts or -
TOTAL CONTAMINATION
~
Measurements or Alpha (dom /100 cm ).
9 eta-Gamma (dom /100 cm )
REMOVABLE CONTAMINATION ' Grid Blocks 2
2 Grid Blocks Highest Grid- ~ Range of Highest Grid Range of Alpha Rangs Beta Range. Exceeding--
2 2
Location Figure Surveyede -. Block Avg.'
Measurements Block Avg.
.Mesourements:.(dpe/100 cm )';(dps/100 cm ) Criterie K
ROOM 103 8
+
Floors and b
9 N/A
<24-25 N/A N/A
<3-3
<6 0
Lower Walls Upper Walls 0
and Colling 2
N/A
<24-42 N/A N/A
<3
<6-d b
1 N/A
<24 N/A N/A
<3
<6 0
Sink ROOM 106 9
Floors and b
5 N/A
<28-85 N/A 610
<3-3
<6 -
0 Lower Walls Upper Walls and ceiling i
. N/A 40 '
N/A
-N/A
<3
<6 0
b ROOM 108 10 Floors and Lower Walls 5
28)
<21 -
N/A N/A
<3.
<6-8 0'
Upper Walls
' <6 0,
b 1
N/A 25 N/A' N/A-
.9 and Ceiling ROOM 104 & 107-11 Floors and
~ <3-3.
-<6-7 0'
Lower Walls 16
<18-
<18-32
- N/A..
N/A Upper Walls and ceiling 4
N/A -,
!<21-32, N/A N/A
<3
- <6 '
0 b
' 6-10' O
-N/A-N/A
<3.7 b
3 N/A.
Misc. Surfaces r
m,w
x:.
TABLE 3 (continued)-
I
~
SupemRY 0F. FINAL 8UILDING INTERIOR SURFACE ACTIVITY MEASUREMENTS.
MIXED OXIDE FACILITY-CIMARRON CORPORATION PLANI CRESCENT. OKLAHOMA Number of Museer of Measurements or
-TOTAL CONTAMINATION' Measurements or
.. Alpha-(dom /100 ce )
Beta-Gamune (den /100 ca )'
~ REMOVABLE CONTAMINATION' Grid Blocks 2
z Grid Blocks Highest. Grid Range of Highest Grid Range of
~ Alpha Range Beta Range Exceeding 2
2 (dpe/100 cm )h (dpe/100 cm ) ~ Criteria -
=
Location Figure Surveyed Block Avg.
Measurements.~ Block Avg... Measurements a
ROOM 105 &
AIRLOCK till 12 Floors and Lower Walls 9
23
<18 N/A N/A
<3-3
<6-19 0
Upper Walls
~
and ceiling 3
N/A
<24-42 N/A N/A
<3
<6 0
b Misc. Surfaced 3
N/A
<24-34 N/A N/A
<3
<6-9 0
,u ROOM 109 13 Floors and Lower Walls 5
30 -
<28-70 N/A N/A
<3
' <6-7 0,
Upper Walls f
and Ceiling 1
N/A 51
., N/A N/A S
O-b Floorb 1
N/A 40 N/A N/A NO SMEAR ROOM 110 14 Floors and Lower Walls.
4
<28
- <28-50 N/A N/A'
<3
<6-' 7 -
0-Upper Walls
.6 0
and Ceiling I
N/A
<24 N/A N/A-
<3 b
N g
^
as sus as as ame as aus as ins aus: case: as; as 'as sum, em asi sme mus af
.. TABLE-3 (continued)~
Sup044RY OF FINAL SUILDING INTERIOR SURFACE ACTIVITY EASUREMENTS MIXED OXIDE FACILITY
'CIMARRON CORPORATION PLANT CRESCEKi. OKLAHOMA Number of-Number of Measurements or -
Measurements TOTAL CONTAMINATION or-Alpha (dpm/100 cm )
Beta-Gamma (dom /100 cm )
' REMOVABLE CONTAMINATION Grid Stocks 2
2 Grid 81ocks Highest Grid
. Range of-Highest Grid Range of Alpha Range-Beta Range.
Exceeding-Location Figure Surveyed
- Block Avg.
Measurements 81ock Avg.
Moseurements ~(dpm/100 cm ) (dpm/100 ce?).. Criteria 2
ROOM 112 15 Floors and Lower Wallsb 6
N/A
<24-68 N/A N/A
<3-3
<6 0
Upper Walls om and Ceiling I
N/A.
<24 N/A N/A
<3
<6 0
b ROOM 113/115 16 FJoor and Lower Walls 16
.30
<28-100 N/A N/A
<3
<6-8 0
Upper Walls
' <6 0
and Ceiling 4
N/A
<24 N/A N/A
<3.
b Lower Wall.
3 N/A'
<24
- N/A.
M/A
<3
<6 0
b ROOM 114 17 Floors and b
5 N/A'
<24-25 N/A N/A
<3
' <6-9 '
O-Lower Wa11s Upoor Walls and ceiling 1
N/A
<24 N/A' N/A
<3 '
<6'-
0 b
I w-
-- muusp yv
% yi
- e ;.y
~-
~
~
x IN h.. -
Y. '
~
~
iTABLE 3 (continued)::
, ~,
~
?.
- 6 Supe #RY OF FINAL BUILDING INTER 10R' SURFACE ACTIVITY DEASUREMENTS
~.....
- MIXED OXIDE FACILITY :
-CINARRON CORPORATION PLANf CRESCENT. OKLAHOMA haber of, Number of Measurements or-
- -TOTAL CONTAMINATION
' Measurements or ',
' Alpha (den /100 cm )
Beta-Gamme (dem/100 cm ).
REMOWABLE CONTAMINATION' Grid Stocks..
2 2
Grid Blocks ' Highest Grid
-Range of Highest Grid.
Range of
~ Alpha Range Beta Range ~ Estceeding,
2 2
~
Location Figure Surveyede 51ock Avg.
Measurements Block Avg.
Measurements.(dpe/100 cm ) (dpe/IGO cm ) ' Criteria ROOM 116 18 Floor and
~M/A
'N/A
<3
<6-7 0
Lower Walls 14 32
<21-64 Upper Walls and Ceiling 3
N/A
<24.34 N/A N/*
<3
'<6 0
b Floorb 1
N/A '
50 560
<3
<6 0
y" ROOM 117 19 Floors and b
IB N/A
<24-34 N/A N/A
'3
<6-9 0.
Lower Walls Upper Walls and Ceiling
'2 N/A
<24 N/A
' N/A
<3
<6 0.-
b ROOM 118 20 Floors and Lower Walls 18 61
<21-170 N/A N/A
<3
<6 '
O Upper Walls b
4 N/A
<18-62 N/A '
N/A O - 18
" <6-8 0
and Ceiling Floorb 2
N/A 110- 130 420- 500 f3
<6 0
Lower Wallb g.
afg"
<28 N/A
<3 7
0~
s:.
^
=ki' 4,
TABLE 3 (continced).-
SUMARY OF FINAL BUILDING INTERIOR SURFACE ACTIVITY EASUREMENTS
~
MIXED OXIDE FACILITY
.CIMARRON CORPORATION PLANT-CRESCENT, OKLAHOMA i
~
Number of Number. of
~
Measurements
' TOTAL CONTAMINATION Measurements or-i
~~
2 2
i or Alpha (dpe/100 cm )
Sete-Gamme (dom /100 cm )
' REMOVA8LE CONTMtINATION -
Grid Blocks-p Grid Blocks Highest. Grid Range of Highest Grid
-Range of-Alpha RangeT 8 eta Range-. Exceeding 2
2 Location Figurs Surveyeda Block Avg.
' Measurements Block Avg'.
Measurements (dpm/100 'em ). - (dpe/100 'ce ) Criteria,
~
ROOM 119 21 Floor and I
Lower Walls 2
<13
<13-23 N/A N/A
. <3
<6 0'
Upper Walls and Ceiling 1
N/A 42 N/A N/A-
<3
<6 0
b ROOM 120 21 Floors and Lower Walls 7
24
<13-36 N/A N/A
<3
<6 0
Uoper Walls i
b and Ceiling 1
N/A 21
' N/A
'9/A
<3
~ <6-0 Lower Wallb 1
N/A 62 N/A N/A NO SEAR l
ROOM 121 21 l
s l
Floors and Lower Walls 19 13
<13-41 N/A N/A
<3-3
<6-17 0
Upper Walls b
and Ceiling 3
N/A.
<21-21 N/A N/A
<3
<6 0
Marble Tableb 1
N/A 53
-N/A N/A
<3
'6 0'.
l l
I I
l
.-c r
,,_m.,
.~.,.,,%
6 W
W W U S-il 1 -.g
~
+
~ t TABLE 3 (continued)E -
-. ~
- =7 _
SupetARY OF. FINAL ~ 9UILDING INTERIOR SURFACE ACTIVITY DEASURDENTS -
~~
MIXED OXIDE FACILITY c
CIMARRON CORM) RATION PLANT CRESCENT. OKLAHOMA Shamber of Number of Measurements TOTAL CONTAMINATION Measurements or.
.or Alpha (dom /100 cm )
Beta-Gamune (dem/100 ce )
REMOVABLE CONTAMINATION'-
Grid Blocks-2 2
Grid Blocks Highest Grid Range of Highest Grid Range of
.. Alpha Range
. Beta Range. Exceeding ~
2 2
Location Figure Surveyed"
_ Block Avg.
Measurements Block Avg.
Measurements (dom /100 cm ) '(dpa/100 cm ) Criteria ROOM 121 PIT 22 Floor and Lower Wa11s 8
N/A
<21-53 N/A N/A
<3-3
<6 0
b Upper Walls and ceiling 3
N/A
<21 N/A N/A
<3
<6-0-
co b
Railings 2
N/A
<21 N/A N/A
<3-3
<6
.O b
RGOM 122/123 23 Floors and
~ N/A N/A
. <3 f<6 0-Lower Walla 22 40
<28-60 Upper Walls and Coiling 5
N/A
<18-36 N/A N/A
<3-3
<6' O
b
]
b
'l N/A.
