Text

Confirmatory Radiological Survey of Bldg C Lynchburg Research Ctr B&W
	ML20206D489
Person / Time
Site:	07000824
Issue date:	07/31/1988
From:	Murphy G; OAK RIDGE ASSOCIATED UNIVERSITIES
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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ML20206D444	List: ML20206D439; ML20206D455; ML20206D466; ML20206D471; ML20206D482; ML20206D489;
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	ORAU-88-G-122, NUDOCS 8811170098
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ORAU 88/G 122 0)

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L Pr: pared by

'!",i$,^" 'id CONFIRMATORY RADIOLOGICAL SURVEY Pr: pared for p

U.S. Nuclear i

Regulatory commission's BUILDING C Region 11 Office sun. ported by LYNCHBURG RESEARCH CENTER Division of h"us'a'r'*sa*fe y BABCOCK & WILCOX COMPANY "d "'d i'* '

LYNCHBURG, VIRGINIA G. L., MURPHY Radiological Site Assessment Program i

l Manpower Education, Research, and Training Division i

i FINAL REPORT JULY 1988 l

1 g311170098 881108 FDR ADOCK 0700 4

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J NOTICES The osaneene esproceed heroM de not necessority reheet the ephiene of the opensering institutene of ook Ridge Asseeisted i

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...e.wrm any ag.meuy or reopenelbuny f or the escurecy, sempietenees, et weeMaese of any Mtermate spearetwo, preewet, et procese esewood, et representa that its wee wewtd not mtringe privete'y owned rights. Reference herein to any speelfte esmmercial preewet, procese, of serv'ee by trese name, mert manutertwret, or othermiee, sees not necouartiy tenetawte er Wply na eneeroement er tuemmends-

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ORAU 88/G 122 CONFIRMATORY RADIO 1DGICAL SURVEY OF BUILDING C LYNCHBURG RESEARCH CENTER BABCOCK AND WILCOX LYNCHBURG, VIRGINIA Prepared by G.L. Murphy Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831 0117 Project Staff J.D. Berger F.A. Lange R.D. Condre J.L. Payne B.D. Hamby D.S. Styers*

A.K. Klitz C.P. Weaver Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Redulatory Commission Region II Offico FINAL REPORT July 1988 This report is based on work performed under Interagency Agreement DOE Ns.

40 816 83 NRC Fin.

No.

4 9076 3 between the U.S. Nuclear Regulatory Commission and the U.S.

Department of Energy.

Oak Ridge Associated Universities performs complementary work under contract number DE AC05 760R00033 with the U.S. Department of Energy.

Currently with ASG, Inc., Oak Ridge. TN.

J

E TABLE OF CCNTENTS Paxe List of Figures 11 List of Tables.

viii Introduction and Site History.......

1 Site Description.

2 2

Purpose.

3 Survey Procedures.

Results.

7 Ocuparison of Results With Guidelines.

11 12 S umma ry....

References.

13 Appendices Appendix A:

Proposed Confirmatory Radiologic.a1.iurvey Plan for Building C Lynchburg Research Center Babcocl; and Wilcox Compan/. Lynchburg, Virginia Appendix B: Major Sampling and Analytical Equipment Aprendix C: Measurement and Analyti:a1 Procedures Appendix 0:

Guidelines For Decontamination of Facilitias and I

Equipment Prior to Release for Unrestricted Use or i

Termination of Licenses for By. product, Source or j

Special Nuclear Material 1

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List of Figures Page FIGURE 1:

Map of Virginia, Shoving Approximate Location of Babcock and Wilcox Facility....................

14 FIGURE 2:

Map of Area Surrounding Babcock and Vilcox Facility....

15 FIGURE 3:

General Site Plan of Mt. Athos Babcock and Wilcox Facility 16 FIGURE 4:

Plan View of the Lynchburg Research Center Indicating Location of Building C.

17 FIGURE 5:

Floor Plan of Building C.

18 FIGURE 6:

Location of Rooms Where im x la Grid was Installed.

19 F8GURE 7:

Indoor Gamma Exposure Rate Measurement Locations 20 FIGURE 8:

Room 3 Showing Locations of 5 point Grid Blocks Surveyed.

21 FIGURE 9:

Room 3 Shoving Locations of Upper Vall and Ceiling Single Point Measurements.

