ML20086C790
| ML20086C790 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 06/30/1991 |
| From: | Beverly Smith OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| ORAU-91-F-93, NUDOCS 9111250094 | |
| Download: ML20086C790 (158) | |
Text
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Prepared by CONFIRMATORY RADIOLOGICAL SURVEY I Oak Ridge Associated Universities FOR PORTIONS OF THE
[ Prepared for SAXTON NUCLF AR EXPERIMENTAL FACILITY u.S. Nuciear Regulatc.t SA ' N. PENNSYLVANIA commisson.s Region i Othee Sponsored by
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Industrial and Medical l
Nuclear Safety l
Environmental Survey and Site Assessment Prog *am Energy / Environment Systems Division FINAL REPORT JUNE 1991
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CONFIRMATORY RADIOLOGICAL SURVEY FOR PORTIONS OF TIIE SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA A
Prepared by Betty M. Smith Emironmental Survey and Site Assessment Program Energy /Emironmental Systems Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff J. D. Berger M. A.1.audeman E. H. Bjelland E. A. Powell P. R. Cotten C. A. Searcy G. R. Foltz T. J. Sowell C. F. Weaver Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region I Office FINAL REPORT JUhT 1991 This report is based on work performed under Interagency Agreement (NRC Fin.
No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.
Oak Ridge Associated Universities performs complimentary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy.
f CONFIRMATORY RADIOLOGICAL SURVEY FOR PORTIONS OF TIIE
-l SAXTON NUCLEAR EXPERIMENTAL FACILITY SAX ~ ION, PENNSYLVANIA f
I Prepared by:
M Date: 9-I-9 l BTM. Sm7th, Project Leader Environmental Survey and Site Assessment Program
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Date:7I
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Prepared by:
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P. R.$otten, Senior Project Leader Environmental Survey and Site Assessment Program E Wh Date: [~ !~
Reviewed by:
C. F. VG: aver, Laboratory Manager Environmental Survey and Site Assessment Program 7///9/
Reviewed by:
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Date:
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D. Berger, ProgragpDirector nvironmental Survey and Site Assessment Program Approved by:
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Date:
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R. J. Cloutier, $sistant Chairman
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Energy / Environment Systems Division l
l TABLE OF CONTENTS l
PAGE i
Lis t o f Figur e s..............................................
ii List of Table s...............................................
ix In trod u c tio n................................................
I 2
Facility D escrip tion...........................................
P roce d ur e s.................................................
4 8
Findings and Results..........................................
Comparison of Results with Guidelines..............................
13 15 Summan..................................................
R e fe r e n ce s.................................................
129 Appendices:
Appendix A:
" Major Sampling and Analytical Equipment Appendix B:
Measurement, Sampling, and Analytical Procedures Appendix C:
U.S. Nuclear Regulatory Commission Guidelines for Surface Contamination and Soil Contamination i
I LIST OF FIGURES (Con't)
PAGE FIGURE 28:
C&A Building First Floor Corridor Ceiling:
Measurement and Sampling Locations..................
44 FIGURE 29:
C&A Building lecker Room: Measurement i
and Sampling locations............................
45 FIGURE 30:
C&A Building Locker Room Ceiling: Measurement 46 and Sampling Locations............................
FIGURE 31:
C&A Buikling Monitor Room: Measurement and 47 Sampling Low tions...............................
FIGURE 32:
C&A Building Monitor Room Ceiling: Measurement 48 and Sampling Imcations............................
FIGURE 33:
C&A Building Toilet and Shower: Measurement 49 and Sampling Locations............................
FIGURE 34:
C&A Building Toilet and Shower Ceiling:
Measurement and Sampling 1Acations..................
50 FIGURE 35:
C&A Building North Stairway: Measurement 51 and Sampling Locations............................
FIGURE 36:
C&A Building Auxiliary Equipment Room:
Measurement and Sampling Locations..................
52 FIGURE 37:
C&A Building Auxiliary Equipment Room Ceiling:
Measurement and Sampling Locations..................
53 FIGURE 38:
C&A Building Southeast Stairway: Measurement and Sampling Locations............................
54 FIGURE 39:
C&A Building Janitor Closet: Measurement and 55 Sampling Locations...............................
FIGURE 40:
C&A Building Instrument Repair Shop: Measurement 56 and Sampling Locations............................
iv 1
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LIST OF FIGURES PAGE q
FIGURE 1:
Saxton Nuclear Experimental Station...................
17 FIGURE 2; Saxton Site Plan.................................
18 FIGURE 3:
C&A Building Ground Floor Plan.................... <
19 FIGURE 4:
C&A Building Second Floor Plan...................,
20 FIGURE 5:
RWDF Building Above Grade Floor Plan................
21 FIGURE 6:
RWDF Building Below Grade Floor Plan................
22 FIGURE 7:
Background Measurement and Baseline Sampling Locations in the Vicinity of the Saxton Nuclear Expe rime n t al S ta tion..............................
23 FIGURE 8:
Saxton Site Plan: Exposure Rate Measurement Loca t i o n s......................................
24 FIGURE 9:
C&A Building Ground Floor: Exposure Rate Measurement Locations........................
25 FIGURE 10:
C&A Building Second Floor: Exposure Rate Measurement Locations............................
26 FIGURE 11:
C&A Pipe Tunnel: Exposure Rate Measurement Locations......................................
27 FIGURE 12:
RWDF Pipe Tunnel: Exposure Rate Measurement Loca ti o n s......................................
28 FIGURE 13:
RWDF Building Below Grade Floor Plan:
Exposure Rate Measurement Locations.................
29 FIGURE 14:
RWDF Building Above Grade Floor Plan:
Exposure Rate Measurement Locations.................
30 ii
I LIST OF FIGURES (Con't)
PAGE I
FIGURE 15:
C&A Building Variable Frequency Room:
31 Measurement and Sampling Locations..................
i FIGURE 16:
C&A Building Variable Frequency Room Ceiling:
32 Measurement and Sampling Locations..................
FIGURE 17:
C&A Building Switch Gear Room: Measurement 33 and Sampling Locations............................
FIGURE 18:
C&A Building Switch Gear Room Ceiling:
34 Measurement and Sampling Locations..................
FIGURE 19:
C&A Buildir.g Battery Room: Measurement and 35 Sampling Locations...............................
l FIGURE 20:
C&A Building Battery Room Ceiling: Measurement 36 and Sampling Locations...........................
FIGURE 21:
C&A Building HP Room: Measurement and 37 Sampling Locations...............................
FIGURE 22:
C&A Building HP Room Ceiling: Measurement 38 and Sampling Locations............................
FIGURE 23:
C&A Building Toilet Room: Measurement 39 and Sampling Locations............................
FIGURE 24:
C&A Building Southwest Stairway: Measurement 40 and Sampling Locations............................
l FIGURE 25:
C&A Building Southwest Stairway Stairs:
41 Measurement and Sampling locations..................
1 FIGURE 26:
C&A Building HP Corridor: Measurement and 42 Sampling Locations...............................
FIGURE 27:
C&A Building First Floor Corridor: Measurement 43 and Sampling Locations...........................
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l LIST OF FIGURES (Con't)
PAGE l
FIGURE 41:
C&A Building Instrument Repair Shop Ceiling:
57 Measurement and Sampling 1.ocations..................
l FIGURE 42:
C&A Building Decon Room: Measurement nnd 58 l
Sampling Locations...............................
FIGURE 43:
C&A Building Decon Room Ceiling: Measurement 59 l
and Sampling 1.ocations............................
FIGURE 44:
C&A Building Sampling Room: Measurement and 60 i
Sampling Locations...............................
FIGURE 45:
C&A Building Charging System Pump Room:
61
}
Measurement and Sampling Locations............
o FIGURE 46:
C&A Building Service Equipment Room 62 (2nd Floor): Measurement and Sampling Locations.........
FIGURE 47:
C&A Building Service Equipment Room (2nd Floor) Ceiling: Measurement and 63 Sampling Locations..................
FIGURE 48:
C&A Building Second Floor Control Room:
64 Measurement and Sampling Locations..................
FIGURE 49:
C&A Building Second Floor Control Room Ceiling:
65 Measurement and Sampling Lc:ations..................
r FIGURE 50:
C&A Building Second Floor Chem Prep Lab:
66 Measurement and Sampling locations..................
FIGURE 51:
C&A Building Second Floor Chem Prep 1.ab Ceiling:
67 Measurement and Sampling Locations..................
i FIGURE 52:
C&A Building Second Floor Control Room Vestibule:
68 Measurement and Sampling Locations..................
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I LIST OF FIGURES (Con't)
PAGE I
FIGURE 53:
C&A Building Second Floor Control Room Vestibule 69 l
Ceiling: Measurement and Sampling Locations.............
FIGURE 54:
C&A Building Second Floor Count Lab: Measurement 70 l
and Sampling Locations............................
FIGURE 55:
C&A Building Second Floor Count Lab Ceiling:
71 Measurement and Sampling Locations..................
l FIGURE 56:
C&A Building Roof and Outside Walls: Measurement 72 I
and Sampling Locations............................
FIGURE 57:
C&A Pipe Tunnel: Measurement and Sampling 73 g
Locations.....................................
FIGURE 58:
RWDF Building Discharge Tank Pad: Measurement 74 and Sampling Locations............................
FIGURE 59:
RWDF Building Scale and Storage: Measurement 75 and Sampling Locations............................
j FIGURE 60:
RWDF Building Scale and Storage Ceiling:
76 Measurement and Sampling Locations..................
I FIGURE 61:
RWDF Building Scale and Storage Stairway:
77 Measurement and Sampling Locations..................
FIGURE 62:
RWDF Building Control Room: Measurement 78 and Sampling Locations............................
l FIGURE 63:
RWDF Building Control Room Ceiling: Measurement 79 and Sampling beations............................
FIGURE 64:
RWDF Building Northeast Lower Stairway:
80 Measurement and Sampling Locations..................
FIGURE 65:
RWDF Building Northeast Lower Stairway Ceiling:
81 Measurement and Sampling Locations..................
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I LIST OF FIGURES (Con't)
PAGE I
FIGURE 66:
RWDF Building Evaporator Room: Measurement f-and Sampling Locations............................
82 l
FIGURE 67:
R%DF Building Evaporator Room Ceiling:
Measurement and Sampling Locations..................
83 FIGURE 68:
RWDF Building Evaporator Balcony: Measurement and Sampling Locations............................
84 i
l FIGURE 69:
RWDF Building Evaporator Balcony Ceiling Measurement and Sampling Locations..................
85 FIGURE 70:
RWDF Building South Stairway: Measurement and Sa mpling Locations...............................
86 FIGURE 71:
RWDF Building South Stairway Ceiling: Measurement and Sampling Locations............................
87 FIGURE 72:
RWDF Building Drum Shipping Room: Measurement and Sampling Lo:U i o ns............................
SS FIGURE 73:
RWDF Building Drum Shipping Room Ceiling:
Measurement and Sampling Locations..................
89 FIGURE 74:
RWDF Building Compressor Room: Measurement and Sampling Locations...............................
90 FIGURE 75:
RWDF Building Compressor Room Ceiling: Measurement and Sampling Locations............................
91 FIGURE 76:
RWDF Building Northeast Upper Stairway:
Measurement and Sampling Locations..................
92 FIGURE 77:
RWDF Building Northeast Upper Stairway Ceiling: Measurement and Sampling Locations.............
93 FIGURE 78:
RWDF Building Sump Room: Measurement and 94 Sampling Locations...............................
sii i
. - -. ~....~..
I.
LIST OF FIGURES (Con't)
PAGE t
FIGURE 79: -RWDF Building Sump Room Ceiling: Measurement 95 and Sampling Locations............................
l FIGURE 80:
RWDF Building Roof and Outside Walls: Measurement 96 and Sampling Locations............................
i FIGURE 81:
RWDF Building Shield Wall: Measurement and 97 i
Sampling Locations................... -............
98 FIGURE 82: ' RWDF Pipe Tunnel: Measurement and Sampling Locations...
FIGURE 83:
RWDF Pipe Tunnel Ceiling: Measurement and.
99 Sampling Locations...............................
}i, FIGURE 84:- Refueling Water Storage Tank Pad: Measurement 100 and Sampling Locations............................
FIGURE 85:
RWDF Pipe Tunnel Roof: Measurement and 101 Sampling Locations...............................
102 FIGURE 86:
Saxton Site Plan: Soil Sampling Locations................
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LIST OF TABLES mz t
TABE 1:
Background Radiation Levels and Baseline l
103 Radionuclide Concentrations in Soil....................
104 TABLE 2:
Summary of Surface Activity Measurements..............
l TABLE 3:
Summary of Uranium and Cesium Concentrations 119 I
in Interior Surface Soil Samples.......................
TABLE 4:
Summary of Plutonium and Strontium Concentrations in 122 I
in*:rior Surface Soil Samples........................
123 TABLE 5:
Summary of Radionuclide Concentrations in Concrete.......
124 TABLE 6:
Summary of Radionuclide Concentrations in Paint..........
l 3
TABLE 7:
Summary of Uranium and Cesium Concentrations in 125 Exterior Surface Soil Samples........................
i TABLE 8:
Summary of Radionuclide Concentrations in 127 S e d im e n t......................................