85 N/A.
N/A 5
<6 0
Floor Lower WalI 5'
-N/A'
<28-90 '
N/A N/A
<3-5
<6 0
b ROOM 124 24 b
'6 N/A 30-120 N/A N/A
<3-10
<6-14 0
Duct Openings Floors and Lower Wells 19 56 -
<28-210 (N/A -
. N/A
<3
<6 0;
Upper Walls
~
N/A
'N/A-
~ <3
<6 0
and ceiling 4
N/A'-
36 _ 62 b
3
_ <6-14
[0 Lower Wallb 6
N/A
<24-76 '
N/A
"/A A-
.LL.
., ~ _
W
' TABLE 3 (continued)
SUBO%RY OF FINAL SUILDING INTERIOR SURFACE ACTIVITY MEASUREENTS MIXED OXIDE FACILITY Cle#RRON N TION PLANT CRESCENT, OKLAH0pm u..
Number'of_
Number of Measurements or Measurements TOTAL CONTAMINATION'
' Grid Slocke 2
2 or' Alpha (dom /100 cm g.
.Sota-n - (dpe/100 ce )
REMOVABLE CONTAMINATION Grid Blocks. Highest Grid'-
Range of Highest Grid-Range of Alpha Range Seta Range Exceeding -
2 (dpm/100' cm )' Criteria a
~
2 Location Figure Surveyed Block Avg.
Measurements Block Avg.
Measurements -(dpm/300 ce )
ROOM 125 25 Floor and Lower. Walls 8
29
<18 62 N/A N/A
<3
<6 0
,o Upper Walls
~ N/A
<24-34 M/A N/A
<3
.7
<6-12 0
b and Ceiling 2
~ <24-76 N/A N/A
<3
<6 0
b 3
N/A Staira ROOM 126 26 Floors and Lower Walle 16 37
<18-45 N/A N/A
<3-7
<6-12 0
Upper Walls N/A 36-98 N/A -
N/A
<3
<6 0
b and ceiling 3
Floorb 1-N/A 23
<420
<3
<6-0 ROOM 127 27 Floor and Lower Walls 16 44
<28-120 N/A N/A
<3
<6 0-Upper Walls and Cei1ing 4
N/A.
<21-64, N/A N/A
-<3
~<6 0-b
,..#Wm-m
m, E 'E N
O OO Oa E
E
.E' -N EH E M
E (E :. E EE -
..q.
-1.-
TABLE 3 (contine'sd) ~
^
Sup04ARY OF FINAL BUILDING INTERIOR SURFACE ACTIVITY DEASUREMENTS MIXED OXIDE FACILITY CIMARRQN CORPORATION PLANT CRESCENTJ OKLAHOMA Number of' Number of Measurements or-
~ Measurements TOTAL CONTAMINATION Alpha (dom /100 cM)
Beta-Gamune (dom /100 cm )
REMOVA8LE CONTAf4INATION Grid Stocks 2
or Grid Blocks Highest Grid
' Range of Highest Grid Range of Alpha Range Bets Range Exceeding.
2 2
Location Figure Surveyeda Block Avg.
Measurements 'Bloct Avg.
phesuromonts (dpm/200 cm ) (dpm/100 cm ). Criteria -
ROON 128 28 Floors and Lower Walls 18 41
<13-77 N/A N/A
<3-13
<6-113 0
Upper Walls and ceiling 4
N/A
<21-42 N/A N/A
<3-3
<6 0
b N
Rallin[
1
'N/A' 95 N/A N/A
<3
<6 0
ROON '29 29 Floor eM Lower Walls 21 54
<28-90 N/A N/A
<3-S
<6-16 0
Upper Walls and Ceiling 6
N/A'
<21-74' N/A
. Id/A
<3
<6-0 b
ROOM 130 30 Floor and Lower Walla 4
59
<18-110 N/A N/A
<3
<6
'O Upper Walls and Cefling 2
N/A
<21-21 N/A N/A
<3
<6 0
b ROON 131 31 Floors and Louer Walls S
23
-<18-50 N/A '
N/A_
<3-5
<6 9
0 Upper Waw
~
<3
<6.
.O b
2 N/A'
<21.
N/A-N/A and Ceiling
^^
-~ U
'v W-
^
TABLE 3 (continued)-
~
.[ N '
SupeeWtY OF FI9IAL BUILDING INTERIOR SURFACE ACTIVITY IEASUREDENTS MIXED ONIDE FACILITY CIpeWWl0N CORPORATION PUWei CRESCENT, OKLAH0pm Number of Number of W.asuremente or TOTAL CONTapeINATION Measurements Alphe (dsse/100 ceF) seta-comme (dse/100 ca )
RemovastE contapINnTross Grid stocks Z
or Grid Blocks Highest 9 id Range of Highest Grid Range of Aiphe Range Seta Range Jacee#ing I
2 Location Figure Surveyed
- 81ock Avg.
penseurements. Block Avg.
Desseurements (dyn/100 cm ) (dpa/100 cm ) Cr' fa ROOM 132 32 Floor and Lower Welle 9
41
<18-50 N/A N/A
<3 44 0
Upper Welle and Ceiling 4
M/A
<21 N/A N/A
<3
<6-12 0
b ROOM 133 33 Floor and Lower walls II 42 C3-95 N/A N/A
<3-3
<4-2 O
Upper Wella and Colling 4
M/A
<21-32 N/A 4/A
<3 44 0
b b
2 N/A
<24-68 N/A 11/A
<3 46 0
Lower Wells ROOM 134 34 Floors and Lower Wells 4
<21
<21-53 N/A N/A
<3
<6 9
Upper Wells and Celling 2
pfA
<21 N/A N/A
<3
<6-14
'O b
b 1
N/A 85 N/A N/A
<3
<6
)
Lower Walls ROOM 135 35 Floor and Lower Walls 6
41
<18-59 N/A N/A
<3
<6
'O Upper Wells and Ceilingb
'2 N/A
<21- '21 N/A N/A
<3
<6 0
mameeemW e
eeememWW mf TA8LE 3 (continued)
SunY OF FINAL BUILDING INTERIOR SURFACE ACTIVITY DEASURE9ENTS stIMED OMIDE FACILITY CIMARON CORPORATION PLANT
~
CRESCENT, OKLAHOM L;
Number of Nunder of Measurements TOTAL CONTAf8INATION peresurements or-a or Alpha (dpe/100 can )
Beta-Gamune (W100 cob RENOVA 8tE CONTAptINATION Grid Blocks z
Grid Blocks Highest Grid Range of.
Highest Grid Range of Alpha Range dote Range Exceeding 2
2 j
Location Figure Surveyed
- 81ock Avg.
90eesurements Block Avg.
pleasurements (dgum/100 cm ) (dym/10) cm ) Criteria
-l ROG4 136 36 Floor and Lower Welle 4
21
<21-64 N/A N/A
<3-3
<6 0
Upper Wells b
l and Ceiling 2
N/A
<21-21 N/A N/A
<3-3
<6 0
i ROOM 137 37 i
Floors and Lower Welle 4
32
<21-64 N/A N/A
<3-3
<6 0
Upper Walls b
and Ceiling 2
N/A 51 N/A N/A
<3
<6 0
i ROOM 138 38 i
Floor and Lower Walle 6
<71
<i'l-42 500
<370 " 700
<2 - 8
<5 - 10 0
l 4
Upper Walls b
j and Ceiling 5
N/A
~ <21-53 N/A -
<370 - 820
<2 - 4
<S O
ROOM 139 39 i
Floor and Lower Walls 4
30
<21-74 480
<370 - 790
<2-5
<S 0
1 t*pper Wei1o b
and Ceiling 5
N/A
<21-32 N/A
<370 - 790
<2
<5 - 12 0
m.
-... 1..
2
.. - -...... - ~
- ~~..
-~-. a
1 U&
S S' &
S S
S O
O^S Wl O
&S
. TABLE 3 (continued) 2 Sup0 WtY OF FIISAL BUILDING INTERIOR SU9 FACE ACTIVITY MEASUPEMENTS
-MIMED OXIDE FACILITY CIpWWt(BI CORPORATION PLANT CRESCENT OKLAHopet Number of s'h of Measuremente TOTAL CONTAceINATION steasuremente or 2
2 or Alpha (dom /100 cm )
- Beta-Gamme (dem/100 cm )
REMOVA8tE CONTApfetATION 3 rid Blocks -
Grid Blocks Highest Grid Range of.
Highest Grid Range of Alpna Range Beta Pange Exceeding 2
I Location Figure Surveyed
- Block Avg.
steasurements Block Avg.
90eecurements (dpm/100 cm ) (dpm/100 cm ) Criteria j
ROOM 140 40 Floors and Lower Wells 11 42
<21 - 95 600
<370 - 800
<2
<5 - 11 0
l Upper Wells.
- Celling, b
and Equipment 8
N/A
<21 - 74 N/A
<370 - Ab'J
<2 - 5
<5 - 10 0
e*
ROOM 141 41&42 Floor and Lower Walls 8
46 (20 - 60
<430
<430 - 600
<2
<5 0
Upper Walle b
and Ceiling 5
k/A
<21 N/A
<370 - 520
<2 - 7
<5 0
l Air Exhaust b
l Vent 4
M/A
<20 - 50 N/A
<430 42
<5 0
i ROOM 142 43 F'oor and Lower Walls 8
36
<18-68 N/A N/A
<3-3
<6 0
Upper Walls b
and Celling 2
N/A
<24-25 N/A N/A
<3
<6 0
ROOM 143 44
{
I Floors and l
Lower Wells 16
<21
<21 - 53 550
<370 - 820
<2-5
<5 - 12 0
i Upper Walls f
and Ceiling
'10 N/A
<21 N/A
<370 - 640
<2 - 7
<5 0
b i
.s
M-@
.M S
E S
UE E
E E
N E
b CL.
O N
O~
~
TA8LE 3 (continued)
SUtemRY OF FIhAL BUILDING INTERIOR SURFACE ACTIVITY OEASUREPENTS MIXED OXIDE FACILITY CItuRRON CORPORATION PLANT CRESCENT. OKLAH00m Number of haber of Mesouremente TOTAL CONTAMINATION Measurements or Alpha (dpe/100 cM)
Seta-Gamma (dpgf100 cm )
MORE CONTMINTION Grid SMs 2
or Grid Blocks Highest Grid Range of-Fighest Grid Range of Alpha Range Seta Range Exceeding Location Figure Surveyeda Block Avg.