22 FIGURE 10:

Root 15 Shoving locations of 5 point Grid. Blocks Surveyed.

23 FIGURE 11:

Fnom 1.% Showing Locations of Upper Vall and Ceiling Single Point Hessurements.

24 FIGURE 12:

Room 16 Shoving Locations of 5 point Grid Blocks Surveyed.

25 FIGURE 13:

Room 16 Showing Locations of Upper Vali and ceiling Single Pein?. Meawarements.

26 I

FIGURE 14:

Room 17 Shoving Locations of 5 point Crid Blocks Surveyed.

27 F8GURE 15:

Room 17 Showing Locations of Upper Vall and ceiling Single Point Measurements.

28 l

F2 CURE 16:

Room 19 Showing Locations of 5 point Grid Blocks Surveyed.

29 FIGURE 17:

Room 19 Showing Locations of Upper Vall and ceiling Single Point Measurements..

30 FIGURE 18:

Room 19 (East Waste / Sump Tank) Showing Locations of 5 point Grid Blocks Surveyed.

31 F8GURE 19:

Room 19 (West Vaste/ Sump Tank) Showing locations of 5 point Grid Blocks Surveyed.

32 FZGURE 20:

Room 20 Shaving Locations of 5 point Grid Blocks Surveyed.

33 11

r List of Figures s

(Continued)

Page i

FIGURE 21:

Room 21 Showing Locations of Upper Wall and Ceiling Single Point Measurements.

34 FIGURE 22:

Room 22 Showing Locations of 5 point Grid Blocks Surveyed.

35 FIGURE 23:

Room 22 Showins Locations of Upper Wall and ceiling Single Point Measurements.

36 FIGURE 24:

Room 26 Showing Locations of 5 point Crid Blocks Surveyed.

37 FIGURE 25:

Room 26 Showing Locations of Upper Wall and Ceiling Single Point Measurements.

38 FIGURE 26:

Room 27 Showing Locations of 5 point Grid Blocks Surveyed.

39 FIGURE 27:

Room 27 Showing Locations of Upper Wall and ceiling Single Point Measurements.

40 F8GURE 28:

Room 43 Showing Locations of 5 point Grid Blocks Surveyed.

41 FIGURE 29:

Room 43 Showing Locations of Upper Wall and ceiling Single Point Heasurements.

42 FfGURE 36 Room 50 Showing Locations of 5 point Grid Blocks Surveyed.

43 FIGURE 31:

Room 50 Showing Locations of Upper Wall and ceiling Single Point Measurements.

44 FIGURE 32:

Men's Change Room Showing Locations of 5 point Grid Blocks Surveyed.

45 FIGURE 33:

Men's Change Room Shoving Locations of Upper Wall and ceilin5 Single Point Measurements 46 FIGURE 34:

Drying oven Showing Locations of 5 point Grid Blocks Surveye d.

47 FIGURE 35:

Drying Oven Showing Locations of Upper Wall and ceiling Single Point Measurements.

48 F2 CURE 36:

Mallway (Area 24) Showing Locations of 5 point Grid Blocks Surveyed.

49 (IGURE 37:

Mallway (Area 24) Showing Locations of Upper Wall and ceiling Single Point Measurements.

50 F2GURE 38:

Hallway (Area 55) Showing Locations of 5 point Grid Blocks f

Surveyed.

51 111 l

List of Figures (Continued)

E*E&

FIGURE 39:

Hallway (Area 55) Showing Locations of Upper Wall and Geiling Single Point Measurements 32 FIGURE 40:

Hallway (Area 56) Showing Imcations d 5 point Grid Blocks i

Surveyed.

53 FIGURE 41:

Hallway (Area 56) Showing Locations of Upper V.sil and Geiling Single *oint Measurements 54 FIGURE 42:

Room 1 Showing Locations of Single point Measurements 55 FIGURE 43:

Room 2 Showing Locations of Single point Measuremcnts 56 FIGURE 44:

Room 4 Showing locations of Single point Measurements.

57 FIGURE 45:

Room 5 Showing Locations of Single point Measuremente.

58 FIGURE 46:

Room 6 Showing Locations of Single point Measurements 59 71GURE 47:

Room 7 Showing Locations of Single-point Measurements 60 FIGURE 48:

Room 8 Showing Locations of Single point Hrasure.nents 61 FIGURE 49:

Room 9 Showing Locations of Singlu poin: Measurements 62 FIGURE 50:

Room 10 Sho.iing Locations of Single-point Heasurements.