128 TABLE 9:
Summary of Uranium Concentrations in Roof Samples.......
ix
I CONFIRMATORY RADIOLOGICAL SURVEY FOR PORTIONS OF THE SAXTON NUCLEAR EXPERIMENTAL FACILTIY SAXTON, PENNSYLVANIA l
i INTRODUCTION i
The Saxton Nuclear Experimental Facility is a deactivated, 20 megawatt thermal, pressurized water reactor located in Saxton, PA. The facility is owned by the Saxton Nuclear Experimental Corporation and is maintained by GPU Nuclear Corporation (GPU).
Saxton Nuclear Experimental Corporation (SNEC) was formed for the purpose of conducting research and experimental programs invoMng the construction, operation, and maintenance of a nuclear test facility. The Saxton Nuclear Experimental Facility (Saxton Facility) was constructed during the period of 1960 to 1962. Initial criticality was achieved on April 13,1962 and final shutdown was completed on May 1,1972. The Saxton Facility was connected to the Pennsylvania-New Jersey-Maryland grid and produced 96,000 megawatt hours of commercial electrical power as a byproduct of its operation.
The Saxton Facility was also used as a research and training reactor. The facility was a testing ground for many concepts and procedures currently in use in the nuclear power industry, such as the use of mixed oxide fuels, development of reactivity coefficients, and development of rod control designs. The Saxton Facility also provided training and operating experience for operations, maintenance, health physics, chemistry, and engineering personnel.
The fuel was removed in 1972 and shipped to the Atomic Energy Commission facility at Savannah River, SC. The buildings and structures that supported reactor operations were partially decontaminated in 1972 through 1974. At that time complete decontamination of the support facilities was not deemed practical, due to residual contamination in the concrete floors and walls of the buildings.
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In 1987, radiological clearacterization surveys were performed by SNEC to determine the extent of decontamination necessary to meet the current U.S. Nuclear Regulatory
.I Commission (NRC) guidelines.
The primary contaminant identified was cesium-137.
Smaller concentrations of cobalt-60 and strontium 90 were also detected. Decontamination l
i activities of the reactor support facilities were conducted through 1988 by SNEC.
i Final release surveys of the reactor support facilities were performed from October 1988 through June 1989 by SNEC and GPU. The survey findings indicated the residual contamination was below the NRC guidelines. However, several inaccessible areas were identified during the final release survey; these included drain pipes, wall penetrations, areas beneath wooden support structures, and areas under groundwater collection pipes.
These areas are identified in the fint.1 release survey (Reference 1) as demolition hold points and will be surveyed during dismantlement and demolition.
The NRC Region I Office requested the Emironmental Survey and Site Assessment Program (ESSAP) of Oak Ridge Associated Universities (ORAU) to conduct a survey of the Control and Au :iliary (C&A) Building, Radioactive Waste Disposal Facility (RWDF)
Building, the C&A Pipe Tunnel, the RWDF Pipe Tunnel, and the Refueling Water Storage Tank (RWST) Pad to confirm that the facility meets the guidelines established for decommissioning.
FACILITY DESCRIPTION The Saxton Facility is located in the Allegheny Mountains, half a kilometer north of the l
borough of Saxton in Liberty Township, Bedford County (Figure 1 ). The site, within the 2
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security fence, contains the containment vessel, reactor operation support buildings, the pipe tunneis, the filled drum storage area, and the facility yard. The support structures or buildings addressed in this survey include the C&A Building, RWDF Building, RWST Pad, C&A Pipe Tunnel, and RWDF Pipe Tunnel. Figure 2 presents the site plan within the security fence.
I The C&A Building, a two story building constructed of block and reinforced concrete, houses the control room, electrical equipment, makeup and purification system components, chemistry and counting labs, and support functions such as locker rooms, office space, etc. (Figures 3 and 4). Surface areas (wall and floor) throughout the building
)
were heavily scabbled and portions of the floors were removed in the Charging System l
Pump and Auxiliary Equipment rooms to expose the soil.
l The RWDF Building, a one story above grade building with a basement area below grade, was used as an accessory processing center and accommodated most of the radioactive effluent from the reactor plant (Figures 5 and 6). The RWDF Building required the most i
extensive decontamination effort. Most surfaces (floors, walls, and ceilings) were heavily scabbled and large sections of ' a floor and walls were removed.
i The RWST Pad held
.,120 liter Refuciing Water Storage Tank, which stored borated water used in refue* r activities. It was part of the safety injection system to supply s
borated water to the main coolant system in the event of a loss of coolant accident. The tank was dismantled by Quadrex and shipped to their facility for decontamination and disposition. The concrete pad of the RWST remains intact.
The Containment Vessel, C&A Building, and RWDF Building are connected by a pipe tunnel, which housed piping runs between the structures. The two sections of the pipe 3
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tunnel addressed in this su.vey are the C&A Pipe Tunnel and the RWDF Pipe Tunnel (Figure 2). The C&A Pipe Tunnel is approximately 1.5 meters wide,11 meters long, and j
2 meters high. The RWDF Pipe Tunnel is approximately 2 meters wide,37 meters long i
1 and 2 meters high. Both tunnels required extensive decontamination.
PROCEDURES l
1
(
During the period of October 14-26, 1990, the Environmental Survey and Site Assessment Program of ORAU conducted an independent radiological survey of the C&A Building, RWDF Building, RWST Pad, and the C&A and RWDF Pipe Tunnels. The survey was l
performed in accordance with a plan developed by ORAU and submitted to the NRC.
Objective l
The objective of the survey was to provide sufficient data to evaluate the radiological l
condition of the facility and to conf-m that decontamination and decommissioning efforts by GPU were effective in meeting the NRC guidelines for unrestricted use (Reference 2).
I Disument Review i
As part of the confirmatory activities, ORAU reviewed the survey report and other supporting documentation prepared by GPU Nuclear Corporation for the Saxton Facility (Reference 1). Data and survey results presented in this report were compared to the established release guUelines.
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I Survey Procedures 1.
Background Measurement / Baseline Sampling One indoor and eight outdw-background locations were selected in the vicinity of the plant (Figure 7). A pressurized ion chamber (PIC) was used to measure exposure rates one meter above the surface at each location. Surface soil samples were taken at each of the eight outdoor locations.
l 2.
Gridding Detailed grid maps were provided to ESSAP by GPU prior to implementing smvey activities. A reference one meter grid system was established and used by GPU to l
perform their final survey. This grid system was re-established by GPU for use by ESSAP in performing the confirmatory survey.
3.
Surface Scans I
t Surface scans were performed on accessible indoor and outdoor structure / building I
Gamma scans were performed using Nal(TI) gamma scintillation surface areas.
2 detectors.
Thin window beta-gamma GM detectors and 100 cm gas flow proportional detectors were used to scan all accessible surfaces. Where possible, a large. area gas proportional floor monitor was used to scan floors for residual p
alpha plus beta activity. All detectors were coupled to ratemeters/ scalers with audible indicators.
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l 4.
Exposure Rate Measurements f
I Gamma radiation exposure rate measurements were performed at the surface (contact) and,)at one meter above the surface at various locations within and around the C&A Building, RWDF Building, RWST Pad, and C&A and RWDF i
Pipe Tunnels (Figures 8-14). Measurements were performed using Nal(TI) gamma scintillation detectors coupled to ratemeters and cross-calibrated with a PIC.
5.
Measurement and Surface Activity Levels Measurements ta determine surface activity levels in each area were performed in approximately 10% of the gridblocks, randomly selected using a random number generator (Figures 15 85). Measurements were performed at the center and at four points equidistant from the center and grid tiock corners (5 point measurements) in accordance with guidance established in NUREG/CR-2082 (Reference 3).
Large area gas proportional detectors were used to perform direct measurements for alpha and alpha plus beta activity. Single-point measurements were performed on upper walls, staircases, and accessihte ceilings. Smear samples for determining removable activity levels were call from each surveyed grid block at the location of the highest direct measurement, from each single point measurement location, and from various pipes, cracks, and crevices. If the surface to be smeared was too rough to maintain the integrity of the smear, then a concrete sample was collected in
.a of the smear.
6.
Soil Sampling Surface soil samples (depth 0-15 cm) were collected from sub-Door excavations within the C&A Building (Figures 15, 25, 29, 31, 33, 36, 39, 42, 44, and 45) and RWDF Building (Figure 59).
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l The outdoor soil is to be addressed by OpU in a later phase of decommissioning.
However, soil samples were also collected from several outdoor locations within three feet of the support buildings and structures (Figure S6), since the licensee expects to raze these facilities upon the completion of decontamination and I
decommissioning activities. Hence, information on the residual soil contamination present is needed so the licensee can control aethities in the building soil interface, as required, to ensure that any residual contamination is not spread.
7.
Miscellaneous Samples Concrete samp!es were obtained in lieu of smears from surfaces that had been heavily scabbled within the C&A Pipe Tunnel (Figure 57), the RWDF Building (Figures 66, 74, end 78), and the RWDF Pipe Tunnel (Figure 82). One bias I
concrete sample was obtained from the outdoor surface (roof) of the RWDF Pipe Tunnri (Figure 8$) at a location of slightly elevated direct radiation identified by the ice scans.
I Paint samples were collected from interior surfaces in the C&A Building (Figures 31 i
1 ar.d 36) End RWDF Building (Figures 62,66,69,70, and 72). Paint samples were also obtained from the exterior walls of the C&A Building (Figure 56).
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Samples were also collected trom the roofs of the C&A and RWDF Buildings i
1 (Figures 56 and 80).
Sediment samples were obtained upstream and downstre.im of the outfall for the plant.
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Samole Analysis and Data Interpretation I
Smears for removable contamination were analyzed for gross alpha and gross beta actWity.
Soil samples, roof samples, and sediment samples were analyzed by solid state gamma spectroscopy. Radionuclides of primary interest were U.235, U 238, Co-60 and Cs.137.
However, spectra were also reviewed for other identifiable photopeaks.
Several soil, concrete, paint and sediment samples were chosen from various locations and q
analyzed by alpha spectroscopy for plutonium.
Several paint samples and sediment samples were also analyzed for Sr 90. Strontium analysis was also performed on composite j
l samples of soil and composite samples of concrete. The composites consisted of aliquots f
l from three to five indMdual samples.
Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and 13.
Results of the independent measurements were compared to the NRC guidelines (Appendix C).
FINDINGS AND RESULTS Document Review The documentation provided by GPU was thorough and adequately described the 1
final radiological status of the site. Radiological data demonstrated that the residual activity levels satisfied the established decommissioning guidelines.
S I
IndependenLSP.nII Background Measurement / Baseline Sampling l
Background exposure rates and baseline soil concentrations within the vicinity of the l
Saxton Facility are presented in Table 1. Background exposure rates at one meter from the surface ranged from 9 pR/h to 13 pR/h and averaged 10 pR/h.
I Radionuclide concentrations in baseline soll samples are typical of concentrations normally occurring in the emironment. The Co 60 concentrations were <0.3 pCilg. Uranium 1f concentrations for U 235 ranged from 0.1 to 0.2 pCilg and for U 238 f anged from 1.2 to 3.5 pCi/g. The Cs 137 concentration ranged from <0.1 to 0.9 pC1/g.
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Interior Survey 1.
Surface Scans Surface scans for gamma, beta gamma and alpha plus beta activity of the walls,
~
Doors, and ceilings of the support facilities did not identify any areas of elevated contact radiation.
I 2.
Exposure Rate Measurements Exposure rate measurements at 1 meter above the surface ranged from 8 to 9 pR/h in the C&A Building, from 6 to 11 gR/h in the RWDF building, and from 9 to 10 pR/h in the C&A and RWDF Pipe Tunnels. These levels are consistent with the background average of 10 R/h.
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l 3.
Surface Acthity Levels The results of total (direct) and removable surface activity measurements are summarized in Table 2. Total activity measurements for alpha aethity ranged from 9
3 r
<39 to 120 dpm/100 cm and from <380 to 3600 dpm/100 cm for alpha plus beta I
r acthity. The highest alpha activity was 120 dpm/100 cm. detected on the wall of the C&A Pipe Tunnel. The highest alpha plus beta aethity was 3600 dpm/100 cm located on the wall of the Northeast Stair in the RWDF Building.
2 Measurements for removable activity were s6 dpm/100 cm for alpha activity and 2
ranged from <13 to 28 dpm/100 cm for beta activity.
4.
Radionuclide Concentrations in Soil Samples The radionuclide concentrations determined for soil samples are presented in Tables 3 and 4. The highes concentrations were detected in the samples obtained from the C&A Building. The highest concentrations were 0.3 pCi/g for U 235, 2.9 pCi/g for U-238,10 pCi/g for Cs 137, <0.08 pCi/g for Pu 238, <0.1 pCilg for Pu 239/240, and <0.2 pCi/g for Sr 90. Concentrations of Co-60 ranged from <0.1 to 0.3 pCi/g.
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l 5.
Radionuclide Concentrations in Miscellaneous Samples Radionuclide concentrations in concrete samples are summarized in Table 5.