Steasurements Block Avg.
acecourements (dyn/100 cm ) (den /100 co-.
Criteria 2
i ROON 136/143 45 CORRIDOR i
Floor and Lower Wellsb 10 N/A
<24 -102 N/A N/A
<3 - 7
<6 - 212 0
Upper Walls b
and Colling 2
h/A
<24 - 25 N/A N/A
<3 - 3
<6 0
4 ROON 201 46 Floor and Lower Walls 29 44
<21-140 N/A N/A
<3-12 46 -
7 0
i Upper Wells f
and Celling 5
N/A
<21-120 N/A N/A
<3
<6 0
b Lower Wallek 3
N/A
<21-74 N/A N/A
<3
<6 0
L Equipmenth 2
. N/A 21-74 N/A N/A
<3 46 - 7 0
j ROON 202 47 i
Floor and Lower Wallsb 23 N/A
~<28 -110 N/A N/A
<3 - 9
<6 - 69 0
Upper Walls b
and Celling 8
N/A
<28 - 40 N/A N/A
<3 - 3
<4 -
7 0
Ecr----.b 8
N/A
<28 - 60 N/A
. M/A
<3 -
3-
<6 -
9 0
y
=
,**,,-e.-
e mp.--....y--
--w-v,,..g r
e
=-
y cww.-
,w es%-. - +. + -
am
,._+
ma.
w..1aue-m
.. --m-
M W 'M Se W
W W
W
-mW W
W m' W _m W W
W D
TASLE 3 (continued) l l
t SUIONRY OF FINAL SUILDING INTERIOR SURFACE ACTIVITY MEASUREMENTS --
MIMED OKIDE FACILITY CIMAMON CORPORATION PLANT CRESCENT. OKLAHOMA Number of Number of Measurements TOTAL CONTMINATION Measurements or 2
2 or Alpha (dpm/100 cm )
Seteh (dpe/IOO cm )
RENDWASLE CONTMINATION Grid Blocks Grid Blocks Highest Grid-Range of Highest Grid Range of Alpha Range Seta Range Exceeding 2
I Location Figure Surveyede Block Avg.
Measurements Block Avg.
80eesurements (dpm/100 cm ) (dym/100 cm ) Criterie ROOM 81A (83) 48 Floors and Lower Wells 5
38
<29 - 80 N/A N/A
<3
<6 -
7 0
UpperWalid 2
N/A 95 -230 TA N/A
<3 46 0
Floorb 3
N/A
<24
.4/A N/A 3
'<6 0
b Lower Walls -
3 N/A
<24 - 25 N/A N/A
<3
<6 0
b "I" Beams 3
N/A 25 -110 N/A N/A
<3
<6 0
j ROOM 901 49 l
Floors and l
Lower Wells 13 60
<28 -100 N/A N/A
<3 46 0
i Upper Walls l
i and Ceiling 3
N/A 36 -125 N/A N/A
<3 - 3
<6 0
b Floorb 2
N/A 120 -130 N/A N/A NO SEAR
-0 Lower Walls 1
N/A 30 N/A N/A NO SMEAR 0~
I b
I ROON 802 50
-[
i Floors and Lower Walls 25 70 _
<21 -140 N/A N/A
<3 - 5
<6 -
9-0 Upper Walls
[
b eed Ceiling 4
N/A
<21 - 85 N/A N/A
<3 - 3
<6 0
Floorb 8
N/A 40
-230-N/A N/A MO SMEM -
0 D
'2 N/A.
<28 - 40 N/A N/A NO SEM
'O Lower Walls f
L i
1
,m.
~ -..
... _, ~ - -... _ - -.... _ _ _ - - _.... -. _. - _ _ _ _ _. -.... _ -.. _ _
- Y O
U.
M M' &
TABLE 3 (continued)
SupgMRY OF FINAL BUILDING INTERIOR SURFACE ACTIVITY MEASUREDENTS MIXED OKIDE FACILITY
..M8W40N CORPORATION PLANT '
CRESCENT, OKLAH0pm Number of Number of l
Measurements TOTAL CONTAMINATION Meeewremente or 2
2 or Alpha (dpat/100 cm ) _
8 eta-e- (dem/100 ce )
REMOWA8tE CONTAMINATION Grid Stocks Grid Blocks Hitest Grid Range of Highest Grid Range of' Alphe Range Sete Range Escoeding 2
2 (dpm/100 cm ) ^(dym/100 cm ). Criteria Location Figure Surveyed
- B1ock Avg.
Measurements Block Avg.
Meeeuremente TUNNEL 51 Floors and Lower Walls 22 44
<28 - 140 N/A N/A
<3 - 3
<6 - 7 0
Upper Wils b
and Ceiling 5
N/A
<21 - 32 N/A N/A
<3
<6 - 9 0
b Pipe Protrusione 7
N/A
<24 - 93 N/A N/A
<3
-3
<6 - 8 0
VAULT ROOF AND 52653 LEDGE Floors and Lower Wells 13 -
54 -
<18 - 152 N/A N/A
<3 - 12
<6 - 13 0
Upper Walls b
and ceiling 2
N/A
<2A - 34 N/A N/A
<3 - 3
<6 - 7 0
Ledgeb 10 N/A
<18 - 107 N/A N/A
<3 - 3
<$ - 13 0
HP CORRIDOR 54 i
Floors and Lower Walla 7
32
<18 - 95 N/A N/A 43
<6 - 8 0
Upper Wells b
and Ceiling 2.
N/A
<24 - 34 N/A N/A
<3
<6 0
LowerWalld-1 N/A
<24 N/A ~
N/A
<3
<6 0
i LOADING DOCK 55 l
l Floor 11 61
<21 - 220 710
<370 - 1.100
<2
At Grid Range of Alphe Range Sete Range Exceeding 2
2 Location Figure Surveyed
- Block Avg.
Measurements B'wx:k Avg.
Moeourements (dpm/100 cm ) (dpe/100 cm ) Criterie DOCK BOARD 56 RECESS Floore 1
30 30 560 560
<2
<5 0
oo Wello 3
<21
<21 510
<370 - 1.000
<2
<5 - IC 0
GUIDELINE N/A 100 300 N/A N/A 20
. M/A Includes follomup measuremonte a5 ingle point measurements taken on upper wells and ceilings unless otherwise indicated.
described in Table 2.
bSingle point measurements only, no grid block everage wee determined.
P, N/A - Indicates not applicable.
C h
'M M~M W
U U)
TABLE 4.
~
~_
RADIONUCLIDE LEVELS IN INTERIOR' PAINT ARE) CONCRETE SAIN'LES NIXED OKIDE FACILITT
~
CINARROW CORPORATION CRESCENT, ORLANONA Sampling Sample Radionuclide Content (pCl) a Locatfon Type U-234 U-235 U-238 Pu-238-Pu-239/240 Room 100 P
10.8 1 1.8 0.4 1 0.5 5.1 1 1.3
<0.1 1.3 1 0.5 b
Room 101 P
5.0 1 1.1 0.3 1 0.4 1.5 1 0.9 0.5 1 0.1 0.1 1 0.1 Room 102 P
7.1 i 1.3 0.9 i 0.8 3.8 1 0.9 0.2 1 0.2 0.1 1 0.2 Room 103 P
4.3 i 0.8 0.4 1 0.2 2.8 1 0.5
<0.1
<0.1 e*
Room 104 P
3.1 1 1.0 0.1 i O.1 1.9 1 0.9 0.9 1 0.3 4.8 1 0.6 Room 105 P
2.1 1 1.0 0.1 1 0.5 2.2 1 0.9
<0.1 0.1 1 0.2 Room 106 P
2.6 1 1.0 0.1 1 0.6 2.9 1 1.0 1.7 1 0.6 0.1 1 0.1 Room 107 P
7.1 1 1.3 0.3 1 0.4 2.9 i 0.7 0.9 1 0.4 12.7 1 1.4 Room 108 P
3.4 1 0.9 0.4 i 1.0 3.9 1 1.0
<0.1 0.3 1 0.3 Room 109 P
2.0 1 0.8 0.2 1 0.3 2.2 1 0.8
<0.1
<0.1 Room 110 P
2.8 i 0.9 0.1 1 0.2 2.4 1 0.8
<0.1 0.5 1 0.3 Room 111 P
4.2 1 1.0 0.3 1 0.4 3.2 1 0.8
- <0.3 0.3 i O.6' Room 112 P
4.4 1 0.8 0.2 1 0.3 1.8 1 0.5
<0.1-0.3 1 0.2 Room 113 P
3.3 1 0.9 0.3 1 0.6 3.1 1 0.7
<0.3-0.3 1 0.3 Room 114 P
4.4 1 1.0 0.3 1 0.4 3.4.; d.9
<0.1 5.9 1 1.3
3: W W
W ~m W
W W
W.M~W'M.M.M M' W W
6 6 TABLE 4 (Continued)
RADIONUCLIDE LEVELS IN INTERIOR PAINT AND CONCRETE SAMPLES NIXED DXIDE FACILITY i
CIMARRON CORPORATION-CRESCENT, OKLANOMA i
a i
Sampling Sample Radionuclide Content (pCI) l Location Type.