63 FIGURE 51:

Room 11 Showing Locations of Single point Measurements.

64 FIGURE 52:

Room 12 Showing lu ations of $1ngle point Hessuremanes.

65

' ICURE 53 :

Room 01 Showing lecations of Single point Measurements.

66 j

FfGURE $4:

Room 02 Showing Lccations of Single point Heasurements.

67 FIGURE 55:

Room 03 Showing locations of Single point Heasurements.

68 F2GURE 56:

Room 04 Shoving Locatf or.s of Single point Measurements.

69 FIGURE 57:

Roos 05 Showing Locations of Single point Measurements 70 FIGURE 58:

Room 06 Showing Locations of Single point Measurements.

71 FIGURE 59:

Room 25 Showing Locations of Single point Measurements.

72 FIGURE 60:

Room 44 Showing Locations of Single point Measurements.

73 FIGURE 61:

Roon 52 Showing Locations of Single point Measurements.

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i List of Figures (Continued)

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t FIGURE 62:

Rooms 53 and 54 Showing Locations of Single point Measurements.

75 FIGURE 63:

Ceramic Lab Showing Locations of Single point Measurements.

76 FIGURE 64:

Fan Room Showing Locations of Single-point Measurements.

77

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FIGURE 65:

Fire Equipment Room Showing Locations of Single point Measurements.

78 FIGURE 66:

HP Lab Showing Locations of Single point Measurements.

79 F2 CURE 67:

HP Office Showing Locations of Single point Measurements.

80 l

FIGURE 68:

Ladies Change Room Showing Locations of Single point Measurements.

81 i

i FIGURE 69:

Laundry Room Snowing Locations of Single point Measurements.

82 F2 CURE 70:

Machine Shop Showing Locations of Single point Measurements.

83 F?,GURE 71:

Mechanical Equipment Room Showing Locations of Sin 5 a point l

1 Measurements.

84

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FIGURE 72:

Pit (Basement Area) Showing Loe.atior.4 e,f Single point Measuremer/

85 FIGURE 73:

Panthouse (Above Room 22) Showing Locations of Sin 5 e-point f

1 Measurements.

86 I

i FIGURE 74:

Penthouse (Above Ladies' Change Room) Showin5 Locations of Sin le point Measurements.

67 i

g F8 CURE 75:

Penthouse (Above Vault) Showing Locativns of Sirigle point Measurements.

88

{

FIGURE 76:

Storage Shod Showing Locations of Single point Measurements.

89

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FIGURE 77:

Vault Showing Locations of Single point Measurements.

90

{

t FIGURE 78:

Hallway (Area 16N) Showing Locations of Single point

[

Measurements.

91 i

FICURE 79:

Hallway (Area 16W) Showing Locations nf Single point i

Measurements.

92 I

F2GURE 80:

Hallway (Area 23) Showing Locations of Single point Measurements.

93 v

List of Figures (Continued)

Pare FIGURE 81:

Hallway (Area 27E) Showing Locations of Single point Measurements.

94 F8GURE 82:

Hallway (Area 27V) Showing Locations of Sir.gle point Measurements 95 FIGURE 83:

Hallway (Area $7) Showing Locations of Single point Measurements 96 FIGURE 84:

Room 1 Showing Trench Soil Sampling Location.

97 FIGURE 85:

Room 3 Showing Trench Soil Sampling Location.

98 F8GURE 86:

Room 5 Showing Trench Soil Sampling Location.

99 FIGURE 87:

Room 6/7 Shoving Trench Soil Sampling Location.

100 FIGURE 88:

Room 15 Showing Trench Soil Sampling Location.

101 FIGURE 89:

Room 16 Showing Trench Soil Sampling Location.

102 F1UURE 90:

Room 17 Showing Trench Soil Sampling Location.

103 FIGURE 91:

Room 19 Showing Tren:h Soil Sampling f.ocation.

104 FfGURE 92:

Roou 26 Showing Tronch Soil Sampling Lacation.

105 i

FIGURE 93:

Room 22 Showing Trench Soil Sampiing location.