Three samples were analyzed by alpha spectroscopy for plutonium and the highest concentration measured was <0.1 pCi/g for Pu 238 and <0.09 pCi/g for Pu 239/240.
Four composite samples, each consisting of aliquots from five indhidual samples, were analyzed fot St-90. The highest concentration of St 90 was <0.4 pCilg.
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The radionuclide concentrations determined for paint samples are presented in Table 6. Two paint samples were analyzed for plutonium by alpha spectrometry and four were analyzed for St 90. The highest concentration for Pu 238 was 2
<3.2 pCi/100 cm in the C&A Building, for Pu-239/40 was <0.6 pCi/100 cm in 3
the C&A Building, and for Sr 90 was <2.5 pCi/100 cm in the RWDF Building.
2 Exterior Survey i
1.
Surface Scans l
Surface scans for gamma, beta gamma, and alpha plus beta activity of the exterior
}
walls and roofs of the C&A and RWDF Buildings, and the RWST Pad did not However, surface scans of the identify any areas of elevated contact radiation.
roof of the RWDF Tunnel identified one area of slightly clevated direct beta-gamma radiation levels. A concrete sample was obtained from this location, i
2.
Exposure Rate Measurements Exposure rate measurements were performed at 1 meter above the surface at locations adjacent to the C&A and RWDF Buildings and the RWST Pad.
Exposure rates measured adjacent to the C&A Building averaged 10 pR/h, aroun the RWDF Building averaged 11 pR/h, and near the RWST Pad averaged 13 pR/h.
These results are similar to the background exposure rate measurements which ranged from 9 to 13 pR/h and averaged 10 pR/h.
3.
Surface Activity Levels A random number generator was used to select approximately 10% of the grid blocks on the roofs of the C&A and RWDF Buildings, and the RWST Pad to be 11 l
I surveyed. The results of total and removable surface activity measurements are summarized in Table 2.
p The highest total aethity measurements for alpha plus beta activity were
<880 dpm/100 cm for the roofs of the C&A and RWDF Buildings, and 2
7700 dpm/100 cm for the RWST Pad. The highest total activity averge for alpha 2
i 2
plus beta activity at the RWST Pad was 5014 dpm/100 cm.
2 All measurements for removable aethity were <6 dpm/100 cm for alpha activity 2
and <13 dpm/100 cm for beta aethity.
Alpha plus beta surface actMty measurements were also performed on the roof of the RWDF Tunnel at the location of elevated direct radiation levels. The total 2
alpha plus beta activity was 3360 dpm/100 cm.
4.
Radionuclide Concentrations in Soil Samples i
The soil outside of the facilities being surveyed is to be addressed by GPU during a later phase of decommissioning. However, at the request of the NRC and in order to determine the concentration of radionuclides in soil adj..eut to the facilities being surveyed, mil samples were collect.d adjacent to the C&A Building, the RWDF Building, the RWDF Pipe Tunnel and the RWST Pad. Radionuclide concentrations aie summarized in Table 7.
The highest concentrations were 0.6 pCi/g for U 235 beside the C&A Buildi.ng,5.1 pCi/g for U 238 adjacent to the RWDF Building, and 100 pCi/g for Cs 137 beside the RWDF Building. The concentrations of Co-60 ranged from <0.1 to 2.1 pCi/g.
l l
12
I l
5.
Radionuclide Concentrations in Miscellaneous Samples The radionuclide concentrations determined for paint samples are presented in Table 6.
The highest concentrations in exterior paint samples were g
8 8
2
<0.4 pCi/100 cm for Pu 238,0.4 pCi/100 cm for U 238, and <2.4 pCi/100 cm for g
Sr 90.
l Table 8 summarizes the results of sediment samples obtained upstream and downstream of the plant outfall. The highest concentrations in sediment samples l
I I
were 0.9 pCi/g of U 235,2.1 pCi/g of U 238, <0.1 pCi/g of Pu 238, <0.07 pCi/g of Pu 239/240, and <0.2 pCi/g of St 90. Co 60 concentrations were <0.2 pCi/g and l.
Cs 137 concentrations ranged from 0.2 to 0.3 pCi/g.
Table 9 summarizes the results of samples obtained from the roofs of the C&A and i
RWDF Buildings.
The highest concentrations were 1.0 pCi/g for U 235 and 6.1 pCi/g for U 238 in samples from the C&A Building roof. Co-60 concentrations were <0.5 pCi/g and Cs 137 concentrations ranged from 0.1 to 4.2 pCi/g.
One bias concrete sample was obtained from the roof of the RWDF Pipe Tunnel l.
at a location of elevated direct radiation levels identifled by the surface scans. The concentrations of uranium in this sample were 0.3 pCi/g for U 235 and <4.0 pCi/g I
for U 238. The Cs 137 concentration was 8.9 pCi/g and the Co 60 concentration was <0.3 pCi/g.
COMPARISON OF RESULTS MTITI GUIDELINES Surface actMty guidelines for the release of formerly licensed facilities for unrestricted use are presented in Appendix C, as well as the guidelines for reddual concentrations of 13
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I thorium and uranium wastes in soll, and additional concentration guidelines for other radionuclides. The primary contaminant of concern identified for this site was cesium 137.
i The guidelines for surface activity for this contaminant are:
2 2
g 15,000 beta gamma dpm/100 cm (maximum in a 100 cm area) 2 2
5,000 beta gamma dpm/100 cm (average over a 1 m area) 2 g
1,000 beta-gamma dpm/100 cm (removable) j-All alpha beta total activity measurements were less than the maximum guideline values of 15,000 dpm/100 cm and all areas surveyed, with one exception, were well below the 2
j average guideline of 5,000 dpm/100 cm. The RWST Pad contained one grid block that 2
averaged 5014 dpm/100 cm alpha plus beta, which barely exceeds the guideline value of 2
-(
500u dpm/100 cm. All other grid blocks of the RWST Pad exhibited lower total surface 2
activity.
Removable activity measurements were well below the guideline value of l
~ 1,000 dpm/100 cm for beta gamma activity. - All alpha activity measurements, total and 2
removable, were well below the applicable guideline values of:
d 2
2 15,000 alpha dpm/100 cm (maximum in a 100 cm area)
- b 2
2 5,000 alpha' dpm/100 cm (average over a 1 m area) 2 1,000 alpha dpm/100 cm (remnvable)
Exposure rates within the facilities ranged from 8 to 10 pR/h. This is consistent with the i
range of background measurements, which averaged 10 pR/h.
Specific soil concentration guidelines have not been developed for this site. However, based on the NRC's Branch Technical Position on " Disposal or Onsite Storage of Thorium 14 1
I
.., ~
_..__a_,-._.
I and Uranium. Wastes from Past Operations" (Appendix C) and NRC cndorsement of concentration guidelines for other radionuclides at other NRC sites, the following guidelines may be used for comparison with the results:
1 Depleted Uranium 35 pCVg Enriched Uranium 30 pCi/g Thorium (Natural) 10 pCi/g Co-60 8 pCi/g g
Cs 137 15 pCi/g l
St 90 1,800 pCi/g i
l The results of interior soil samples demonstrate that the guidelines were met. However, many of the soil samples collected outdoors adjacent to the buildings and structures did l_
not meet the Cs-137 concentration guideline value.
SUMMARY
At the request of the Nuclear Regulatory Commission, Region I, the Emironmental Survey and Site Assessment Program of Oak Ridge Associated Universities conducted an
'I independent radiological survey of the Saxton-Nuclear Experimental -Facility from October 15 through October 26,1990. The survey included surface alpha, alpha plus beta, I
beta gamma, and gamma scans; measurement of direct snd removable contamination lev is: axposure rate measurements; and determination of radionuclide concentrations in
'I soil, sediment, concrete, paint, and roof material samples.
- i Initial measurements identified only one area of residual activity exceeding the
-- l ;
guideline levels; This was one grid block at the RWST pad; the remainder of the RWST Pad had much lower total surface activity levels.- Additionally, the Cs 137 concentrations
.l-15 L
i-l
... - =
1 i
in many outdoor soi! samples adjacent to the buildings and structures exceeded the guideline values for Cs.137. The results of the confirmatory survey support the findings l
of the final survey performed by GPU Nuclear Corporation, hnd in ORAU's opinion, confirm that the decontamination efforts have been successful in satisfying the NRC I
guidelines for release for unrestricted use for the C&A Building, RWDF Building, and C&A and RWDF Pipe Tunnels of the Saxton Nuclear Experimental Facility; however, work to be performed involving the building soil interface will need further evaluation before proceeding. Additionally, the one grid block of the RWST Pad which exceeds the guideline value will require remediation and resuney.
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Saxton Nuclear Experimental Station 23
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Exposure Rote Measurement Locations 24 1
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Exposure Rate Measurement Locations 25
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Exposure Rote Measurement Locations 27 l
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Exposure Rote Measurement Locations I
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Exposure Rote Measurement Locations i
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Measurement and Sampling Locations i
31
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WETERS FIGURE 17: C&A Bu ' ding Switch Gear Room:
Measureinent and Sampling Locations 33
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Measurement and Sampling Locations 34 I
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FIGURE 19: C&A Building Battery Room:
Measurement and Sampling Locations 35
f
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Measurement and Sampling Locations i
36
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Measurement and Sampling Locations t
I 37
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Measurement and Sampling Locations i
38 l
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I FIGURE 23: C&A Building Toilet Room:
Measurement and Sampling Locations 39 i
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WETERS FIGURE 24: C&A Building Southwest Stairway:
Measurement and Sampling Locations 40
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FIGURE 25: C&A Building Southwest Stairway Stairs:
Measurement and Sampling Locations 41
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FIGURE 26: C&A Building HP Corridor:
Measurement and Sampling Locations 42 s
l
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FIGURE 27: C&A Building First Ficor Corridor:
Measurement and Sampling Locations 43 I
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t FIGURE 28: C&A Building First Floor Corridor Ceiling:
Measurement and Sampling Locations t
44 l
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METERS FIGURE 29: C&A Building Locker Room:
Measurement and Sampling Locations
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Mnasurement and Sampling Locations 46 I
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FIGURE 31: C&A Building Monitor Room:
c Measurement and Sampling Locations I
i 47 l
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Measurement and Sampling 1.ocations 1
48
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METERS FIGURE 33: C&A Building Toilet and Shower:
Measurement and Sampling Locations 49 h
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FIGURE 34: C&A Building Toilet and Shower Ceiling:
l Measurement and Sampling Locations 50
p l
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12 A smcLE-PO(NT wtTtR5 FIGURE 35: C&A Building North Stairway:
Measurement and Sampling Locations 51
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FIGURE 36: C&A Building Auxiliary Equipment Room:
Measurement and Sampling Locations 3
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Measurement and Sampling Locations i
53
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FIGURE 38: C&A Building Southeast Stairway:
Measurement and Sampling Locations 54
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Measurement and Sampling Locations 59
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FIGURE 45: C&A Building Charging System Pump Room:
Measurement and Sampling Locations 61 I
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l Measurement and Sompling Locations 63
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FIGURE 48: C&A Building Second Floor Control Room:
I Measurement and Sm.pling Locations 1
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F GURE 50: C&A Building Second Floor Chem Prep Lob:
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Measurement and Sampling Locations 67
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I FIGURE 54: C&A Building Second Floor Count Lob:
Measurement and Sampling Locations 70 t
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Measurement and Sampling Locations 71
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1 Measurement and Sampling Locations I
72
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FIGURE 57: C&A Pipe Tunnel: Measurernent and Sampling Locations i
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FIGURE 58: RWDF Building Discharge Tank Pod:
Measurement and Sampling Locations 74
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FIGURE 59: RWDF Building Scale and Storage:
Measurement and Sampling Locations 75 1
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i FIGURE 60: RWDF Building Scale and Storage Ceiling:
Measurement and Sampling Locations 76
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l FIGURE 61: RWDF Building Scale and Storage Stairway:
Measurement and Sampling Locations 77 l
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I Measurement and Sampling Locations I
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FIGURE 63: RWDF Building Control Room Ceiling:
Measurement and Sampling Locations 79
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i FIGURE 64: RWDF Building Northeast Lower Stairway:
Measurement and Sarnpling Locations 80 i
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FIGURE 65: RWDF Building Northeast Lower Stairway Ceiling:
Measurement and Sampling Locations 81 1
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Measurement.and Sampling Locations 82 i
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l i
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i FIGURE 68: RWDF Building Evaporator Balcony:
Measurement and Sampling Locations i
l 84 1
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FIGURE 69: RWDF Building Evaporator Balcony Ceiling:
I Measurement and Sampling Locations 85 l
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FIGURE 70: RWDF Building South Stairway:
Measurernent and Sampling Locations 86 l
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Measurement and Sampling Locations 87
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Measurement and Sampling Locations 88 l-
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i FIGURE 73: RWDF Building Drum Shipping Room Ceiling:
Measurement and Sampling Locations i
89
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Measurement and_ Samping Locations l
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Measurement and Sampling Locations 91 i
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FIGURE 76: RWDF Building Northeast I arer Stairway:
Measurement and Sarnpliriy LOCOtions j
92 1
SAXS4 t
l l
1 4
0 1
2 zz A
B 7
c o
A 5 e
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i N
n j
i 4p MEASUREMENT AND SAMPLING LOCATIONS h
A SINGLE-POINT FEET g
37 l
l 4
6 uEas 4
l 1
i FIGURE 77: RWDF Building Northeast Upper Stairway Ceiling:
Measurement and Sampling Locations i
l 93 l
l
-SAX 51 l
O l 1 l 2 l 3 l 4 l 5 l 6 l 7 l 8 l 9 l10l11l12l13l14l15l16l17l18l19l20l 21l22)
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l MEASUREMENT AND SAMPLING LOCATIONS h
r I
FEET GRID BLOCK (5-POINT) 0 12 L
r A s:NGLE-POINT NETERS FIGURE 78: RWDF Building Sump Room:
Measurement and Sarnpling Locations 94 i
l
SAX 53 i
i O
1 2
3 4
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SURFACE REMOVED
-N Il h
MEASUREMENT AND l
SAMPUNG LOCATIONS ll A SINGLE-POINT FEET
_l-g METERS l-l l
Ll FIGURE 79: RWDF Building Sump Room Ceiling:
Measurement and Sampling Locations 95 l
L
SAX 47 f
i O I 11213 l 4 I s I 6 l 7 l 8 l 9 l10l11l12l13114l15l16l17l18]19l20l21l22j23l24l25l261 ZZ A
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MEASUREMENT AND SAMPLING LOCATIONS g
A SINGLE-POINT FEET g METERS t
FIGURE 80: RWDF Building Roof and Outside Walls:
l-Measurement and Sampling Locations 96
SAX 74 I
i s
0 1
2 3
4 5
6 7
a 9
10 11 ZZ Yh A
-}
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- NE r
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BELOW CROtlND LEVEL N
j i df' MEASUREMENT AND SAMPUNG LOCATIONS d
1 A SINGLE-POINT g
0 12 6
Ns
,i FIGURE 81: RWDF Building Shield Wall:
Measurement and Sampling Locations 97 I
i
SAX 63a
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l 112 l 31 l 4 l 5 l 6 l 7 l 8 l 9110111l12l13l14l15l16l17l18l19[20l21I22l23#4k546l27l28!29 Oj31h2 3h4 567 8 9l40l4 A
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i WALL OR FLOOR 4
l REMOVED SURFACE REMOVED N
h MEASUREMENT AND Wp SAMPLING LOCATIONS GRID BLOCK (5-POINT) g 0
12 4
WEERS y
li.