U-234 U-235 U-238 Pu-238 Pu-239/240 T
Room 115 P
5.4 1 1.6 0.9 i O.7 3.4 1 1.1 2.9 1 0.9 2.2 1 0.7 Room 116 C
6.6 1 1.1 0.1 1 0.3 6.5 i 1.0
<0.1
<0.1 b
l Room 117 P
5.1 1 0.7 0.2 1 0.2 2.2 1 0.5 0.1 1 0.2 0.1 1 0.2 l
Room 118 P
4.1 1 1.1 0.3 1 0.5 3.9 1 1.1
<0.2 2.5 1 0.8 i
"o i
O Room 119 P
4.0 1 0.9 0.3 1 0.4 3.1 1 0.8 0.4 1 0.4 3.8 i 1.1 Room 120 P
6.2 1 1.3 0.6 1 0.6 3.7 1 1. 0
<0. '1
<0.1 i
Room 121 P
2.2 1 0.6 0.2 i O.3 -
1.6 1 0.5 0.3 1 0.3 2.1 1 0.5 i
Room 122 P
4.9 1 1.1 0.3 1 0.4 2.2 1 0.7 0.2 1 0.3 0.2 1 0.2 Room 123 P
5.0 1 2.6 0.2 i 1.0 3.8 1 2.2
<0.2 0.5 1 0.5 i
Room 124 C
4.5 i O.8 0.3 1 0.3 4.8 i 0.8
<0.1 0.2 1 0.2 j
Room 125 P
6.3 1 1.4 0.5 1 0.5 5.5 1 1.2 0.9 i 0.5 6.5 i 1.2 i
l
- Room 126 C
1.3 1 0.4 0.1 1 0.1 1.7 i O.4
<0.1 0.1 1 0.1, k
Room 127 C
20.3 i 3.0 0.8 1 0.8 20.0 1 3.0 1.1 1 1.4 0.5 i 1.6 Room 128 C.
17.7 i 2.7 1.0'i 0.7 16.7 1 2.7'
'O2102 1.5 i O.7 Room 129 P
1.4 1 0.7 0.1 1 0.4 1.2 1 0.6'
. <0.1
<0.1-
,,.4 y
,....,m..u----
ry.-
,m w.~,+-
-+-*.u.n>we+,.m a-7*
w e'---
'w+-
rur-+-'
,w,-We--*4--=-%e---
m
--m----
^i-*
~.
I TABLE 4 (Contimmed)-
RADIONOCLIDE LEVELS IN INTERIOR PAINT.
AND CONCRETE SAMPLES NIXED OKIDE FACILITT CINARRON CORN 0 RATION' CRESCENT. OKLANOMA Sampling Sample Radionuclide Content (pCI) a Location Type U-234 U-235 U-238 Pu-238 Pu-239/240 Room 130 P
1.8 i 0.6 0.1 1 0.4 1.6 1 0.6
<0.1 0.3 1 0.2 Room 131 P
5.6 i 1.4 0.4 1 0.5 4.4 1 1.1
-C i
l Room 132 P
3.5 1 0.9 0.1 1 0.3 2.8 i 0.5 0.1 i O.2 0.1 1 0.1 t
g Room 133 P
2.7 i 0.7
~0.3 1 0.3 1.3 1 0.5 0.1 1 0.2 0.2 1 0.2
(
Room 134 P
7.8 1 1.5 0.2 1 0.4 3.2 1 0.9 0.2 1 0.4 0.6 1 0.6 i
Room 135 P
55.5 1 4.1 3.5 i 1.3-4.8 i 1.3 0.2 1 0.4 0.9 i G.6 l
i j
Room 136 P
1.8 i O.4 0.1 1 0.2 1.3 1 0.3 0.1 1 0.1 0.1 1 0.1 x
Room 137 P
2.3 i O.6 0.2 1 0.2 1.5 1 0.4
<0.1
<0.1 I
Room 140 P
3.0 1 0.9 0.3 1 0.3 2.2 1 0.7 0.1 1 0.3 0.3 i O.3 I
Room 142 P
3.0 i 1.0 0.3 1 0.4 2.5 1 0.8 0.1 1 0.2 0.2 1 0.2 l
HP Corridor P
5.8 1 1.2 0.3 i O.4 1.6 i O.7
<0.1
<0.1
.i Hal1 Between P
138/1's 2.7-i 1. 0 0.1 1 0.3 1.3 i O.7 0.1 i O.2
<0.1 Room B01 C
3.6 1 0.8 0.1 1 0.3 3.1 1 0.7 0.1 1 0.2 0.3 1 0.2 Room BIA C
0.9 1 0.2 0.1 1 0.1 0.6 i O.2 0.1 1 0.1 0.2 1 0.1
.y
U TABLE 4 (Cont 1Daed)_
~
RADIONUCLIDE LEVELS IN INTERIOR PAINT AND CONCRETE SAMPLES MIKED OXIDE FACILITY.
CINARRON CORPORATION CRESCENT, OKLANONA Radionuclide Content (sci) a Sampling Sample Pu-239/240 Location Type U-234 U-235 U-238 Pu-2,38 Room B02 C
2.4 i G.6 0.2 1 0.2 2.4 1 0.8 0.2 1 0.2 0.2 1 0.2 Nechanical C
1.8 i 0.4 0.1 1 0.1 1.7 i O.4 0.1.1 0.1 0.1 1 0.1 Tunnel Vault Roof C
1.9 i 0.5 0.2 i'O.2 1.9 1 0.5 0.2 1 0.1 0.2 1 0.1 Room 201 C
8.3 1 1.3 0.3 1 0.3 10.4 i 1.4 0.1 1 0.3 0.1 1 0.3 Room 202 P
3.8 1 0.4 0.1 1 0.1 1.4 1 0.3 0.1 1 0.1 0.2 1 0.1 aP: Paint, C: Concrete,,
Uncertainties represent the 95% confidence levels, based only on comating statistics; b
additional laboratory uncertainties of i 6 to 104 have not been propagated into these data.
cDash Indicates analysis not performed.
O r
'e=m-
u en a t
n TAEEE 5 RADIONUCLIDE CONCENTRA110NS IN SOIL SAMPIES FROM EXCAVATBONS INSIDE THE BUILDING MIXED OXIDE FACIERY CIMARRON CORFORA110N CRESCENT, OKIAHOMA R=di<wtenida Cancentratinn (oCi/mi In:ation U-735 U-238 Pu-239/240 Am-241 Composite" Pu-239/240 Rm 106 0.2 0.1*
0.9 0.8 23 03 N/A Rm 114 0.1 0.1 1.6 0.9 10.0 0.1 N/A 5
Rm 104 0.1 0.1 0.7 0.5 (0.7 2.5) E-2
<0.2 N/A Rm 124
<0.4 0.7 0.5 N/A
<0.1 (15.8 5.2) E-2 Rm 124 0.1 0.1 0.4 0.5 2.04 0.27 0.8 0.2 N/A Rm BOIA 0.1 0.1 1.4 0.7 (5.8 4.9) E-2
<0.2 N/A Rm B01
<0.4 1.5 1.1 (7.1 5.6) E-2
<0.2 (8.8 6.8) E-2 Rm 136
<0.4
<0.9
<0.2 N/A Rm 138 0.2 0.1 1.5 0.8 (0.6 2.0) E-2
<0.2 N/A Rm 136 0.1 0.1 1.0 0.6
<0.2 N/A Rm 135 0.1 0.1 1.2 0.8 N/A
<0.2 (4.5 4.6) E-2
W W
W W
M' M
M: M M
W m M
M M
W W
W
. TABIE 5 (Cent'd) '
RADIONUCIJDE CONCEMA110NS IN SOIL SAMPI25 I
FROM EXCAVA110NS INSIDE 11EE BUIIBING MIXED OKJDE FACIIEIY CIMARRON CORFORA110N 1
CRFSCENT, OKIAHOMA
}
p m -- : ' Cnare=* ration foCWr)
Location U-235 U-238 Pu-239/240 Am-241 Camponis#
Pu-239/240 l
Rm 135 0.1 0.1
<0.9 N/A
< 0.1
.N/A
)
l Rm 132 0.1 0.1 0.4 0.6 N/A
<0.2 (9.9 6.2) E-2 Rm 132 0.1 0.1 1.1 0.7 N/A
<0.2 N/A l
2 l
Rm 132 0.4 0.3 0.5 0.5 N/A
<0.1 N/A
.j Rm 132 0.1 0.1 0.5 0.4 N/A
<0.2 N/A-1 Rm 132
< 0.4
<0.9 N/A-
<0.1 N/A i
Rm 140 0.1 0.1 0.2 0.2 N/A
<0.1 (8.416.6) E-2 N/A i
Rm 140 0.1 0.1 0.9 0.9 N/A
<0.1 Rm 140
<0.5 0.6 0.7 N/A
<0.2 N/A
(
i Rm 140 0.1 0.1 0.9 0.7 N/A
<0.2 N/A i
i i
Rm 140 0.1 0.1
.<1.0 N/A
< 0.2 N/A-
]
i
}
l I
I
m-m m :m _ m.
m m
m em.
mm m
M M
M TABIE 5 (Cent'd) -
RADIONUCIJDE 00NCENTRA110NS IN SOIL SAMPIRS FROM EXCAVA110NS INSIDE 11EE BUILDING MIKED OKIDE FACIIEIY CIMARRON CORFORA110N CRESCENT, OKLAHOMA i
pa
.e+ C% tion (oCiM i
Location U-235 U-238 Pu-239/240 Ann-241 Connicasi#
Pu-239/240 i
l Rm 140 0.1 0.0 0.8 0.7 N/A
<0.2 N/A i
Rm 129 0.1 0.1
<0.9 N/A
<0.2 (7.9 2 5.5) E-2 Rm 129 0.0 0.0 1.1 0.7 N/A
<0.1 N/A 8
I Rm 129
<0.4 0.5 0.5 N/A
<0.1 N/A-l Rm 129 0.1 0.1 0.4 0.5 N/A
<0.1 N/A 1
i I
Rm 129
<0.5 0.6 0.5 N/A
< 0.2 N/A i
i Rm 129
<0.5
- 1.0 0.8 N/A
<0.2 N/A 4
l Rm 129 0.0 0.0
<0.9 N/A
<0.1 N/A i,
i Rm 124 0.0 0.1 0.4 0.6 N/A
< 0.1 N/A i
" Samples from the Room were um;pordied for analysis..
- Dash indicates analysis not performed.
' Uncertainties represent the 95% confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these data.-
f
.l
~l 4-1 LU' u
TABER 6 RADIONUCtJDE CONCENTRA110NS IN SAMPIRS FROM BARRNI 4 OF EXCAVA1ED SOEL MIXED OXIDE FACHEIY CIMARRON CORPORAlbN CRESCENT, OKIAHOMA p a.4 ne ceh (nci/m)
A m-241-Pu-238 Pe-239/240 Barrel #124-1 0.1 0.1" 0.7 0.6
<0.2 5
Barrel #124-2 0.1 0.1 0.7 1.3
<0.2 Barrel #124-3 0.1 0.1 0.7 0.5
<0.2 Barrel #124-4 0.1 0.1 0.4 0.6
<0.1 Barrel #124-5 0.1 0.1 0.9 0.9 231 1.6 50.321.3 458.923.9
- Uncertainties represent the 95% confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these data.