106 FZGURE 94:

Hallway (Area 24) Showing Trench Soil Sampling Location.

107 FfGLRE 95:

Ladies' Change Room Showing Ttench Soil Sampling Location.

108 i

FEGURE 96:

Laundry Room Showing Trench Soil S Ampling Location.

109 FIGURE 97:

Men's Change Room Showing Trench Soil Sampling Location.

110 F2 CURE 98:

Vault Showing Trench Soil Sampling Location.

111 F2 CURE 99:

Hallway (Area 16N) Showing Trench Soil Sampling Location.

112 FIGURE 100:

Hallvay (Area 16V) Showing Trench soil Sampling Location.

113 FIGURE 101:

Hallway (Area 23) Showing Trench Soil Sampling Location.

114 FIGURE 102:

"Cold" Drain Residue and Swipe Sampling Locations.

115 FIGURE 103:

Roof Area Showing Locations of Direct Measuremen*;s and Gravel Sampling.

116 vi

is List of Figures (Continued) l

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FIGURE 104:

Surface Soil Sampling locations and Direct Radiation Levels Measured Around Building C,

117 i

FIGURE 105:

Isopleth Exposure Rate levels Determined at Suilding C.

118 4

FIGURE 106:

Direct Radiation Levels North of Building C 119 FIGURE 107: Surface Soil Sampling Locations North of Building C 120 l

4 FIGURE 108: Outdoor Area Showing Storm Drain and Shallow Borehole

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Locations.

121 j

1 FIGURE 109:

Locations of Background Measurements and Baseline Sampling.

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LIST OF TABLES Page TABLE 1:

Direct Radiation Levels and Radionuclida Concentrations Measured at Baseline Sampling Locaticas.

123 TABLE 2:

In4'oor Gamma Exposure Rate Measurements.

124 TABLE 3:

Summary of Surface Contamination Hessurements in Areas with a High Probability of Contamination (HPC).

12$

TABLE 4:

Summary of Single Point Surface Contamination Measurements from Low Probability of Contamination Areas (LPC).

131 TABLE 5:

Radionuclide Concentrations in Soil Samples Collected From Exposed Trenches Inside Building C.

134 TABLE 6:

Radicnuclide Concentrations in Residue Collected from "Cold" Drains.

137 TABLE 7:

Summary of Beta. gamma Surface Contamination Measurements from the Roof of Building C.

138 TABLE 8:

Radienuclida Concentrations in Gravel Collected from the Roof 139 of Buildtog C.

TABLE 9:

Radionuclide Concentratians in Surftce Soil Samples Collected Aroa.>i Building C.

140 TABLE 10: EaJtent:11de Concentrations in Surface Soil Samples collected North of Building C (4/26/88) 141

?ABLt 11:

Radionuelida Concentrations in Soil frem Storm Drain and Shallov Boreholes from Forrer Locations of Waste Orain Lines,

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CONFIRMATORY RADICIhCICAL SURVEY OF BUILDINC C LYNCHBURG RESEARCH CENTER BABCOCK AND VILCOX COMPANY LYNCHBURG, VIRGINIA INTRODUCTION AND SITE HISTORY The Lynchburg Rodearch Center (LRC), located on the Babcock and Vilcox Company site east of Lynchburg, Virginia, is a facility used to test and study nuclear cycles, under Nuclear Regulatory Commission license number SNM 778.

Building C was former1v used as a research and development facility for

uranium, thorium, and plutonium fuels. The existing structure is the result of several additions to the original laboratot building constructed in 1962.

2 The building consists of approximately 950 m of laboratories, office space end support facilities.

The dscommissioning of Building C occurred in three phases.

Phase I censisted of former laboratories (rooms 25, 26, 27, 43, 44, 50, 51, 52, 53, end 54), offices associated with rooms 43, 44, and 50, the western portion of hallway 23, and the Central Stores area.

Research conducted in thesa locations involved uranium, thorium, and plutonium solutions and powders.

Phase II included former laboratories 15, 16, and 17; and, offices and hallways along the eastern side of the building. Research in these areas involved plutonium and uranium oxides in powder form.

Phase III included former laboratories 19 and 20, two vaste tanks, two cpecial nuclear material vaults, hallway 24, che remainder of hallway 23, change rooms, ventilation equipment, and three penthouse locations.

These creas primarily se rved to support and perform analytical chemistry on plutonium fuels.