i i
FIGURE 82: RWDF Pipe Tunnel:
Measurement and Sampling Locations 98
SAXG4 l
l 1 l 2 l 3 l 4 l 5 l 6 { 7 l B l 9 l10111l12l13l14l15l16l17l18l19#0l21l22p3l24l25l26l27l2Bl29130131 2b3}34%5}36%7 8 914Dl T
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a CEluNG REMOVED SURFACE REMCNED N
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h MEASUREMENT AND SAMPUNG LOCATIONS d
A sNGLE-POINT g
A ucrtas I
FIGURE 83: RWDF Pipe Tunnel Ceiling:
Measurement and Sampling Locations 99 I
SAX 75 O
1 2
3 4
5 6
7 8
9 10 i
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FEET O
12 l
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f FIGURE 84: Refueling Water Storage Tank Pad:
Measurement and Sampling Locations l
100
.I i
p SAX 65 1
i f
f i
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h
- lb MEASUREMD4T AND SAMPLING LOCATIONS A SINGLE-POINT 4
ucitRS l
FIGURE 85: RWDF Pipe Tunnel Roof:
Measurement and Sampling Locations 101
-SAX 4b
- CHLORINATION PUMPHOUSE x
x x
M x
x X
X X
X X
x X
x SAFETY INJECTION X
REFUELING TANK PAD
,c k\\
!$l 9
33 g 1D k
12 6
i CONTAINMENT k
k x
TWO CONCRETE VESSEL
)<
BARRIER WALLS x
INSTALLED 7
/
26
( 33 g
X
- (
I O
n 6x RWDF PIPE TUNNEL CV PIPE TUNNEh_6 CONCRETE g1
- -C&A PIFZ TUNNEL BARRIER WALL-#J v
4 12 19 14 RAD. WASTE 5"
INSTALLED 4
(
DISPOSAL k
]k 25$
20 FACILITY g
x CONTROL AND AUX.
. 21 I
4 BUILDING 9
g15 g
22 A
+I
-k 24
$ 23 x
FILLED DRUM STORAGE AREA g
y
/
\\
x j_
x x
x x
x x
Af SOIL SAMPLING Y
LOCATIONS X
X M-FENCE N
h O
n 0
50
- =1 METERS 1
1 FIGURE 86: Saxton Site Plan:
l Soil Sampling Locctions i
102
TABLEI BACKGROUND RADIATION LEVELS AND BASELINE RADIONCULIDE CONCENTRATIONS IN SOIL SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA Exposure Rate (pR/h)
Radionuclide Concentration (oCi/e)
Location' at I m above Surface U-235 U-238 Cs-137 1
10 0.2 i 0.1*
1.9 i 1.0 0.6 i 0.1 f
2 13 0.2 i 0.1
< l.8 9.3 0.1 3
9 0.1 i 0.3 1.2 i 0.9 0.3 i 0.1 4
12 0.2 i 0.1 3.2 1 2.1 0.2 i 0.1 y
5 13 0.2 i 0.1 1.2 i 1.0 0.2 i 0.1 6
10 0.1 1 0.1 2.2 i 1.2 0.5 i 0.1 7
11 0.2 0.1 2.2 i 1.2
<0.1 8
10 0.2 i 0.2 3.5 1 2.2 0.9 i 0.I 9
10 (indoor)
N/A N/A N/A
' Refer to Figure 7.
' Uncertainties represent the 95% confidence level based only on counting statistics. Additional laboratory uncertainties of i 6 to 10% have not been propagated into these data.
t
_a_.
TABLE 2
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total Alpha-Total Alpha Plus Beta Removable 2
2 or dpm/100 cm dom /100 cm Contaminat*mn Meets 2
Location Figure Locations Ilighest Ilighest Ranee dpm/100 cm Guidelines?
Measured Average.
Range' Average Range Alpha Beta C&A Bldg.
Variable Freq. Ro: m 630 410- 9306
<6
< 13 Yes Floor 15.
2 lower Walls 15 4
460
<410- 660
<6
< 13 Yes Upper Walls
- 15 3
N/A
< 410
<6
< 13 Yes.
Ceilings
- 16 1
N/A
< 410
<6
< 13 Yes Switch Gear Room Floor
'17 5
770
< 390- 980
<6
< 13 Yes 410
< 390- 470
<6
< 13 Yes Lower Walls 17 8
N/A
< 390
<6
< 13 Yes Upper Walls
- 17 4
N/A
<:ns
<6
< 13 Yes-Ceilings
- 18 2
Battery Rm.
t 650
<430- 84b
<6
< 13 Yes Floor 19-1 Lower Walls 19 -
2
< 430
< 430
<6
< 13 Yes N/A.
<430 l
<6
< 13 Yes Upper Walls
- 19 -'
2 N/A
<430
<6
< 13 Yes Ceilings
- 20 1
TABLE 2 (Con't)
SUMMARY
.OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA.
- of Grids Total Alpha-Total Alpha Plus Beta Removable 2
2 or
' dom /100 cm dom /100 cm Contamination Meets 2
Location Figure Locations Ilighest '
Ifighest Ranee dom /100 cm Guidelines?.
Measured Average Range Average
-Range Alpha Beta IIP Room 600
' <420- 840
<6
< 13.
Yes Floor 21 2
< 420
<420 (6
< 13 Yes Le ver Walls
'21 3
Upper Walls
- 21 3
N/A
<420
<6
< 13 Yes N/A
< 420
<6
< l3 Yes 5
Ceilings
- 22 1
(I Beam)
Toilet Room Floor 23 1
< 480
< 480
<6
< 13 Yes lower Walls 23 2
900
< 480-1800
<6
< 13 Yes Southwest Stairs Floor 24,25 3
< 39
< 39 640 440- 830
<6
< 13 Yes Lower Walls 24 3
< 39
< 39
< 420
<420
<6
< 13 Yes Upper Walls 24-1
< 39
< 39
< 420
< 420
<6
< 13 Yes
~ ~.
m
-e..
m 9
TABLE 2 (Con 4)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA' i
l
- of Grids Total Alpha Total Alpha Plus Beta Removable or dDm/100 cm dom /100 cm Contamination Meets 2
2 2
Location Figure Locations
. liighest liighest
- Ranee doai/100 cm Guidelines?
Measured Average Range
. Average Range Alpha Beta -
l IIP Corridor Floor 26 1
610 540- 740
<6
< 13 Yes Lower Walls 26 1
400
< 380- 470
<6
< 13 Yes N/A
< 380
<6
< 13 Yes Upper Walls' 26 3
1st Floor y
Corridor 510
<420- 620
<6
< 13 Yes Floor 27
'2 Lower Walls 27 4
< 420
<420
<6
< 13 Yes Upper Walls
- 27 2
N/A
< 4?0
<6
< 13 Yes Ceilings
- 28 1
N/A 430
<6
< 13 Yes (I Beam)
Locker Rm.
Floor 29 6
1800
< 450-3500
<6
< 13 Yes Lower Walls 29 6
< 450
< 450
<6
< 13 Yes Upper Walls' 29 4
N/A
< 450
<6
< 13 Yes Ceilings * -
30 2
N/A
<450
<6
< 13 Yes
.-m.%
m.m.,
.m m
m ww.a*+
p+-
,~n, em TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total Alpha Total Alpbs Plus Beta' Removable 2
2
.or' dDm/100 cm dom /100 cm Contamination Meets 2
Location Figure Locations Ifighest liighest.
Ranne dom /100 cm Gukielines?
Measured Average Range Aversge Range Alpha Beta Monitor Rm Floor 31 2
1500 710-2900
<6
< 13 Yes
< 410
<410
<6
< 13 Yes Lower Walls -
31 3
Upper Walls
- 31 2
N/A
< 410
<6
< 13 Yes N/A
< 410
<6
< 13 Yes g1
' Ceilings
- 37 1
Tollet &.
Shower Floor 33.
2 1100
< 500-1500
<6
< l3 Yes Imwer Walls 33 2
640
<500- 780
<6
< 13 Yes Upper Walls
- 33 2
N/A
< 500
<6
< 13 Yes N/A
< 500
<6
< 13 Yes I
Ceilings
- 34 (I Beam)
North Stairs 710 600- 870
<6
< 13 Yes Floor 35 1
Lower Walls 35 3
<440
< 440
<6
< 13 Yes Upper Walls' 35 3
N/A'
< 440
<6
< 13 Yes
1 TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMEN'IS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total' Alpha Total Alpha Plus Beta Renovable 2
2 or dom /100 cm dom /100 cm Contam*mation Meets Location Figure IAcations liighest liighest Ranae dom /100 cm' Guidelines?
Measured z Average Range Average '
Range Alpha Beta Aux. Equip.
Room Floor 36' 12
<40
< 40 1400
<450-2100
<6
< 13.
Yes Lower Walls 36 7-
< 40
< 40 580
< 450- 790
<6
< 13 Yes 5
Upper WalIs*
36 5
N/A
< 40 N/A
< 450- 870
<6
< 13 Yes Ceilings
- 37 2-N/A
< 40 N/A
< 450
<6
< 13 Yes Southeast Stains Floor 38 2
< 39
< 39 630
<430 - 930
<6
< 13 Yes Imwer Walls 38 2
<39
< 39
< 430
<430
<6
< 13 -
Yes T
I Upper Walls' 38 2
.'N/A
< 39 N/A
< 430
<6
< 13 Yes i
Janitor Closet Floor 39 1
550
<410- 660
<6
< 13 Yes Lower Walls 39 3
420
< 410- 470
<6
< 13 Yes Upper Walls
- 39 1
N/A
<410
<6
< 13 Yes u
c
m s
..--ww
.a mi. W
_r l
TAQLE 2 (Con t);
i
SUMMARY
0F SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY
. SAX 1DN, PENNSYLVANIA i-i.
- of Grids Total Alpha -
Total Alpha Plus Beta.
Rernovable 2
2 l
or L.
dem/100 cm -
dom /100 cm Contamination
' Meets -
2
' Location '
Figure Locations Highest '
Highest -
_B_a_ngs dom /100 cm -
Guidelines? -
Measured Average-Range Average Range Alpha Bets Instrument Repair Shop
,a Floor 40 1
< 57
<57 860-533-1100-
<6
< 13 Yes.
Lower Walls 40.
-4
. < 57..
< 57 460
<430-577
<6
< 13 Yes Upper Walls
- 40 1
N/A
< 57 N/A
<430
<6
< 13 Yes g
Ceilings
- 41 1
N/A
< 57 N/A 440
<6
< 13 Yes Decon Room Lower Walls 42 3-1100
<410-1800
<6
< 13 Yes N/A' 430
<6
< 13 Yes f
Upper Wallt 42
'1 Ceilings' 43 1
N/A
< 410
<6
< 13' Yes (I Beam)
Sampling Room j
790
<460-1300
<6
< 13 Yes j
Lower Walls 44 2
?