- Dash indicates analyses not performed.
...i2---,
a:---r a
tiisi il.i iii imii e.-%-
W W
W W
W W
W W
W W
W W
.A TABIE 7
SUMMARY
OF LOCA110NS OF E1EVATED GAMMA EXFOSURE RATES I
MIXED OXIDE FACIIXIY CIMARRON CORPORA 110N FIANT CRESCENT, OKIAHOMA j
EXPOSURE RATE 1 meter contact Radionuclide Cetion (oCi/mi Imcation" pR/h '
R/h U-235 U-238 Pu-238 Pu-239/240 Am-241 f
r 6
1 PRE DECON 12 32 243.8 3.9 1404 13
<2.0 i
5
?
~
j-PRE DECON 12 32 241.6 3.8 1260 1 12
<2.2 POST DECON 12 18 0.4 0.4 4.1 0.7 10.4 10.4
- 99.3 1.4
<0.2 i
l I
l 2
'13 12 0.3 0.2 2.3 1.0 0.01 0.03 0.15 0.08 h
l 4
I t
i r
" Refer to Figure 60.
- Uncertainties represent the 95% confidence levels, hased only on counting statistics; additional laboratory uncertainties i
of 6 to 10% have not been p.cpegeted into these data.
l
' Dash indicates analysis not performed.
1 3
e,
,-ew-.
q e -, u w-rw -~
.:rs
<-ww eav
..e.
,<oe,
.,,e-r__,om,'
4-m
,-s,,m,m.e-~m-,.me
M M
1_
fIl 11 }
.l_
T v.E8 URAMIUM AND PLUT0NItM ODICENTRATIONS 181 SOIL SAprLES 9t!MED OKIDE FACILITY.
C18 terr 0pt CORPORATION CRESCENT OKLAN0pm PlutoniustConcentratlone (pCi/g)
Sampiing*
Depth Urenium Concentretions (pCi/g)
Pu-238 Ptt-239/240 location (cm)
-U-235
.U-238 60W. ISON Surface 0.2 1 0.2 2.1 1 1.3 Composite 11 (0.6 1 2.0) E-2 (0.612.6) E-2 b
15-30 0.3 1 0.1 1.6 1 0.9 30- 45 0.2 1 0.1 1.9 1 1.3
^
- 45-60 0.2 1 0.1 2.4 1 1.1 60- 75 0.1 1 0.1 1.2 1 1.1 75-100 0.3 1 0.1 1.5 i 1.1 60W. 190N Surface 0.2 1 0.1 2.1 1 1.0
~
60W. 200N Surface 0.3 1 0.1 1.9 1 1.2 60W. 210N Surface 0.2 1 0.1 0.9 i 1.3 60W. 220N Surface 0.2 1 0.1 1.9 1 1.1 60W. 230N Surface 0.2 1 0.1 1.9 i 1.2 60W. 240N Surface 0.2 1 0.1 1.011.0 60W. 250N Surface 0.4 1 0.4 2.2 1 1.0 60W. 260N Surface 0.2 1 0.1 1.9 1 1.1 60W. 280N Surface 0.2 1 0.1 2.8 1 1.5 60W. 290N Surface 0.210.1-
<1.6 50W, 180N Surface 0.2 1 0.1 1.5 i 1.1 Composite 9 (0.5 i 1.8) E-2 (0.5 1 1.8) E-2 50W. 190N Surface 0.1 1 0.1
<1.4 50W, 200N Surface 0.2 i O.1 1.1 1 0.9 Composite 6 (0.7 1 2.9) E-2 (0.7 1 2.9) E-2 50W. 210N Surface 0.2 1 0.1 1.3 1 0.9 50W. 220N Surface 0.2 i 0.1 0.7 i 0.9 50W. 230N Surface 0.2 1 0.1 1.7 1 1.2 Composite 5 (1.2 1 2.9) E-2 (1.2 1 2.9) E-2 50W. 240N Surface 0.1 1 0.1 2.2 1 0.9 50W. 250N Surface 0.2 i 0.1 1.110.6-50W. 260N Surface 0.2 1 0.1 1.5 1 0.9 50W. 270N Surface 0.1 1 0.1 2.8 1 1.2 Composite 1 (1.5 i 3.4) E-2 (9.0 1 6.2) E-2 50W. 280N Surface' O.1 1 0.1 1.2 i O.9
M M
M M
M M
M M
M M
M M
M M
eemW W~
W i:
TABLE 8 (Cont'd)
IMANIISE AfG PLUTONIts CasCENTRATIONS IN SOIL SMPLES 9tI) LED OKIDE FACILITY ClaufW10N CORPORATION CftE3 CENT. OKLAH0pm 4
f a
Sans: ling Death Uranium Concentretions (pCi/g)
Flutonie Concentretions (sci /s)
Location (ce)
U-235 U-238 Pu-238 Pu-239/240 i
48W, 193N Surface 0.2 i u.1 1.5 i 1.1 ra-rmite 11 (0.6 1 2.0) E-2 (0.612.6) E-2 15-30 0.3 1 0.3 0.8 1 0.8 30-45 0.3 1 0.1 2.711.1 45-60 0.1 1 0.1 0.8 1 0.8 60-75 0.1 0.1 1.9 i 1.0 75-90 0.1 1 0.1 1.1 1 1.1 yo*
45W. 280N Surface 0.1 1 0.1 1.4 1 1.1 Composite 11 (0.6 1 2.0) E-2 (0.6 1 2.6) E-2 15-30 0.2 1 0.1 1.0 1 0.9 30- 45 0.1 i 0.1 0.9 1 1.0 45-60 0.1 1 0.1 1.9 1 0.6 i
60- 75 0.2 i 0.1 1.6 1 0.9 75-90 0.1 1 0.1 1.2 1 1.0 40W. 180N Surface 0.2 1 0.1 0.8 1 1.0 Composite 9 (0.5 1 1.8) E-2 (0.5 1 1.8) E-2 40W. 190N Surface 0.2 1 0.1 1.3 1 0.3 40W. 200N Surface 0.2 1 0.1 1.6 1 1.0 ra=rasite 6 (0.7 1 2.9) E-2 (0.7 1 2.9) E-2 i
40W. 210N Surface 0.2 i O.4 0.8 1 0.7 40W. 220N Surface 0.1 1 0.1 2.0 i 1.0 C
Surface 0.2 1 0.1 1.7 1 0.9 Composite 5 (1.2 1 2.9) E-2 (1.2 1 *.9) E-2 40W, 230N 40W. 240N Surface 0.1 1 0.1 1.610.9 40W, 250N Surface 0.1 1 0.1 1.1 1 0.6 40W. 260N Surface 0.2 1 0.1 1.3 1 0.8 Composite 1 (1.5 1 3.6) E-2 (9.016.2) E-2 40W. 270N Surface 0.1 1 0.1 0.7 1 0.8 40W, 200N Surface 0.5 i 0.6 0.2 i 1.3 d
3ew. 234N Surface 0.3 1 0.1 1.9 1 1.0 Composite 11 (0.6 1 2.0) E-2 (0.6 1 2.6) E-2 36W. 234N 45-60 0.1 1 0.1 0.9 i 0.6
~..
, 7.A,
~
mW W
W W
W W
W W
W W
W W
W W
W W
W W
N
- L.
TABLE G (Cont'd URANIUM AND PLUTONIUM CONCENTRATIONS IN SOIL SMPLES I'
MIXED OXIDE FACILITY
'CION ROM CORPORATION l
l-CRESCENT, OKLAN0pm l.
~
i.