Babcock and Vilcox submitted three final survey reports (Phase 7, II, and III)l, which indicate that the site meets the NRC guidelines for release for unrestricted use.

During the decontamination procedure all contaminated

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t materials, equipment, drain lines, soil, and ductwork were removed from the facility for commercial disposal.

At the request of the Nuclear Regvlatory Commission (NkC), Region II, the Radiological Site Assessment Program of Oak Ridge Associated Universities radiological survey from August 17 to S9ptember 2,1987, (ORAU) conducted a and April 26, 1988 to confirm that the radiological status of Building C meets the NRC guidelines for release for unrestricted use.

SITE DESCRIPTION The Lynchburg Rasearch Center is loca:ed on the Mt. Athos, Babcock and Wilcox property, vest of Route 726, 16 kilometers east of Lynchburg, Virginia (Figures 1 and 2).

The facility is located in Campbell County and is bounded on three sides by the James River.

Babcock and Wilcox Mt. Athos maintains 212.5 hectares, and the LRC occupies approximately 5.5 ha.

Other Babcock and Wilcox facilities operated on the site are the Commercial Nuclear Fuels Plant and the Naval Nuclear Fuels Division (Figure 3).

Building C is located on the northeast corner of the LRC site (Figure 4).

The floor plan for Building C is presented in Figure 5.

Building C contains two vaults, formerly used for the storage of special nuclear material, and two vaste tanks, buried beneath the building.

An operating

'an room and exhaust stack se rve the ventilatien systems of Buildings B and C.

A small basement area is located beneath the fan roca.nd Room 50.

PURPOSE The purpose of the survey was to confirm the licensee's final su-vey

results, by measuring surface contamination levels and radionue.ide concentrations in soil and other media, relative te release of the facility to unrestricted use.

t 2

SURVEY PROCEDURES Document Reviev ORAU reviewed the final survey reports (Phases I, II, and III), and supporting documentation for the facility. Approximately 10% of the raw data on a room by room basis was compared to the data presented in the final survey report.

Survey Method A proposed survey plaa (Appendix A) was submitted to NRC Region II for approval prior to beginning survey work at the site.

The plan outlines site specific survey and sample collection procedures.

The facility was divided into two areas for survey [High 'robability of Contamination (HPC) and Low Probability of Contamination (LPC)), based on history of radioactive material

use, licensee characterization data, level of effort required for remedial action, and final survey data.

Facility Su rv sv Gridding Confirmatory measurements were referenced to a 1 m x 1 m grid system installed by ORAU on the floors and lower walls (up to 2 m), in the HPC areas.

Measurements collected from ungridded surfaces (upper walls and ceilings) were referenced to the floor and lower wall grid or to promirant building features.

Figure 6 identifies the areas where the grid was installed.

No grid was established in the LPC areas.

Surface Scans Alpha, beta gamma and gamma scans were performed on 100% of the floors (both HPC and LPC areas) and 50% of the lover walls in the HPC area and random surfaces in the LPC areas, using an alpha /bata floor monitor, "pancake" CM detectors, and NaI(T1) scintillation detectors coupled to scaler /ratemeters 3

with audible indicators.

Representative ovethead surfaces (above 2 m) such as ledges, beams, pipes, ductwork, and miscellaneous equipment were also scanned.

Exposure Rate Measurerents Camsa exposure rates at one meter above the floor, were measured at 12 locations inside the facility, using NaI(Tl) gamma scintillation detectors cross calibrated onsite with a pressurized ionization chamber (Figure 7).

Measurement of Total and Removable Contamination Two hundred twenty one (221) grid blocks on the floors and lower walls of the HPC area were randomly selected for surface contamination measurements (Figures 8 to 83).

Total measurements of alpha and beta gamma contamination levels were systematically pe rformed at the center and four points cidway between the center and block corners.

Smears for removable contamination levels were performed at the location in each grid block where the highest direct reading was obtained.

Single point total contamination levels were also measured at 87 locations on the upper walls, ceilings, and miscellaneous overhead objects.

Smears were collected at each single point measurement location.

Two hundred twenty (220) single point measuresents were performed on the floors and lower valls, upper walls and ceilings, and miscellaneous.rerhead objects of the LPC area.

Smears for removable contamination levels were performed at each single point location.