I
+
1 L
1
=
---me-
_~
TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON,PENNSYLVANLA
- of Grids Total Alpha Total Alpha Plus Beta Removable h
dom /100 cm dom /100 cm Contamination Meets 2
2 or Location Figure Locations Ifighest Ilighest Range dom /100 cm Guidelines?
Measured Average Range Avenge Range Alpha Beta Charging System Pump Room Lower Walls 45 6
< 60
< 60 710
< 490-1600
<6
< 13 Yes Upper Walls
- 45 1
N/A
< 60 N/A
< 490 6
< 13 Yes Service Equip. Rm l
I.
Floor 46 2
490
<420- 630
<6
< 13 Yes 1
o i
I
< 420
< 420
<6
< 13 Yes Lower Walls 46 3
Upper Walls' 46 2
N/A
< 410
<6
< 13 Yes Ceilings
- 47 1
N/A
< 410
<6
< 13 Yes Control Room 700
<415-780
<6
< 13 Yes Floor 48 13 420
< 400- 480
<6
< 13 Yes Lower Walls 48 10 Upper Walls
- 48 3
N/A
< 400
<6
< 13 Yes N/A
< 400
<6
< 13 Yes Ceilings
- 49 2 (I Beam
& Pipe)
.=~
.~
TABLE 2 (Con t)-
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS
. SAXTON NUCLEAR EXPERIMENTAL FACILITY l
SAXTON, PENNSYLVANIA l
- of Grids Total Alpha Total Alpha Plus Beta Removable 2
2 or-
'dmn/100 cm dom /100 cm Contamination Meets 2
Location Figure Locations Highest:
Ilighest Renee dmn/100 cm Guidelines?
Measured Average Range Average Range Alpha Beta Chem Prep l
Isb Floor 50 3
< 40
< 40 730-460- 880
<6
< l3 Yes Iower Walls 50 6
<40
< 40 450
<420- 560
<6
< 13 Yes Upper Walls
- 50 2
N/A
<40 N/A
< 420
<6
< 13 Yes
{
Ceilings
- 51 1
N/A
< 40 N/A
< 420
<6
< l3 Yes Control Room Vestibule 600
<400- 980
<6
< 13 Yes Floor 52 1
560
< 400-1210
<6
< 13 Yes lower Walls 52 2
Upper Walls' 52 1
N/A
<400
<6
< 13 Yes Ceilings
- 53 1
N/A
< 400
<6
< 13 Yes
-(I Beam)
P
M j M Mr WD MW.. m
'M.-'*M eMP TABLE 2 (Con't)-
SUMMARY
OI' SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY
. SAXTON, PENNSYLVANIA
- of Grids
. Total Alpha '
Total Alpha Plus Beta
. Removable or dom /100 cm dom /100 cm Contamination Meets 2
2 2
Location Figu m Locations :
Ifighest Ilighest Ranee dom /100 cm Guidelines?
Measured Average Range Average Range Alpha Beta Count Lib Floor 54 4-900
< 420-1000 '
<6-
< 13 Yes Imwer Walls.
54 3
t < 420
< 420
<6
< 13 -
Yes Upper Walls
- 54 2.
N/A
< 400
<6
< 13 Yes O
Ceilings
- 55 1
N/A
< 400
<6
< 13 Yes u
Roof Yt.:
Roof 56 12 N/A-
< 880 Tunnel Floors 57 1
< 40
< 40 1300
<520-2100
<6
< 13 Yes l
Walls 57 5
62
< 40-120 1600
< 520-2700
<6
< 13 Yes i
l l
TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total Alpha-Total Alpha Plus Reta Removable 2
2 or dom /100 cm iom/100 cm Contamination _
Meets 2
Location -
Figure.. - Locations Ilighest -
Ilighest Rance dom /100 cm Guidelines?
l
[ Measured
. Average.
Rartge
' Average '
Range Alpha '
Beta RWDF l
Discharge Tank Pad 1
Floor 58 3
69
< 66-30 970
< 940- 970
<6
< 13 Yes Walls 58 1
71'
. < 66-89
< 940
< 940
<6
< 13 Yes Scale &
C Storage Floor 59 2
< 40
'<40 1100 560-1800 i
<6
< 13 Yes l_ower Walls 59 6-
< 40 -
< 40 1100
<430-1900
<6
< 13 Yes
_ Upoer Walls' 59 3
N/A
< 4(I N/A
<430
<6
< 13 Yes dedings*
60 2
N/A
< 40 N/A
< 430'
<6
< !3 Yes Scale &
Storage Stairs Floors
- C1 2
N/A
< 50 N/A
<500
<6
< 13 Yes Upper Wa s' 61 3
N/A
< 50 N/A
<500
<6
< 13 Yes i
TABLE 2 (Con't) L-
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERtMENTAL FACILITY
- SAX 1DN, PENNSYLVANIA -
- of Grids
. Total Alpha ~
Total Alpha Plus Beta
. Removable 2
2 or-dom /100 cm =
dom /100 cm Contaminatioin Meets 2
Lreation Figure Locations II!ghest
- Ilighest.
Ranee dom /100 c.u Guidelines?
Measured Average -
Range Average Range Alpha Beta Control Ro6m Floor 62 5
<40
<40 1100
<410-1800
<6
. < 13 Yes Lower Wails 62.
5
<40
<40 670
< 410-1700
<6
< 13 Yes Upper Walls
- 62:
3 N/A
< 40 N/A
< 410 '
<6
< 13 Yes Cei:Ings' 63. -
2 N/A
< 40 N/A
<410- 490
<6
< 13 Yes:
Northeast Stair (IAwer)
Floof 64-1-
'N/A
< 50 N/A 1094
<6
< 13 Yes Imwer Walls
- 64 4
N/A
< 50 N/A 1850-3600
<6
< 13 Yes Ceilings" 65 1
N/A
< 50 N/A
%1
<6-
< 13 Yes l-t r
FP"h 4*tlus+ef4i..
NwM MW y '
- gigt@
, e edemlla' J.
+e4
__g i
TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMFN13 l
SAXTON NUCLEAR EXPERIMENTAL FACILITY l
SAXTON, PENNSYLVANIA.
l
- of Grids Tctal Alpha Total Alpha Plus Beta Removable l
or do-.1/100 cm dom /100 cm Contamination
- Meets -
2 2
n 2
l -
Location Figure Locations
'Ilighbt Ilighest..
Ranne dmn/100 cm Guidelines?
. Measured Average Range Average Range Alpha Beta Evaporator l
Room Floor 66 5
< 40
' < 40 613
<410- 920
<6
< 13 Yes -
Lower Walls 66 7
< 40
< 40
'1488
<41,0-1983
<6
<13 Yes :
Upper Walls' 66 2
N/A'
< 40 N/A 246-277
<6
< 13 Yes 3
' Ceilings" 67 1
N/A
< 40 N/A' 298
<6
< 13 Yes-Evaporator i
Balcony
.I Floor 68 1
< 66
< 66
< 944
<944
<6
< 13 Yes l Lower Walls 68 2
< 66
< 66
< 944
< 944
<6
< 13 Yes
TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total Alpha Total Alpha Plus Beta Removable or dpm/100 cm dom /100 cm Contamination Meets 2
2 Location Figure Locations Ilighest Ilighest Rance dom /IO0 cm Guidelines?
2 Measured Average Range Average Range Alpha Beta South Stairs Floof 70 1
N/A
<40 N/A 470
<6
< 13 Yes Lower Walls
- 70 4
N/A
<40 N/A
< 450-1610
<6
< 13 Yes E
Ceilings
- 71 1
N/A
< 40 N/A
< 450
<6
< 13 Yes Drum Shipping Room Floor 72 4
<40
< 40 1060
< 420-1450
<6
< 13 Tes Lower Walls 72 8
< 40
< 40 2876
< 420-3570
<6
< 13 Yes Upper Walis' 72 2
N/A
< 40 N/A
< 420-1650
<6
< 13 Yes Ceilings
- 73 2
N/A
< 40 N/A
< 420- 511
<6
< 13 Yes 1
i
~
TABLE 2 (Con't)
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
- of Grids Total Alpha Total Alpha Pius Eda Removsble 2
2
.. or.
dpm/100 cm dpm/100 cm -
Contamination Meets '.
2 Location Figure Locations Ilighest flighest Range dom /IGO cm Guidelines?
Measured -
Average Range Average Range Alpha Beta Compressor 4
Room Floor 74 5
< 50
< 50 1864
<420-2560
-Yes Lower Walls 74 5
< 50
< 50 1272
< 420-2060.
Yes :
E Upper Walls
- 74 4
N/A
< 50 N/A
< 420- 950
<6
< 13 Ceilings' 75 4
N/A
< 50 N/A
< 420-1180
<6
< 13-28 Yes -
Northeast Stairs (Upger)
Room Floof 76 1-
-N/A
< 40 N/A
< 480
<6
< 13 Yes tower Walls
- 76 4
N/A
< 40 N/A
< 480-2800
<6
< 13 Yes Ceilings
- 77 1
N/A
< 40 N/A
<483
<6
< 13 Yes b
. = -
.m, me...
s
+.
'M j pmf 8
=
mm
==
TABLE 2 (Con't).
SUMMARY
OF SURFACE ACTIVITY MEASUREMENTS SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA nwn..
7 Total Alpha Plus Beta Removable
- of Grids Total Alpha 2
2 i
or dom /100 cm dDm/100 cm Contamination Meets 2
Location Figure Locations
. llighest Ilighest
' Ranee dom /100 cm
. Guidelines?
Measured Average Range Average Range Alpha Beta l-Sump Room
.< 60 j Yes
< 60 1296
< 540-2620 Floor 78 8-Lower Walls 78 7
< 60
< 60
< 540
< 420- < 540 Yes E
lipper Walls
- 78 2
N/A
< 50 N/A
< 420 -
<6
< 13 Yes -
Ceilings
- 79
'1 N/A
< 50 N/A
< 420
<6
< 13 Yes Roof
- 80 8
N/A
< 880 Yes -
Shield Wall' I 81 1
< 880
< 880 Yes l
l Tunnel Floors 82 7
<40
< 40 1160
< 540-1980
<6
< 13 Yes l
Walls 82 15
< 40
< 40 1212
< 540-2190
<6
< 13 Yes l
Ceilings
- 83 2
N/A
< 40 N/A
<540
<o
< i3 r
Yes l
l No RWST Pad 84 9
5014
<490-7700
<6
< 13
- Not applicable; Alpha measurements were not performed on outdoor surfaces. Concrete samples were l
obtained in lieu of smears on rough surfaces.
l
%e range iridicated is the range of actual measurements, not averages.
l
' Single point measurements only, no gridblock average was determined.
2
.m 1
.. 2 u
I TAllLE 3 SUhlMARY OF URANIUhl AND CESIUhl CONCENTRATIONS IN INTERIOR SURFACE SOIL SAhtPLES SAXTON NUCLEAR EXPERIh1 ENTAL FACILITY SAXTON, PENNSYLVANIA I4 cation Figure U.23% (pCilg)
U-238 (pCl/g)
Cs-137 (pCL/g)'
C&A Building Auxillary Equip. Room F-7 b
0.2 0.16 1.9 i 1.8 7.2 i 0.2 J-6 0.3 i 0.2 0.2 i e 2.0 i 0.2 K-7 0.2 i 0.1 4.1. 8 3.0 0.2 k
I K-6
< 0.7 1.8 i 1.5 1.2 0.2 I-5 0.2 i 0.1 1.4 i 0.8 9.5 0.4 f 98 0.2 0.1
< 2.3 0.2 0.1 G/H-10 0.2 0.1 2.3 i 1.4 10.0 i 0.4 1-15 0.2 0.1 2.3 2.3 0.2 i 0.1 l
K-15 0.2 i 0.1 2.5 i 1.5 4.5 i 0.2 F-12 0.1 i 0.1 1.9 1.2 0.4 i 0.1 l
H-11 0.1 i 0.1 2.5 i 1.8 5.7 0.3 Charging System Room G/H 9/10
?5 0.1 i 0.1 1.6 t 0.8 1.6 i 0.2 1/J-9/10 0.3 1 0.1 2.1 1.4 1.8 i 0.1 G/H-7/8 0.1 i 0.1 1.5 i 1.0 0.5 0.1 l
1/J-7/8 0.1 i 0.1
< 2.4 0.3 i 0.1 G/H 5/6 0.3 0.4 1.4 i 1.1 0.8 i 0.1 H/I-5/6 0.2 i 0.1 1.7 i 1.8 0.4 0.1 119 i
TAllLE 3 ' Con't)
SUh!AfARY OF URANIUh! AND Ct i(Uh! CONCENTRATIONS l
IN INTERIOR SURFACE SOIL SAh1PLES SAXTON NUCLEAR EXPERIA1 ENTAL FACILITY.
j SAXTON, PENNSYLVANIA Location Figure U-235 (pCl/g)
U-238 (pC1/g)
Cs-137 (pCl/g)*
Sampling Room FJP/G-6/7 44 0.1 0.1 1.8 1.4 1.4 0.2 Decon Room E/F-6/7 42 0.1 0.1 2.9 2.1 3.0 i 0.2
{
G 0.2
. 0.3 1.5 i 1.2 -
2.7 i 0.2 Janitor 1
Closet H5 39 0.1 i 0.9 1.6 i 0.9 1.3 0.2 Monitor Room F8 31 0.2 0.1 2.0 i 1.5 1.2 0.2 l
F-6 0.1 i 0.I
< 2.3 0.7 0.I F-5 0.3 i 0.1 2.4 i 1.2 1.7 i 0.2
.. Locker Room G-10 29 0.2 0.I 1.6 1.1 0.7 0,1 G-8 02 i0.1 1.9 1.3 0.7 i 0.1 G/H-5/6 0.2 i 0.1 1.0 0.9 0.2 0.1 Shower Room F-5 33 0.2. 0.1 0.1 0.1 0.3 i 0.1 L
IIP Corridor 1.