1 i
Scapling"
')epth Uranium Concentratione (pCf/s)
Plutonium Concentretione (sci /s) l' Location (ce)
.U-238 Pu-238 Pu-239/240 30W. 260N Surface 0.2 i O.1 0.7 1 0.8 Composite 2
'(0.7 1 3.2) E-2 (0.7 i 2.4) E-2 30W. 2704 Surface 0.2 i C.1 1.711.0 30W, 280N Surface 0.2 i 0.1 2.8 1 1.5 30W. 290N Surface 0.2 1 0.1 1.9 i 1.0 29W. 276N Surface 0.1 1 0.1 1.711.1 Composite 11 (0.6 1 2.0) E-2 (0.6 1 2.6) E-2 U
29W. 276N 45-60 0.1 1 0.1 1.7 i 1.0 O
29W, 276N 75-90 D.2 1 0.1 1.0 1 0.8 i
20W, 190N Surface 0.2 1 0.4 3.2 1 0.9 Composite 2 (0.7 1 3.2) E-2 (0.712.4) E-2 20W 260N Surface 0.6 1 0.5 1.3 1 0.6 l
20W. 270N Surface 0.2 0.1 1.1 i O.9 j
20W. 280N Surface 0.2 1 0.1 2.6 i 1.1 i
15W. 190N Surface 0.3 1 0.1 1.5 i 0.8 Composite 12 (0.7 i 3.1) E-2 (2.1 1 3.7) E-2 45-60 0.2 1 0.1 1.4 i 1.0 90-105 0.1 1 0.1 1.9 i 1.0 165-180 0.2 i 0.1 1.0 1 0.3 10W. 190N Surface 0.2 1 0.1 2.0 1 0.9 Coscosite 10 (0.7 1 2.9) E-2 (2.6 i 3.6) E-2 l
10W. 252N Surface 0.2 1 0.1 1.8 1 0.8 45-60 0.1 i 0.1 1.5 1 0.8 1
75-90
-0.1 1 0.1 1.1 1 0.7 10W, 260N Surface 0.2 1 0.1 2.2 1 0.8 Comeceite 3 (0.7 1 2.9) E (1.312.5) E-2 j
10W. 270N Surface-0.1 1 0.1 2.0 1 0.9 10W. 280N Surface 0.1 1 0.1 2.3 1 1.0 10W, 285N Surface 0.2 i O.1 1.610.9 Composite 11 (0.6 1 2.0) E-2 (0.612.6) E-2
- ~
45-60 0.3 1 0.1 2.6 i 1.6 60- 75' O.2 1 0.1 1.3 1 1.2' i
. ~. -
., - ~.,. _ _ - _.. _. -. _ -. _. ~ - -... _.. _.. _ _. _ _ _ - -
m.-
.. t ro <
14 TABLE 8 (Corv2*d)
URAM1UM AND PLUT0NIUN CONCENTRATIONS IN SOIL SAMPLES MIMED OX1DE FACILITY CIMARROC CORPORATION CRESCENT. OKLAH0pm Plutonism Concentretiorm (pCi/2)
Oranium Concentretione (pCi/g)
Pu-239/240 Sampling
- Depth Pu-238 location (cm)
U-235 U-238 10W. 290N Surface 0.2 1 0.1 1.8 i 1.2 15-30 0.2 1 0.1 2.0 1 1.1 30- 45 0.2 1 0.1 2.1 1 1.2 45-60 0.4 1 0.9 2.6 1 1.0 Composite 11 (0.6 i 2.0) E-2 (0.6 1 2.6) E-2 60- 75 0.3 i 0.1 2.1 1 1.0
~
75-90 0.2 1 0.1
<1.9 0, 190N Surface 0.3 1 0.1 1.7 1 1.0 Composite 10 (0.7 1 2.9) E-2 (2.613.6) E-2 t=d
- 0. 252M Surface 0.1 0.1 2.2 1 0.8 45-60 0.1 1 0.1
<1.3 75-90 0.2 1 0.1 1.7 i 0.7
~
135-150 0.2 1 0.1 1.7 i O.7
- 0. 260N Surface 0.1 1 0.1 1.4 i 1.1 Composite 3 (0.712.9) E-2 (1.31 2.6) E-2
- 0. 270N Surface 0.2 1 0.4 3.2 1 0.8 0, 280N Surface 0.2 1 0.1 1.9 i 1.0 8E. 218N Surface 0.3 i 0.1 1.8 i 1.0 30- 45 0.4 1 0.4 4.1 1 1.5 75-90 0.2 1 0.1 1.5 i 1.0 10E, 100N Surface 9.2 1 0.3
<1.5 10E. 190N Surface 0.4 1 0.4
<1.3 Composite 10 (0.7 1 2.9) E-2 (2.613.6) E-2 10E. 200N Surface 0.3 1 0.1 2.0 1 1.1 Composite 8 (1.2 1 3.2) E-2 (1. 2 1 2.3) E-2 10E. 210N Surface 0.4 1 0.5 1.711.1 10E, 220N Surface 0.2 1 0.1 2.3 1 1.0 10E, 230N Surface 0.4 i O.1 2.2 1 1.1 Composite 7 (2.0 1 3.7) E-2 (0.7 1 2.9) E-2 O.3 1 0.1 1.5 i 1.2 10E, 240N 10E, 250N Surface 0.2 1 0.1 1.3 1 0.9
h7
.I l
.I V netE o (cont c)
URAmitM AND PLUTONIUM CONCENTRATTONS IN SOIL SdePLES MIXED ORIDE FACILITY CInWIRON CORPORATION CRESCEN7. OKLAH0pm Plutonies Concentrations (pCi/a)
Sampling Depth Uranium Concentratione (pCi/s) s Pu-238 Pu-239/240 Locetion (es4 U-235 U-238 l
10E 260N Surface 0.2 1 0.1 1.711.2 Composite 4 (1.9 i 3.3) E-2 (1.9 1 2.8) E-2 l
10E, 270N Surface 0.3 i 0.4 0.9 i 1.1 10E, 280N Surface 0.3 1 0.4 1.411.3 15E. 240N Surface 0.4 1 0.4 2.1 1 1.0 45-60 0.2 i 0.5 2.1 1 1.2 Compoelte 12 (0.7 i 3.1) E-2 (2.1 2 3.7) E-2 90-105 0.3 i 0.1 1.6 1 1.1 U
135-150 0.4 1 0.5 1.6 1 0.9 18E, 277N Surface 0.2 0.1 2.711.2 45-60 0.3 1 0.1 2.4 i 1.0 composite 12 (0.7 1 3.1) E-2 (2.1 2 3.7) E-2 90-105 0.9 i 0.S 2.011.0 135-150 0.6 1 0.5 2.411.4 20E. 190N Surface 0.2 i O.1 2.3 1 0.8-Comumeite 10 (0.712.9) E-2 (2.6 i 3.5) E-2 20E, 200N Surface
,0.8 i 0.9 1.1 0.8 Composite 8 (1.2 1 3.2) E-2 (1.2 1 2.3) E-2 20E, 210M Surface 0.3 i 0.1 2.0 1 1.1 20E, 212N Surface 1.5 1 0.6 4.3 1 1.9 30- 45 1.5 1 0.5 4.6 i 1.0 75-90 0.6 1 0.6 2.0 1 1.0 20E, 220N Surface 0.2 1 0.I' 1.5 1 0.8 Composite 8 (1.2 1 3.2) E-2 (1.212.3) E-2 20E. 230N Surface 0.3 1 0.6 2.3 1.1 Composite 7 (2.0 1 3.9) E-2 (0.7 1 2.9) E-2 20E, 240N Surface 0.4 1 0.2.
1.5 i 1.2 20E. 250N Surface 0.2 1 0.1 1.3 1 1.2 20E, 260N Surface 0.3 1 0.4
<1.7 Composite 4 (1.9 i 3.3) E-2 (1.9 i 2.8) E-2 20E. 270N Surf &ce 0.8 1 0.7 2.8 1 1.1 20E. 200N Surface 0.2 1 0.1 1.9 1 1.0 20E, 290N Surface 0.1 1 0.1 1.6 f.1.0
w s _
.W4 TA8tE 8 (Cont'd)
URMIIUN AND PLUTONIUM CONCENTRATIONS IN SOIL SAM LES MIXED OKIDE FACILITY C1944RR0N CORPORATION CRESCENT, OKU340pm 4
i s
a Sampling Depth Uranium Concentretions (pCi/s)
Plotonlum Concentretions (pCi/g)
Location (ce)
U-235 U-238 Pu-238 Pu-239/240 30E, ISON Surface 0.5 1 0.3 2.5 1 0.8 30E, 200N Surface 0.5 1 0.5 6.4 1 2.0 30E, 220N Surface 1.3 1 0.6 7.7 i 1.2 30E, 250N Surface 0.3 1 0.1 2.5 i 1.2 15-30 0.2 1 0.6 1.4 1 1.1 C
30- 45 0.6 i 0.5 3.2 1 1.1 45-60 0.3 1 0.1 2.1 1 1.1 Composite 12 (0.7 1 3.1) E-2 (2.1 1 3.7) E-2 60- 75 0.3 1 0.1 1.6 1 1.0
(75-100 0.2 1 0.2 1.6 i 1.1 30E, 270N Surface 0.2 1 0.1 0.7 1 1.1
%efer to Figure 61.
4ncertainties represent the 95% confidence levels, based only on counting statistics: additional laboratory uncertainties of i 6 to 104 have not been propageted into these deta.
CAlso contains 0.810.1 pC1/g of An-241.
dAleo contains 4.610.1 pCi/g of Ant-241.
I
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W ulus t
r1_fo t_;
TABLE 9 DRAINAGE OUITALL SAMPLES AND MEASUREMENTS MIXED OXIDE FACIIIIY CIMARRON CORPORATION FIANT CRESCENT, OKIAHOMA Contact RDIDWASLE CONTaNIIIATION RADie ISE NTIGIS (mC1/m3 LOCATION
- Alpha Seta Gamune Alphe sets (dpm/100 c=8) (dpm/100 cm*)
(pa/h)
(dpm/100 cm )
(dpar100 am*)
u-235 u-238 Am-Mi ev-238 ev-239/MS m0.
1 Inside
<28 1900 8-11 3
4 0.2 a 0.1 2.5 e 1.3
<0.3 0.06 a 0.06 0.7 a 0.1 b
2
<28 390 8-10
<3
<6 C.1 s 0.1 1.4 e 1.0
<0.2 0.01 s 0.03 0.09 e 0.06 3
<28
<350 8-10
<3 4
0.8 s 0.5 5.0 s 0.9
<0.3 0.01 a 0.05 0.01 a 0.04 4 On screen 60
<350 9
<3
<6 0.1 e 0.1 2.5 e 0.8
<u.2 0.02 a 0.07 0.01 a 0.05
~.
s 5
<28
<350 9-10
<3 8
0.3 a 0.1 3.1 a 1.0
<0.3 0.01 a 0.02 0.01 s 0.02
- Refer to Figure 62.
hertainties represent the 95% confidence levels, based only on comtin0 statistics; additionet laborotory acertainties of 2 6 to 10% have not been propogeted into these dets.