H-6 26 0.1 i 0.1 1.8 1.3 0.6 0.1 120 I
l l-
TAllLE 3 (Con't)
SUM I Y OF URANIUM AND CESIUM CONCENTRATIONS IN INTERIOR SURFACE SOIL SAMPLES SAXTON NUCLEAR EXPERIMENTAL FACILITY
{
SAXTON, PENNSYLVANIA
_.a Lauttion Figure U-235 (pCL/g)
U 238 (pCL/g)
Cs 137 (pC1/g)
Vadable Freq. Room i
G 11 15 0.2 i 0.1 1.7 i 1.2 0.5 i 0.1 G-13 0.2 i 0.1
< 1.6 1.5 i 0.2 RWDF Scale and Storage Room F-9 59 0.2 i 0.1 1.6 i 1.4 0.9 i 0.1 i
G-12 0.2 i 0.1 0.9 i 0.2 0.1 i 0.1 1-11 0.2 0.1 2.4 i 1.5 0.2 i 0.1 H-10 0.1 i 0.1 2.5 i 1.3 1.1 i 0.1
' Review of the gamma spectra indicated that only Cs-137 exhibits positive levels gr ter than background.
I
' Uncertainties represent the 95% con 0dence level, based only on counting statistics; additionallaboratory uncertainties of i 6 te 10% have not been propagated into these data.
i
)
121
l TABLE 4 l
SUh1A!ARY OF PLUTnNIUh1 M'D STRONTIUh!
CONCENTRATIONS IN INTERIOR SURFACE SOIL SAh!PLES SAXTON NUCLEAR EXPERIhfENTAL FACILITY SAXTON PENNSYLVANIA Location Figure Pu 238 (pCUg)
Pu-239/240 (pCl/g)
Sr-90 (pC1/g)
C&A Building Locker Room 29
<0.05
< 0.07 G-10 l
j C&A Building HP Corridor 26
< 0.08
< 0.1 H-6 RWDF Scale and Storage 59
< 0.07
<0.04 i
G-12 g
1 C&A Building
< 0.1
}
Aux. Equipment Room 36 i
F-7, J-6, K-7, K 6, I 5 C&A Building Charging System Room
< 0.2 G/H 9/10, I/J 9/10, 45 G/H-7/8, I/J 7/8, G/H-5/6 C&A Building
< 0.2 Decon Room 42 FJF-6/7, G-8 I
l
' Indicates analysis not performed.
122 Y
c
TAllLE 5
SUMMARY
OF RADIONUCLIDE CONCENTRATIONS IN CONCRETE SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA Location Figure Pu 238 (pCUg)
Pu 239/240 (pCUg)
Sr-90 (pCUg)
RWDF l
Sump Room 78
< 0.10
<0.09 M-13 RWDF Pipe Tunnel 82
<0.05
<0.04 F-28 RWDF Evaporator Room 66
< 0.10
< 0.08 l
? 12 RWDF
< 0.3 Sump Room 78 L-12, M-13, K-13, 1
J-10, K-10 RWDF Pipe Tunnel
<0.4 F-28, E-26, 0-12, 82 L-9,F-9 RWDF
< 0.3 Evaporator Room 66 i
M 11, N-13, 012, L-9, I-12 RWDF
< 0.3 Compressor Room 74 1
E 13, C-11, F-39, I
H-3, L-6
' Indicates analysis not performed.
l l
123
I TABLE 6
SUMMARY
OF RADIONUCLIDE CONCENTRATIONS IN PAINT SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA
..,w._
Location Figure Pu 238 Pa 239/240 Sr-90 2
2 2
(pC1/100 cm )
(pC1/100 cm )
(pC1/100 cm )
C&A Building Aux. Equipment Room 36
< 3.2
< 0.6 J-2 RWDF Evaporator Room 66
<0.I
< 0.08
< 2.5 V-9 C&A Building Outside Wall 56
<0.4 0.4 i 0.26 U-32 C&A Building
<2.4 Outside Wall 56 A-26 RWDF Outside Wall
< 2.4 W-3 80 RWDF
< 1.1 Evaporator Room 68 Balcony B-1 RWDF f
Drum Shipping Room 72
< 1.6 C-10 RWDF
< l.5 Control Room 62 L-6
' Indicates analysis not performed.
' Uncertainties represent the 95% confidence level based only on counting statistics. Additionallaboratory uncertainties of 6 to 10% have not l
3 been propagated into these data.
124 l
TABLE 7 SUh1 MARY OF URANIUh! AND CESIUM CONCENTRATIONS IN EXTERIOR SURFACE SOIL SAMPLES SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA Location Figure U-235 (pCUg)
U-238 (pCUg)
Cs-137 (pCUg)
Outdoor Areas 1
86 0.3 0.3' 1.3 i 1.2 0.4 i 0.1 2
0.2 0.2
< 3.3 19.0 i 0.1*
3 0.1 0.1 1.6 i 1.1 4.0 0.3 4
0.4 0.2 4.4 3.8 15.0 0.1*
5 0.4 0.3 5.1 i 2.3 7.9 0.6 6
0.3 i 0.2
< 3.3 5.1 i 0.4 7
0.3 i 0.2 5.1 9.4 0.5 8
0.3 0.4
< 2.4 25.0 i 1.0*
9 0.1 i 0.2 1.2 1,2 7.7 i 0.4 10 0.2 i 0.2 2.9 3.3 14.0 i 0.6 11 0.2 i 0.2
< 2.7 12.0 i 0.5 12 0.2 i 0.1 2.4 i 1.7 7.2 i 0.4 13 0.2 0.1 1.5 1.1 20 0.2 13B' 0.2 i 0.1 1.8 1.5 1.0 0.1 14 0.3 0.2 2.2 i 1.2 6.5 i 0.4 15 0.2 i 0.3
<6.2 100.0 1.6*
15B
< 0.9 1.4 1.4 28.0 i 0.7*
16 0.2 i 0.2
< 3.2 20.0 i 0.7*
17 0.2 i 0.1 2.2 i 1.2 0.9 0.1 18 0.2 0.2
< 3.5 14.0 i 0.6 l
19 0.3 i 0.3 1.6 1.8 55.0 i 1.0*
125 m
_,m., _
TABLE 7 (Con't)
SUh1 MARY OF URANIUS1 AND CESIUS1 CONCENTRATIONS IN EXTERIOR SURFACE SOIL SAMPLES SAXTON NUCLEAR EXPERIh! ENTAL FACILITY SAXTON, PENNSYLVANIA t
f Location Figure U-235 (pC1/g)
U-238 (pCl/g)
Cs-137 (pCUg) j Outdoor Areat 19B 86
< 1.4 2.1 i 1.9 23.0 0.7
- 20 0.2 t 0.2 1.2 t 1.6 20.0 i 0.7*
21 0.4 0.4 2.9 i 1.8 20.0 i 0.9*
22 0.3 0.2 2.5 i 1.9 7.3 i 0.5 23 0.3 i 0.2 2.7 i 1.7 4.2 0.4 t
24 0.6 i 0.2 2.5 1.9 '
8.6 i 0.6 1
25 0.2 0.1 1.3 i 1.0 1.1 t 0.1 26 0.3 i 0.2
< 4.0 8.9 0.6
_ l
- Uncertainties represent the 95% confidence level, based only on counting.
l statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these data.
' Indicates a second sample was obtained and analyzed.
l
- Indicates measurements which exceeded the guideline value.
i l
i i
I i
i 126
I a
TABLE 8 SJMMARY OF RADIONUCLIDE CONCENTRATIONS IN SEDIMENT
~ SAX *IDN NUCLEAR EXPERIMENTAL FACILITY
[
SAX 1DN, PENNSYLVANIA Radionaalie Concentration foci /e) in:ation U-235 U-2.55 Pu-238 Pu-239/240 Sr-90 Upstream of.
0.9 i 0.8' l.5 i 1.0
< 0.19
<0.07
< 0.1 Outfall i
i G
Downstream of 0.1 1 0.1 2.1 i 1.5
<0.07
<0.05
< 0.2 Outfall l
4
' Uncertainties rep wt the 95% confidence level based only on counting o
statistics; additional laboratory uncertainties of i 6 to 10% have not been propagated into these data.
I f
i r
[
F l
ns
l t
I 1
TABLE 9
~
SUMMARY
OF URANIUM CONCENTRATIONS IN ROOF SAMPLES SAXTON NUCLEAR EXPERIMENTAL FACILITY SAXTON, PENNSYLVANIA Location Figure U.235 (pCl/g)*
U 238 (pC1/g)
C&A Roof-H-32 56 0.4 i 0.3'
<2.4 G-25 56 1.0 i 2.2 6.1 i 4.9 1
RWDF Roof I-7 80 0.4 0.4 3.9 2.6 Q-12 80 0.4 t 0.2
<2.9 g
RWDF Tunnel Roof C-35 84 0.3 i 0.2
<4.0 l -
i
'Relatively high measurement sensitivities were the result of limited sample quantity.
- I-
' Uncertainties represent the 95% confidence level, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been propagated into these dnta.-
l
)
f-I i.'
4 f
l:
L 128-i
.~.
.u-r,-..
...,-._m..,
_.+
r..-----
I REFERENCES 1.
"Saxton Nuclear Power Plant Final Release Survey of Reactor Support Buildings,"
GPU Nuclear Corporation, April 1990.
I 2.
' Termination of Operating Licenses for Nuclear Reactors," Regulatory Guide 1.86, U.S. Nuclear Regulatory Commission, June #74.
3.
"idonitoring for Compliance with Decommissioning Termination Survey Criteria,"
NUREG/CR 2082, U.S. Nuclear Regulatory Commission, June 1981.
i i
l n.
I i
l l
(
129 I
l i
l L
4 I
i l
i i
1 I
i APPENDIX A s
i MAJOR SAMPLING AND ANAIXrICAL EQUIPMENT I
I i
s t
APPENDIX A l
MAJOR SAMPLING AND ANALYTICAL EQUIPMENT I.
DIRECT RADIATION MEASUREMENT Eberline Alpha Scintillation Detector Model AC-3 7 (Eberline, Santa Fe, NM) 1 Eber!!ne " RASCAL" Portable Ratemeter Scaler 1
Model PRS-1 (Eberline, Santa Fe, NM)
Eberline PRM 6 l
Portable Ratemeter (Eberline, Santa Fe, NM)
Eberline Beta-Gamma " Pancake" Detector Model HP-260 (Et>erline, Santa Fe, NM) ~
Ludlum Alpha Beta Floor Monitor Model 239-1 (Ludlum, Sweetwater, TX)
.I Ludlum Alpha Beta Gas Proportional Detector Model 43-68 (Ludlum, Sweetwater, TX)
F Ludlum Ratemeter-Scaler Model 2220
'.(Ludlum, Sweetwater, TX)
'l i'.
Ludlum Ratemeter Scaler Model 2221 (Ludlum, Sweetwater, TX) _
A-1 j.
.i.
\\
(
i I
Reuter Stokes Pressurized Ion Chamber Model RSS 111 (Reuter-Stokes, Cleveland, OH)
Victorcen Beta Gamma " Pancake" Detector l
Model 489-110 (Victorcen, Cleveland, OH)
Victorcen Nal Scintillation Detector Model 489 55 (Victorcen, Cleveland, OH) t II.
LABORATORY ANALYTICAL EQUIPMENT i
Low Dackground Alpha Beta Counter Model LB4110 (Tennelec, Oak Ridge, TN) i
]
High Purity Germanium Coaxial Well Detector Model GWL-1102010 PWS S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN) i I
Used in conjunction with:
Lead Shield Model G 16 l
(Applied Physical Technology, Atlanta, GA)
Multichannel Analyzer
.j ND-66/MicroVax (Nuclear Data, Schaumburg, IUDigital Equipment Corp., Maynard, MA)
Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)
Multichannel Analyzer ND-66 (Nuclear Data, Schaumburg, IL)
{
Solid State Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)
(Tennelec, Oak Ridge, TN)
A-2 1
f l
I t
i i
\\
I APPENDIX B MEASUREMENT, SAMPLING, AND ANALYTICAL PROCEDURES i
i J
l
I i
APPENDIX B i
MEASUREMENT, SAMPLING, AND ANALYTICAL PROCEDURES 4
Surface Scans Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and surface was maintained at a nominal distance of approximately 1 cm. Identification of elevated levels was based on increases in the audible l
signal from the recording or indicating instrument. Scans of large surface areas on the floor of the facility were accomplished by use of a gas proportional floor monitor with a 2
550 cm sensitive area. The detector was slowly moved in a systematic pattern to cover 100% of the accessible floor area. Other surfaces were scanned using smaller, hand held detectors. Combinations of detectors and instruments for the scans were:
l Alpha Ludlum Model 43 68 gas proportional detector with Ludlum Model 2221 ratemeter/ scaler i
Eberline Alpha Scintillation Detector Model AC-3 7 with f
PRS-1 ratemeter/ scaler.
Gas proportional floor monitor with Ludlum Model 2220 Alpha Plus Beta ratemeter/ scaler Ludlum Model 43-68 gas proportional detector with i
Ludlum Model 2221 ratemeter/ scaler
(
l B-1 1
Beta-Gamma -
Pancake GM probe with PRM 6 ratemeter Pancake GM probe with PRS-1 ratemeter/ scaler Victoreen Nal teintillailon detector with Eberline PRM 6 Gamma ratemeter.
Reuter Stokes Pressurized Ion Chamber.
Alpha and Beta Gamma Surtnce Activity Measure;nents t
k Measurements of total alpha activity, total alpha plus beta activity, and beta gamma
{
activity levels were performed using Ludlum Model 43 68 hand held gas proportional detectors with the Model 2221 portable ratemeter/ scaler, Eberline alpha scintillation detectors with the PRS-1 ratemeter/ scaler, and Model HP-260 thin window pancake GM probes with Eberline Model PRS 1 portable ratemeter/ scaler. Count rates (cpm) were converted to disintegration rates (dpm/100 cm ) by dividing the net rate by the 4 x 2
efficiency and correcting for the active area of the detector. The effective window area 2
2 2
was 100 cm for the proportional detectors,15 cm for the GM detectors, and 59 cm for the alpha scintillation detector. The background count rate for gas proportional probes averaged approximately 1 cpm alpha and 300 cpm alpha plus beta; the average background count rate was approximately 40 cpm for the GM detectors; the average background count rate for the alpha scintillation probes was approximately 2 cpm.
B.emovable Activity Measunment i
i Smears for the determination of removable activity levels were performed using numbered filter paper disks,47 mm M diameter; smears were placed in labelled envelopes with the location and other pertinent information recorded. The smears were counted on a low-background gas proportional counter for gross alpha and gross beta activity.
B2 i
?
I i
l Emsure Rate Mensurements Measurements of gamma exposure rates were performed using Eberline PRhi-6 portable ratemeters with Victoreen Model 489 55 gamma scintillation probes. Count rates l
wete converted to exposure rates (pR/h) by cross-calibrating with a Reuter-Stokes pressurized ion chamber, Model RSS 111.
Soll! Concrete Sample Anahals Gamma Spectroscopy Sarr.ples were placed in a 0.5 liter (0.53 qt) Marinelli beaker. The quantity placed in each beaker was chosen to reproduce the calibrated counting geometry and ranged from 244 to 882 g of material. Net weights were determined and the samples counted using high purity intrinsic germanium detectors coupled to a Nuclear Data Model l
ND-66/MicroVaxil pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system.
Energy peaks used for determination of radionuclides of concern were:
Cs-137 0.661 MeV U 238 0.093 MeV from Th 234' U 235 0.143 MeV Co-60 1.173 MeV i
Spectra were reviewed for other identifiable photopeaks at concentrations above i
those normally encountered in ervironmental media.
(
- Secular equilibrium assumed.
B-3 l
1 I
k Alpha Spectroscopy Selected samples and composites of samples were analyzed for plutonium. Solid I
samples were homogenized and aliquets of these mixtures were dissolved by pyrosulfate fusion and precipitated by barium sulfate. The barium sulfate precipitate was redissolved and the specific elements of interest were individually separated by liquid liquid extraction.
The radionuclides were then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC), alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
Strontium Determination i
Several samples were selected to be analyzed for the presence of strontium. In soil and sediment samples, the soll/ sediment was dissolved using a pyrosulfate fusion in which strontium was precipitated as a culphate. Successive treatments with EDTA preferentially removed lead and excess calcium anii returned the strontium to solution. Ferric and other insoluble hydroxides were precipitated at a pH of 12 to 14. Strontiumwasre precipitated as a sulphate. Barium was removed as a chromate using DTPA. The final precipitate of strontlurn carbonate wes cuanted using a low background Tennelec alpha beta propodional counter.
f I
Uncertainties and Detection Limits The uncertainties associated with the analytical data presera: d in the tables of this report, represent the 95% confidence level for those data. These uncertainties were calculated based ou both the gross sample count levels and the associated background I
count levels. When the net sample count was less than the statistical deviation of the f
B-4 l
l 1 --
J
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 j
sample and instrument to instrument. Additional uncertainties of 6 to 10% associated with laboratory procedures have not been propagated into the dats presented in this report.
i Calibration aml Ounlity Assurance i
The Erwironmental Survey and Site Assessment Program conducted the survey and i
analytical activities according to laboratory and field survey procedures specified in manuals developed specifically for the Oak Ridge Associated Universities. The specific manuals and procedures applicable to this survey were the " Quality Assurance Manual,"
February 1990, Revision 3; the " Survey Procedures Manual," March 1990, Revision 5; and the " Laboratory Procedures Manual," Februa;y 1990, Revision 5.
l F
With the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated with NIST-traceable standards. The calibration procedures for the portable gamma instruments are performed by comparison with a NIST calibrated pressurized ion chamber.
Quality control procedures on all instruments included daIN background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and EML Quality Assurance j
- Programs, i
I B5
4 i
1 l
)
t i
i l
a 3
i
. ' 1 L
4 4
1 i
i f,
i
- l APPENDIX C i
i
'l U.S. NUCLEAR REGUIATORY COMMISSION GUIDELINES FOR SURFACE CONTAMINATION h
AND SOIL CONTAMINATION t
ta
'zu h
b 4
i-J 2
I.
3 c
[~..
U.S. ATOMIC ENERGY COMMICTICN i REGULATO RY GUIDE i
4 s!
DIRECTORATE OF REQULATORY STANDARDS REGULATORY Gul0E 1.86 l
TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. <N n 0 0 m l0 N A licensee hadng a possetuon.only lirxnse must retam, with ths Part 50 Ucenu, authon:ation for spec:a1 Secuen $0.51, " Duration of licenw. renewa!," of 10 nudeu matern! (10 CFA Put 70, "Special Nucleu 0FR Part 50. "Deennns of Production and UEitation Matenal"), byproduct restaru) (10 CFR Pan 30 "Rulu i
Tadhues" reggires that tach license to operate a of General Applicabihty to uoenatrig of Byproduct production and utilization facihty be hsued for a Matena!"), and source matenal (10 CFR Part 40, specified durstson. Upon expiration of the spee!fied "Licensms of Source Matent!"), until the fuel, radio.
l period, the license may be either renewed or terrmnated scuve components, and sources ne removed from the by the Com=tulon. Section 50.81, " Applications for faciuty. Appropriate administraties centrols and facihty l
ter=mation of licemes," rpecmes the requirements that reqturemenu are impcmed by the Pan 50 licenu and the must be satiMed to termhate an opersting license, technical specificatierts to atster that proper survei!!ance -
including the requirement that the dis:nantlement of the is perfortned and that the reactet fse!11ty is maintuned facility and disposal of the component parts not be in a safe crsadition and not operatet inimical to the commer defense and seemty or to the health and safety of tu public. This guide descriets A possrulon-only license per:ntu vamus optlans and inethods at:d procedures considered acceptable by the procedures for decomm:ssientng, such as mothbaning.
l Reguhtery staff for the twrmination of operating entombment, or dismanthng. The requuements imposed g
hernses for nuclear tsactors. Ths Addaory Cornnutta cepend on the opuon smiectei.
on Rear. tor Safeguttd: has been cortsulted concerning this gv'.de and has concutnd in tbo regulatory position.
Section 50.82 provides that the licensae may dh.
l mantle and dhpose of the component parts of a nuclear I
E. D13CusslON reactor in accordance with existing regulations. For rescuch resciers and critical facilides, this has usually When a licensee decidn to terminatt, his nuclest rneant the disusembly of a reactor end tu shipment.
reactor openting liceme, he may, u a fint sicy in the ofInte, romeumes to another appropriately heensed process, request &at his openting license be amended to organt ation for further use. The site frorn which a restnet him to possen hn not operate the faWiry. The nactor has been removed must be decentam!nated, u
[
,edvantage to the thensee of 'ecnverting to such a necessary, and hrrpected by the Commission to deter.
l penusion.only thme is reduced nrveultmos require.
rmns whether untertncted ac:ss: can be approvet in mens in that periodic sarveillance of equipment im.
the case of nuclear power reactora, dismantling has ponant to the safety of nactor operation is no longer usuaE/ been pccomplisbd by shipphts fuel offsite, nquind. Once th:s possession.only license is issued, makmg the reactor inopi.ratle, arid disponsg of seine of reactor opention is not pentdtted. Other activities the radioactive compenents.
i related to cesastion of operations such as smloading fus!
from the reactor and placmg it in storage (etthet entite Radioactive components may be ei'.her dipped off.
of offitte) may be contmued.
site for burial at an authoined bunal, ground o.t secured i
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IN C-1
an the cts.Thon radi: active materials remaining en the, fluLk and waste should be remma fr:m ths ute.
ute rous: be lufsted from the public by phync4 barnen Adequate radiation morutonag. environmental surveu.
i
(
x utb mem to prevmt public access to heardous lance. and appropnate secunty procedures should be lestb of M.at>on. SurveiSance is necessary to rJ.sure the etabEthed under a ponctuonenly beense to ensure that long term etegnty of the barners. The amouat of the health and safety of the public is not endangeret surveClann quared depends upon (1) the potential hr.ard ta v.s bra!th and safety of the public from
- b. In. Place Entombment. In place entombment con.
rz6cactse matent! remaming ori the ate and C) the msts of seahng all the remamtag lughly radioactive or inteppy of the phyncal bamers. Defore areas may be contammated componenu (e.g., the pressure venel and releand fot unrestncied uu, iney must have been reacter miemais) withm a structure intepal with the decosummated or the rectoseunty must have decayed bantoped shield after having au fuel anembbes, radio-to hu than presenbed timats (Tabis !).
active fluids and wartet, and centso selected cern.
ponenu shipped offme. The structure should prende The hazard asocisted with :he reured facility is inteptty over the pened of time in which ognificant wsluated by considenn the amount and type of quanuties (peater than Table I levels) of r 6cactivity remaming cotstam:nauon, the depee of confmement of remam wtth the matenal in the entombment. An the remammg r:6cactve matenais the phyncal secunty appropriate and contmums surveitance propam should prended by the confinement, the rux:rptibihty to be esubhshed under s pessession.only license.
relsase of radiation u a result of natural phenomena, and the durauon of required surveillance.
- c. Removal of. Radioactive Components and Dis-l znantling. AI! fuel sasemblies, raboscuve Outd! and j
C. REGut.ATORY POSITION waste, and other matenth havmg activities abbve ac.
i cepted unrestricted acunty Irvels (Table !) should be
,1
- 1. APPLICATION FOR A LICENSE hO POSSESS BLT removed from the site. The facihty owner may then have
{
NOT OPERATE (POSSESSION-ONLY LICENSE) untertncted use of the ute with no requirement.for a license. If the facihty owner so decres, the remahder of A request to amend an operating license to a the reactor facility may be dismantled and all vestres possest.!hnanly liemane thould be raade to the Director removed and disposed of.
of I.lcennng. U.S. Atomic Energy Cornmission, Washing-ton. D.C. 20545. The request should include the L Cenvenion to e New Nuden S/nem or a Fear 2 followmg infor=ation Fuel Systun. This alternauve, which apphes only to nudsar p,ower plants, ut!h:es the ex: sting turbbe synem I
- t. A description of the current status of the faculty.
wnE a'new stearn supply rystem. The onpnal nuclear i
steam supply system should be separated from the j
- b. A description of msuures that wcl be taken to electric pnerating system and disposed ofin accordance prevent enucahry or reacurity changes and to mirti=ias with one of the pronous three retirement ahrmauves, releases of radioactivtry from the facility..