TABLEle 1
)
SUMMARY
OF SURFACE ACTIVTIY MEASUREMEh'!11 ON THE J
BUILDING EXTERIOR, WALEWAYS AND MISCELLANEOUS SURFACES MIXED OXIDE FACIIIn'
[
CIMARRON CORPORATION PLANT l
CRESCENT, OKLAHOMA vu TCTAL CONTAMINATION ELEMOVARLE CONTAMINATION Alpha Beta Gamma Alpha Beta 8
2 8
8 1DCATION*
(dpe/100 ca )
(dpa/100 cm )
(dps/100 ca )
(dps/100 ca )
I i
1 6500 3700 58 9
2 100 530
<3
<6 3
40
<350 3
<6 4
160
<350
<3
<6 1
5 110
<350
<3
<6 6
240 440
<3
<6 7
<28
<350 5
<6 8
290
<350 5
<6 9
230
<350 5
<6 10
<28
<350 5
7 11 70 530 7
7 l
12 40
<350
<3
<6 13
<28
<350 3
<6 14 120 470
<3
<6 15 40 470
<3
<6 16 220
<350
<3 8
17 110
<350
<3
<6
. 1 18 30
<350 5
<6 19 40
<350
<3
<6 20 40
<350
<3
<6
-g 21 50 530 3
<5
.l 22
<28 (350
<3
<6 23
<28
<350
<3
<6 24
<28 610
<3 13 1
25 80
<350
<3
<6 26 30 780
<3
<6 27 30 690
<3
<6 28 110
<350
<3
<6 1
29 80 1000
<3
<6 30 70
<350
<3
<6 31 110 670
<3
<6 32 140 1200
<3 9
33 130 720
<3
<6 34 90
<350
<3
<6 35
<28
<350
<3
<6 36 40
<350
<3
<6 37 160 1500
<3
<6 115
s a
TASLE 10 (Continued)
J
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS ON THE BUILDING EXTERIOR, VALEUAYS AND MISCELLANEOUS SURFACES l
MIKED OF.ZDE FACILITY D
CIMARR0N CORPORATION PLANT CRESC1NT, OELAMOMA
'=
TOTAL CONTAMIMATION REMOVABLE CONTAMINATIf3L.,
Alpha Beta Canna Alpha Beta 8
8 8
8 LOCATION *
(dpa/100 en )
(dpa/100 ca )
(dpa/100 en )
(dpa/100 cm )
1 38 2500 3500
<3
<6 1
39 100
<350
<3
<6
=
40 130 1000
<3
<6 41 40
<350 3
<6 h
42 100 610
<3
<6 l
43 60
<350
<3
<6 44 140
<350 3
<6 45 490 1700
<3 8
1 46 1800 2900 3
<6 47 2000 1800 7
<6 48 2400 1900 3
<6 49 600 1700
<3 8
"1 50 230 550
<3
<6 51 240
<420
<3
<6 52 410 820
<3
<6 1
53 660 1200
<3 7
54 380 790
<3 12 55 310
<420
<3
<6
)
56 500 420 3
<6 3
57 250 470
<3 10 58 200 610 3
<6 59 200
<350
<3 8
1 60 270
<350
<3
<6 61 50 440
<3
<6 62 860
<350 18 15 63 220 390
<3
<6 64 240
<350
<3
<6 65 170
<350 3
<6 66 130
<350
<3
<6 67 1100
-b
<3
<6 68 1200 1100 18
<6 69 310
<420
<3 7
- Refer to Figures 57 and 58.
bDash indicates measurement not performed.
116 s
M' W
W L__f ~ U
'O L___>
TAME 11 RADIONUCLIDE CONCENTRATIONS IN NISCELLArtE00S EXTERIOR SAMPLES NIXED OXIDE FACILITY CINARRott CORPORATION CRESCENT OKLAHORA Radionuclide Concentration (pCf 't)
Sampling Location U-234 U-235 U-238 Pu-238 Pu-239/240 paint /beneath east stairway 6062 1 80s 356 1 27 540 1 90 0.15 1 0.15 0.52 1 0.17 concrete /beneath east stairway 476 i 9 22 1 3
15 1 2
0 91 i 0.02 0.14 1 0.05 concrete /loating dock sidewalk 4.55 1 0.24 0.26 i O.08 1.06 1 0.12 0.01 1 0.01 0.13 1 0.04 gravel / roof 0.46 i O.18 0.12 1 0.11 0.51 1 0.17
<0.01 0.01 1 0.02 gravel / roof 0.45 1 0.09 0.01 1 0.03 0.49 i 0.09 0.05 1 0.03
<0.01 gravel / roof 0.86 0.12 0.02 1 0.03 0.38 1 0.08 0.01 i O.02
<0.01 fence section 115.4 1 1.8 5.67 1 0.52 35.2 1 1.0 0.04 i O.04 0.15 1 0.07 aUncertainties represent the 95% confidence levels, based only on counting statistics; additional laboratory uncertainties of i 6 to 10% have not been propagated into these data.
.M
-M.
M M M ^ M M
M M
M M
M M
M M
-M' W M
8 l
~ TABIE 12
SUMMARY
OF SURFACE ACI1VrIY MEASURERENT AT IDCA110NS IN THE SANITARY DPAIN SYSIEM MIXED OXIDE FACIIEIY CIMARRON CORPORA 110N FIANT CRESCENT, OKIAIIOMA j
TOTAL COffrAMINATION EXPOSURE RATE REMOVABE CONTAMINA~I1ON Alpha Beta-Gamma Ganuna Alpha Beta 2
2 2
2 LOCATION" (dpunf1'IO cm )
(dpm/100 cm )
pR/h (dpan/100 cas )
(dpan/100 cas )
l{
1
<28
<350 8 - 10 7
78 E
2
<28
<350 9 - 10
<3 20'
{
4 3 In Pipe 30
<350 7-8
<3
<6 Box Bottom 30 560 7-8
<3
<6 4
30
<350 8-9
<3
< 6' i
i
" Refer to Figure 59.-
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REFlERENCES 1.
Chnarron Corporation, Request for Plutonium Plant Release From NRC Ucensing, July 27,1999, and annociated supporting survey data.
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. APPENDIX A -
s y
- MAJOR SAMPIJNG AND ANALYTICAL EQUIPMENT >
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3
. APPENDIZ A-m 4
MAJOR SAMPLING AND ANALYTICAL EQUIPMENT
=
'Ibe dhplay or decription of a speciSc product is not to be construed as ar. endorsement of that-3 product or its manufacturu by the authors or their employer.
s 1
A.
Dieset Radiation Measurements M
Eberline " RASCAL'
=i Portable Ratemeter-Scaler Model PRS-1 (Eberline, Santa Fe, NM)
Eberline PRM4 Portable Ratemeter 2
(Eberline, Santa Fe, NM)
Eberline Alpha ZnS Scintillation De'.ector
. Model AC-3-7 or AC-3 --
(Eberline, Santa Fe,' NM).
Eberline Beta-Gamma " Pancake" Detector -
~
Mcdel HP 260
, (Eberline, Santa Fe, NM) aE Ludlum Alpha-Beta Floor ikuitor Model 239-1 6
(Ludlum Measurements, Sweetwater, TX) k Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Sweetwater, TX)
Ludlum Ratemeter-Scaler MoCel 2200 -
(Ludium Measurements, Sweetwater, TX) -
-Reuter-Stokes Pressurized Ionization Chamber
=
. Model RSS-111 (Reuter Stokes, Cleveland, OH) 4 g
A.1 1
.___m
y>
l' 1/
iVu:toreen Beta. Gamma " Pancake" Detector Model 489110 :
(Victoreen, Cleveland, OH);
l Victoreen Nal Scintillation Detector Model 489 55
' (VMw Cleveland, OH).
Ludlum Proportional Detector Model 4M8 (Imdiums Measurementa, Sweetwater, Tx)
. P7CRON Na! ScintGation Detector.
Model G5,fFIDLER' (Bicron Corp., Newbury, Ohio)
B.
Imboratory Analyses
- Automatic low-background Alpha Beta Counter -
Model LB5110 2000 1
' (Ta=W. Oak Ridge, TN)
I i High Purity Germtnium Detector -
Model GMX.23195-S, 23% efficiency _
(EG&O ORTEC, Oak R'dge, TN)
Used in conjunctior, w'.dn I. mad Shield, G j (Gamma Products, Inc., Palos Hills, IL) l Multichan=1 Analyzer ND46/MicroVax.
- (Nuclear Data, Schaumburg, IUDigital Equipment Corp., Maynard, MA)
I
. Alpha Spectrometry System Tennelec Electronics
'(Tennelec, Oak Ridge, TN)
Solid State Surface Barrier Detectors (EG&O ORTEC, Oak Ridge, TN)
.(Tennelec, Oak Ridge, TN) y-L Multichannel Analyzer Model ND46 :
(Nuclear Ds% schaumburg,IL) i A-2 I
~~9'.,
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o-APPENDIX B.'
I' MEASUREMENT, SAMPIJNG, AND ANALYrICAL PROCEDURES 4
I1.
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1 APPENDIX B.
. MEASUREMENT, SAMPLING, AND ANALYI1 CAL PROCEDURES r
EartamLSans i
Surface scans were performed by passing the probeb slowly over the surface. M distance between thel probe and the surface was maintained at a minimum - nominally about 1 cm (0.4-in).
IdentiScation of elevated levels was based on increases in the audible dgnal from the recording or indicating instrument.x Combinations of detectors and instruments used for the scans were:
Alpha l'
- Ludlum Model 4348 gas proportional detector with Ludlum Model 2221 ratemeter acalor 1
Large area gas proportional detector with Ludlum Model 2220 ratemeter-scaler 1
Gamma
- Victorcen Nal scintillation detector with Eberline PRM4 ratemeter Bicron "FIDLER". scintillation detector with Ludlum Model 2221 ratemeter-scaler -
Measurements of total alpha and beta-gamma radiation activity levels were performed using Ludlum (Model 2221 portable ratemeter scalers' with Model 4348' thin window proportional: detectors, Eberline Model PRS 1 portable ratemeter scalers with Model AC3-7 alpha scintillation detectors il or Model HP-260 thin-window "p=--b" OM detectors. Count rates (cpm) were converted to disinteOation rates (dpm/100 cm ) by dividing the net rate by the 4 r efrx:iency and correcting for -
2 2
2 the active area of the detector. Effective window arecs were 59 cm for the ZnS detectors,15 cm B-1
~
3 2
for the dpha scintillation detectors, and 100 cm for the proportional detectors. Background count l
rates from 12 cpm for alpha detectors,40 47 eps for GM 'y--b' detectors, and 14 cpm for -
proportional' detectors with voltage settings in tbs alpha region.-
I.
_ _ Man rm o,
Smear essesurements were perfonned using numbered filter paper disks, 47 mm in diameter.
2 I4
-M- * "j 100 cm was wiped applying madarste pressure. _ Smears were counted on a low-g
- background alph Deta gas proportional counter at the Oak Ridge laboratorf.
h -
Expos.no Rate Mensamenents a
Measurements of gamma exposure rates were performed using Eberline PRM-6 portable ratemeters x
- with Victoreen Model 489 55 gamma scintillation probes containing 3.2 can (1.25 in) x 3.8 cm (1.50 in) Nal(T1) scintillation crystals. Count rates were converted to exposure rates ( R/h) by cross _ -
calibrating with a'Reuter Stokes Model RSS 111 pressurized ionization chamber. Count ratu obtained from the Bicron "FIDLER" were used for reference purposes only and:therefore were
. not converted to exposure rate measurements.
g7 W-"-ly 1 kg of soil was collected at each sample locrtion.- Surface saples were collected from 015 cm..