- 3. SURVEILLANCE AND SECURITY FOR THE RE-
,l
- c. Any proposed changes to the technical speciEca-TIREMENT ALTERNATIVES
- WHOSE FINAL tiens that 7:Gect the poneuion.culy facihty status and STATUS REQ UIRES A POSSISSION ONLY the necessary disassembly /retuement activines to be LICENSE performei
...N facility which has been licensed under a pones-L A safety analycs of both the activities to be sion4:mly liemse may conuut a signi. Scant amount of accomphshed and the preposed changes to the technical audiosctivtry in the form of activatd and cantammated speciScaticins.
huhars and structural matanals. SurvnClance and commensurate secumy should bs providd to usure that
- c. An inventory of activated materiz.h and their the public health and safety ars not endanned.
location in the fafhty.
a Physical security to pevent inadvertem c;tposun
- 2. ALTERNATWES FOR REACTOR RETIRIMENT of personnel should be prended by multiph locked bames. The pressuct of these bamers should nake it 1
Fmtr ahenativts for retirement of nudcar reactor extremely difficult for an unauthonzed penen u,cun
-)
.fadhties an considered acceptnole by the Regulatcry access to areas when radiation or contamination 1 veis stan.There art::
exceed these specified in Reguistory Ponuon C.4. To prevent inadvertent exposure, radiaths areas abo
- t 5 j
- a. Methba!!bg. Mo.aballing of a wicat reactor mR/hr, such as near the acuvated primary rystem i f a facihty consuu of puttmg the faculty in a state of power pla st, thould be sppropnately marked ana sho ald protecuve nomp. In general, the facihty may be left not be accessible exnept by cuttmg of welded closurti er intact except
- hat all fuel usemblics and the radioactive the dtsassembly and removal of substantial struct tres 1.86-2 C-2
and/or thidding 'tvtenal. Mearst such as e remote-(1) Enworunental sumeys, readout intrusion alarm system should be provided to mdicatt to destpated penannel when a phyucal barner (2) Facility redstion surveys, a penetrated. Secunty penonnel that provide access control ?o the facility rnay be used instead c' the (3) latpesttoru of the physical bamen, and physica! barnen and ths intrusiott ahnn systems.
(4) Abnormal occur.cnces.
- b. The physical barrttrs to unauthorized entrance
{
into the facuity, e.g., fer.cet, bum.inp. welded doors, and steen openings, should se inspected at less
- 4. DECONTAk! NATION FOP REI. EASE FOR t%
quanerly to auun thst Sese bamen have not detenor.
RESTRICTED USE hted and that locks and lockhg apparatus are intact.
If it is deured to terminate a license ud to climmate
- c. A facuity radiation survty thou14 be perfonned at any funhet surveillance requuemente, the facility should least quarterly to verify that no radioactfu mater.41 is be sufficiently decontammated to prevent nsk to the j
escapmg or being transported tbrough the containment pubhc health and safety. After the decontamination is bamen in the facGity. Sunpl3ng should be dona along uusfactorily accomplished and the sits inspected by the most probable path by whjca radioacuve matena!
the Commusion, the Comm3nion may authenze the such as that stored in the inner containment regions license te be termmated and the facuity abandoned or could be tranrponed to the outer repora of the facility released for unrestricted we, The licenae should per-l and ultimately to.the enviroE form the decontamination utmg the 'foDonng guide.
lines:
l
- d. An enwonmental ranatjen swvey thould be perfoimed at teact semiannuaDy to verify that no
- 1. The licemes should make a reasons' ale. effen to siplicant amounu of radlauen have been released to the cuncaste rendual conm.unation.
environmsnt from the faccity. Sarnples such as sou, wptation, and water should be taken at locations for
- b. No covenng thould be applied to radioactive
{
which sutisth! data hu been ystabluhed dunns reactor surfaces of equipment or struerures by punt, phtmg.or operations.
other covmng material umn it is known that contamins-tion levels (determmed by a servey and documented) are
- e..A ute representative should be desjpated to be below the limits specified in Table 1. In addition. a responsible for controning authented acccu into and reasonable effen should be made Ond documented) to movement withh the facatty.
fu:ther mM'e contamination pnor to any cuch covenng.
f.' Administr3tive procedures should be estabushed for the notincation and re;.orting of abnormal ot; cur.
- c. The radioactivity of the interior su'rfaces of pipes, -
rences such as (1) the entrance of an unauthorted drzin linet, or ductwork should be determised by
. peon or pesons into the faculty and (2) a significant -
maki.y measurements at all trap ancl other appropnate chany in the radiation or contamination levels in the as? u pcmt*, provided contamination at theatlocations
~
h IIkely to be represenutive of coitamination on the fac!hty Jr the ofIsi+e environment.
interior of the pipes, drua hnes, or ductwork. Surfaces
- g. The foDowing repons should be rna le:
of prumises equipment, or scrap w'Jeh are ifxely to be l
contammated but are of such ::n constructien, or 3
l (1) An annual report to tla Director ofIdeennat, location as to make the surface inaccessible for purposee U.S.' Atomic Energy Commission, Washington, D.C.
of measurement should be sasumed to be contancnated.
.i 20545, describtag the results of the environmental and in extase of the pernusaable radiation hmiu.
faculty radiatier, surveys, the sutus of the facairy, and en - evaluabon of the performance of secunty and
- d. Upon request, the Comminion may authoriza a t
survenlance measures.
licenwe to reunquish possession or control of premises, equipment, or scrap having surfaces contaminated in *
(2) An abnormal occurreacs report to the Regula-excess of the htmu specified. This may include, but is tory Operauora Regional Office by tele;6one withm 24. not hmited to, epecial ctrcumstancs surk as the transfer hours of 62cevery of an abnormal occurrence. The cf premises to another licensed orpacation that wcl abnormal occunence will also be reported in the annual contmus to work eth radioactive materials. Requects
[
l repen described in the precedmg item.
for such authonzation should prod:
1
- h. Records or loss relauve to the ft,Dowmg items (1) Detailed, specific information describing the l
should be kept and retained unta the liccuse is termi.
premues, ecuspment, si.: rap, and radioacuve conta=J-nated. after which they may be stored with other phnt cants and the nature, extent, and degree of residual records:
rurface contu tmauen.
l 1.86 3 1
l C-3
1 i
(:) A detailed health and safety analysu indl.
o7 s chante in the technical specificauons thould be I
canng that the rendual am0unu of materials on surface treewed and approved in actordance with the require-areu, together with other consderations such u the ments of 10 CFR {50.!9.
I prcipecuve use of the premues, equipment, or scrsp.are unlasly tc result in an unreuonable tak to 21e healta If major structural changes to radicactive components l
and safety of the pubhe.
of the facihty are planned, such u removal of the
]
pressure venet or major components cf the pnmary
- e. Pnot to releast of the premises for unrestncted system, a d.smintlement plan includmg the informauen use, the licerace'should make a comprehenuve radisuon required by {$0.22 should be subtrutted to the Commis-survey establishmg that contaminanon is wittun the sion. A dismantlement plan should be subrutted for all i
hmsts specined in Table 1. A survey report should be the altenuuves of Replatory Position C.: except nied withane Director of I icenung. U.S. Atomic Energy mothbal!mg. However, minor dtsauemoty acunt es may l
Commusion, Washington, D.C. 20545, with a copy to stiU be performed in the absence of such a plas, l
the Director of the Regulatory Operations Reponal provided they are permitted by ensung openung and Ofnce haveg jurucction. The report thould be filed at mamtenance procedures. A dtrmantlement pian should leut 30 days pner to the planned date of abandonment.
include the following-I
(
The survey report shouldt
- 1. A desenpuen of the ultimate status of the facility (1) Iden:ify the premises!
- b. A desenption of the dhmantilng actinties and the I
( ) Show that reasonable effort hu been made to precautons to be taken.
(,.i reduce residual contamination to as low as practicable
- c. A safety analysis of the dismantimg acuwties levels; including any efnuenu which may be reitued.
l (3) Des:: fee the scope of the survey and the 1
genera! procedures foUowed; and
- d. A saftry analycs of the facihty in tu ulumate status.
l j
(4) State the Anding of the survey in units l
rpee!Se d in TabW l.
Upon satisfactory renew and approval of the dis-mantimg plan, a 6 mant11ng order u inued by the Aher renew of the report, the Commission may Comm1 sion m accordance with $50.82. Wnen da.
inspect the fac!bties to conth n the survey pner to tr.antling is compicted and the Com:nhuon has been
- anung approval for abandonmeet.
notified by letter, the appropriate Retulatcry Open-tions Reponal Office inspecu the fa:cfry and vertfics l
4
- 5. REACTOR R TIREMENT PROCEDURIS compleuen in accordance with the dismantlement plan.
If residual radiauon leveh do not exceed the values in As indicated in Regulatory Podtfon C.2, several Table I, the Commiuion may terminate the license. If alterr.atrves are acceptable for reactor facGiry retirement.
these levels are exceeded, the licensee tctuns tne l. 1 If mmer ciisauembly or mothballing" la planned, this ponession-only license under which the dismantilt:g l Ij could be done by the exisung openting and mamte.
activ: ties have been conducted or, as ui alternattw, may ruace procedures under the license m effect. Any make applicacon to the State (if an Agreement State)
I p'.anned actions involving an unreviewed t.afety question for a byproduct matenals license.~ -..
I 1
h%
f.'3 n
+
I 1.86 4 C-4 l
l
TABE !
ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCL! des AVERAGE 0C l
MAX 1MUMo d l
REMOVABLED '
U.nat, U.035, U. 36, and 5.000 dpm c/100 c5
!$.000 dpm c/100 cm2 1.000 dpm a/100 cm2 associated decay procu:ts Transurtnics, P *:6, Ra.228, 100 dpm/100 cm2 300 dpm/100 cm2
- 0 dpm/!00 cm2 Th 230.Th 238,Pa 231 At027,1125,1129 Th nat Th 232, Sr.90.
1000 dpm/100 cm2 3000 dpm/100 em:
200 dpm!!00 cm2 Ra.
3, Ra ::6. U 232, 1106,1131,1133 2
2 1000 dem M/100 cm2
-l Beta.pmma emitters (nuclides,
5000 dpm M/100 cm 15,000 dpm M/100 cm with de: y modes other than aJpha j
emission or spontaneous fissien)
'l except St 90 and othen noted above. i eWhere surface contammation by both alpha, and beu pmme emmmg nuchats surts, the limits esublished for alpha and i
beta-pmtro-emittag nuchdes should apply macpendently.
bas used in this table, dpm (dinntepauena per trunuts) means the rate of emtamon by radacactrve materu! as determined by conecung the connu per rainute observed by an approprute detector for bacxpound, emetency, and reometric facton assoc:sted =1th tas msmimentatson.
8Measuremenu of avertre contartunant should not be aversted over more than I square meter. For obpets of leu surface arsa the
(
avente should be derned for each such object.
2 dDie ma.ureum conurnmation levej sppues to an area of not fnore than 100 cm.
'I
' Die amount of removable ndioact7ve matenal per 100 ed of surface ares should be detemuced by s,pmg that arts s,th dry futer or soft sbsorbent papet, applyttig moderate preuurt, and assess.ng the arnount of radsoactres matenal on tne mpe sith an apprognate instrument of known emcsency. When nmovable conurmaation on obpett of neu surfam arsa is cetermined, the perunent leveh should h reduced prcporuonally and the enin surface abould be s1 ped.
l I
i i
i i
1 l
i
!1 f
j 1.
i i
l s
l l
J i
[
+
)
i 1
1.56-5 l
]i C-5 l
l l--
Guidelines for Residual Conce:trations of Thorium and Uranium Wastes in Soil On October 23,1981, the Nuclear Regulatory Commission publist.ed in the Federal Register a notice of Branch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium l
Wastes from Past Operations." This document establishes guidelines for concentrations of uranium and thorium in soil, that will limit maximum radiation received by the public under various conditions of future land usage. Ecse concentrati. ns are as follows:
a Maximum Concentrations (pCi/g) for various options 6
d Material 18 2
3' 4
l-Natural norium (Th.232 + %.228) 8 i
with daughters present and in equilibrium 10 50 500 Natural Uranium (U-238 + U 234) with daughters present and in 40 200 equilibrium 10 Depleted Uranium:
1,000 Soluble 35 100 3,000 Insoluble 35 300 Enriched Uranium:
.f 1,000 Solt.ble 30 100 Insoluble 30 250 2,500
- Based on EPA cleanup standards which limit radiation to 1 mrad /yr to lung and 3 mrad 4T to bone from ingestion and inhalation and 10 pR/h above background from direct external expocure.
j Based on limiting individual dose to 170 mrem 67.
6
' Based on limiting equivalent exposure to 0.02 working level or less, d Based on limiting individual dose to 500 mrem /yr and in case of natural uranium, limiting expcsure to 0.02 working !cvel or less.
I i,
l l
ADDITIONAL CONCFXIRATION GUIDELINES Specific criteria for unrestricted release of the Sarton Nuclear Experimental Facility have not been developed. However, based on NRC guidelines and NRC endorsement of concentration I
guidelines for other radionuclides at other NRC sites, the following guidelines may be used for comparison.
Inhalation and Incestion 1
Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mrem to the lung or 60 mrem to the bone.
Limiting soil concentrations are derived to satisfy these external and internal target criteria. The concentration limits are presented in the folloMng table.
Radionuclide Concentration Limit Atvwe Backcround (nCi/c) 1 1
Depleted Uranium 35 l
Enriched Uranium 30 Thorium (Natural) 10 f
Co40 8
Cs 137 15 St-90 1.8 x 10' I,
1 1
_