Subsurface samples were collected at various depths as accessible.
a g
- Interior samples ~ from escavations were collected from accessible W_ soil surfaces and from faub0cor excavations. Samples were also collected from barrels of excavated soil.
- 'i!<,
4 h,,
?
B-2 p.'
c<
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=
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Concrete and paint samples were taken by chipping or scraping material from approximately 100:
2 cm og,,,g,,,,
SaltaseqphtAnahnis
=
Gamma Spectroscopy Soil samples were dried, mined, and a' portion sealed in 0.5 liter (0.53 qt) Marinelli beaker, h quantity placed in each beaker was chosen to reproduce the cahbrated counting geometry'and -
- ranged from 600 to 900 g (1.3 to 2.0 lb) of soil. Net soil weights were determined and the samples'-
t
- counted using high-purity intrinsic germanium detectors coupled to a Nuclear Data pulse height analyser system. - Background and.Compen stripping, peak search, peak lidenti6 cation, and
--7 concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks'of M interest were: U-235,0.144 MeV; U-238, 0.093 MeV from 'Ih-
.L' g
234 and 1.001 MeV from Pa-234 m; and Am-241,0.059 Mev. - Spectra were also icA-d for the!
presence of other photopeds.
_1_
' Alpha Spectrompyi 9
n 1
J Groups of soil samples were composited for isotopic uranium and plutonium analyses. Portions of
.]
5 to.10 original samples were combined and homogenized. - Aliquots of these mixtures.were '
'.c Tdissolved by pyrosulfate fusion and precipitated by barium sulfate, h barium sulfate precipitate
[ was redissolved and the speciSc elements of interest were individually separated by liquid liquid '
extraction. The radionuclides were then precipitated with a cerium Douride carrier and counted
}
using" surface barrier detectors 1(ORTEC), alpha spectrometers (Tennelec), and an ND.66 Multichannel Analyzer (Nuciciar Data).
y.
B-3 1
m,
Cancreta. Paint and Miscellaneoas Sample Analysis Concrete and paint samples were ground to a fine consistency and analyzed for uranium and plutonium as previously describen Sr soil. A section of the perimeter fence was washed with acid and the washina wm analysed in tu same==aar.
Uncertainties and Detection llanits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% annReinnce levele for that data. 'Ibese uncertainties were calculated based on both the ~
'gmas ample count levels and the associated background count levels.- When the net sample count was less than the statistical deviation of the background count, the sample concentration was reported as less than the detection limit of the procedures. Because of variation in background levels, detector efficiencies, and the effects of other radionuclides in samples, the detection limits '
differ from sample to sample and instrument to instrument.
Calibration and Omality Assurance Ihe Environmental Survey and Site' Assessment Program conducted the survey and analytical activities according to labo72 tory and field survey procedures specified in-manuals developed sM6=9y for the Oak Ridge Associated Universitics' Environmental Survey and Site Assessment Program to meet the requirements of ANSI /ASME. NQA 1, " Quality Assurance ' Program l
LRequirements for Nuclear Facilities". 'Ihe specific manuals and procedores applicable to this survey were the " Quality Assurance Manual", December 1988, Revision 2: the " Survey Procedures Manual,"
l
- August 1988, Revision 4; and the " Laboratory Procedures Manual," August 1988, Revision 4.
f
' Witht the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated with NIST-traceable standards. The cahtration procedures
- for the portable gamma. Instruments are performed by comparison with an NIST calibrated pressurized ionization chamber.
B-4 m
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eta'10 COBflI13 SquipEnent Operation within Weble statistical fluctuations. ' he f ORAU laboratory participates in the EPA and EML Quality Assurance Prograns.
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- APPENDIX C
' GUIDELINES FOR DECONTAMINATION AND DECOMMISSIONING -
3 i
- OF THE CIMARRON CORPORATION MIXED OXIDE L
FUEL FABRICATION PIANT M
M
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' The. instructions.;in this -' guide, in conjunction with Table. l -'specify
' he radionuclides and : radiation ' exposure rate limits which should be used t
'i3C decontamination, and survey of surfacest or premises and equipment, prior-
- < ts: abandonment or-release for unr'estricted use.
The limits in Table 1 do
" nit'aN1ytopremises,-equipment', or scrap-containing induced radioactivity i>
for Mbich1 the radiological considerations pertinent to their use. may. be -
<difIerent. 'The~ release of s'ach facilities or itoms'from regulatory control
'is ' considered on a case-by-case basis.
1
-f'..
. The' licensee shall make a ' reasonable ef fort to eliminate residual c
' 'l.
contamination.
2.
Radioactivity. on equipaent or surf aces shall not' be covered by paint,
_ plating, ; or 'other covering, material unless-contamination. levels, as -
- determined by i a - survey and documented, are below the limits specified 4L in Table 1. prior to the application of the covering.-
A ' reasonable -.
g f
> effort must be made to minimize the contamination prior to use of any-covering.
q 3y ' The radioactivity onithe interior surf aces of pipes, _ drain lines, or
, ductwork shall.be determined' by-making-measurements at all traps,. and
[' t ~
other appropriate access points, provided that contamination at these -
3
~ locations; is. likely to. be representative of contamination ' on the
-interior of the-pipes, drain - lines,. or ductwork. -
Surfaces or premises, equipment,~or' scrap which are likely to be contaminated but-J' t are of = such i ize,7 construction, or location as'to make.the surface s
. inaccessible ifor! purposes of measurement shall be presumed to be contaminated in excess of the limits.
- 4 ~.
Upon request. the Commission' may authorize a licensee to relinquish-pcssession or contro11of ' premises,-- equipment, or.' scrap having surf aces contaminated with materials in excess of the: limits specified..This may include, i but.would not be limited to,' special ' circumstances.such
- as ' razing. of buildings, transf er' of premises, to -'another organization n
. continuing. work ? with _ radioactive ' materials, ior conversion of
+
facilities to a long-term storage or, standby, status.' Such' requests
- must:
s '.
Provide detailed, specific information describing 'the ~ premises, equipment. or. scrap radioactive contaminants, and the nature.
extent, and degree of residual surf ace contamination, b.-
Provide a detailed. health and safety analysis which reflects that.
- the residual' amounts of materials on-surf ace-areas, together with other considerations such as prospective use of the premises, 4
equipment or -scrap, are unlikely to result in an 'uurea6onable risk to the health and safety of the public.
4
- 5. -
Prior to release of premises for unrestricted use, the licensee shall
~
make a
comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of C-1 1
f\\
i
+ '
the survey report shall be filed with the Division of Fual Cycle and Material
- Safety, USNRC, Washington, D.C.
- 20555, and also the Administrator of the NRC Regional Of fice having jurisdiction.
The
!=
report should be filed at least 30 days prior to the planned date of abandonment. The survey report shall:
(
a.
Identify the premises.
=-
b.
Show that reasonable ef fort has been mada to eliminate residual contamination.
Describe the scope of the survey and general procedures followed.
c.
d.
State the findings of the survey in units specified in the instruction.
7ollowing review of the report, the NRC will consider visiting the facilities to confirm the survey.
I
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TABLE l
' ACCEPTABLE ~ SURFACE CONTAMINATION LEVELS Nuclidesa-b
-. Average,c,f Maximum,d,f.
b Removableb,e,f U-nat, U-235, U-23 8,. and -
associated decay products 5,000 dpa ' a/100 cm2 :
15,000 dpm a /100' cm2 L1,000 dpe n/100 'cm2 N
Transuranics, Ra-226, Ra-228, 100.dpe/100 cm2 Th-230, Th-228, Pa-231, 300 dpa/100 'em2
~ 20 dpm/100 cm2-Ac-227, I-125, I-129 Th-nat, Th-232, Sr-90, Ra-223 1000 dpe/100 cm2 Ra-224, U-232, I-126, I-131, 3000 dpe/100 cm2 I-133 200 dpa/100 cm2-Beta gamma emitters (nuclides o
O with decay modes other-than 5000 dpa Sy/100 cm2 15,000 dpa Sy/100 cm2 1000 dpm Sy/100 cm2 alpha emission or spontaneous fission) except Sr-90 and-others noted above.
a Where surface contamination by both alpha-and beta gamma-emitti As used in this table, dpa (disintegrations'per minute) means the rate of e iesta ng nuclides exists, the limits b
material as determined by correcting the counts per minute observed by an appropriat m ssion'by radioactive background, efficiency, and geometric factors associated with-the instrumentation e detector for c Measurements of. average contaminant should not be averaged'over mo of less surface-area, re than i square meter. For objects the maximum contamination level applies ' to an area of not more 'than 100the average"should d
- The amount of removable radioactive material:per 100 cm 2
cm,
2 wiping that area with dry filter or: soft' absorbent paper, applying moderate p of surface area.should be determined by ure, and assessing-reduced proportionally and the' entire surface;should be viped. removable contamination
- nown efficiency. When-should be f
emitters should notl exceed 0.2 mrad /h at I-cm and 1.0~ mrad /h~at I cmThe avera resulting from beta gamma not more than 7 milligrams 'per square centimeter of' total absorber.-, respectively. measured through
~
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FOR L. '
RESIDUAL RADIONUCIJDES IN SOIL t-7
.De gamma level in air at one meter above ground level is not to exceed 10 gR/h (above background) for a diffuse source area and is not to exceed 20 'pR/h_(above background) for a i
discrete area.
a-uL Concentrations la Soil 4
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Concentrations of residual radionuclides were established by the NRC to assure that the does to
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i thh body fan inhalation would not asceed 1 mradly, above Wcond, to the bone. These dose :
criteria are consistent with those recommended by EPA for residual transuranic contamination of.
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- soil. 'On the basis of these dose criteria, the guidelines for radionuclides in soil the Ci:narron :
Corporation site were determined to be:
Plutonium 25 pCi/g Americian 241 30 pCi/g Total Uranium (enriched in U-35)
- 30 pCi/g:
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.'When mixtures of radionuclides are present, the sum of the ratios of individual radionuclide concentrations to their respective guwliae levels must be less than or equal to 1.
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