Indoor Soil Sampling Fifty one (51) soil samples were collected from exposed trenches inside Building C,

where drain lines had been removed during remedial action, f

Figures S4 to 101 indicate the soil sampling locations, with the trench 1ccations overlaid on the individual room outline.

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Drain Sampling Three drain residua samples were collected from "cold" drains remaining in Building C.

Six swipes were run through the "cold" drain lines and returned for analysis.

Figure 102 presents the drain residue and swipe sampling locations.

Water Sampling

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One standing vster sample was collected from a pit located in room 52.

Roof Systematic gamma scans and eight random beta gamma measurements were performed on the Building C roof (Figure 103), using "pancake" CM detectors and NaI(Tl) scintillation detectors coupled to ratemeters with audible indicators.

Four gravtl samples were collected from random locations on the roof.

Outdoor Survey Cridding t

The immediate area surrounding Building C was enclosed by chain link fence located approximately 5 to 10 meters ' om the building walls.

The area was not gridded, and all s ample s collected were referenced to prominent building features or existing landmarks.

The follow up survey performed on April 26 used a 5 m grid established on the northeast side of Building C.

Surface Scans ORAU performed walkover surfaco scans at 1 to 2 meter intervals on the areas adjacent to Building C, using NaI(Tl) scintillation detectors coupled to ratemeters with audible indicators.

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Soil Sampling Sixteen (16) surface soil samples (0 - 15 cm) were collected at randoe around Building C (Figure 104). A large portion of the area was covered by asphalt / concrete / gravel walkways, parking lots or driveways, and available soil sampling locations were limited.

Ten surface soil samples (0 15 cm) were collected at 5 m grid intervals from the area north of Building C to provide additional soil concentration data on the follow up survey (Figure 107).

Twenty three (23) surface and/or shallow borehole soil samp1.s were collected from the locations where the "hot" waste drain line connected Building C to the liquid waste holding tank (Figure 108).

Two sediment samples were collected from the storm drain located near the loading dock on the north side of Building C (Figure 108),

Background Samples and Measurements Samples of surface coil were collected and exposure rates were measured at 6 offsite locations (Figure 109) in the crea around the Babcock and k'ilcox

facility, to establish baseline radionuclide concentrations and exposure rates.

This data was collected during the ORAU confirmatoty survey of Building A performed in July 1986, and presented in the ORAU June 1987 final report 2, Sample Analysis and Interpretation of Results

Soil, sediment, swipes, drain residues, and gravel saaples were analyzed by gamma spectrometry, and the spectra were reviewed for identifiable photopeaks, with particular attention to U 238, U 235, Th 232, Co 60 and Cs 137.

Alpha spectroscopy was performed in selected samples for Pu 238 and Pu 239/240.

The water sample and smears were analyzed for gross alpha and gross beta activity.

Additional information concerning majnr instrumentation, sampling equipment, and analytical procedures is provided in Appendices B and C.

Results were compared with NRC guidelines for release of facilities for unrestricted use (Appendix D).

6

RESULTS Document Review l

In ge ne rc. '

the decontartnation plan appears to be adequately developed and implemented er *.re the NRC guidelines are met, and the final survey 3 iological status of the site.

Babcock and

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report adequatei<

r s sed tapling approach, and the data presented in Wilcox used a s te ic e. >

c section 5 of the

-'?arca were within the NRC guidelines.

No significant discrepancies were

d. * ;fiao e documents reviewed, i

e Background Levels and L ' -\\[ne,,oncentrations Background exposure rates anl baseline radionuclide concentrations in soil from the vicinity of the Babcock and Vilcox site were determined in a 2

July 1986 ORAU survey of Building A, Lynchburg Research. enter,

Table 1 summarizes the exposure rates (range 8 to 11 pR/h) and radionuclide concentrations.

Uranium 235 concentrations were less than 0.3 pC1/g, and U 238 concentrations ranged from (0.4 to 2.1 pCi/g.

Cobalt 60 and Cs 137 concentrations were

<0.1 pCi/g and

<0.2 pCi/g, rsspectively; Th-232 concentrations ranged from 0.4 co 2.8 pCi/g.

Facility Survey Surface Scans A few minor areas of contamination were identified during the survey.

The areas were brought to the immediate attention of Babcock and Wilcox, and additional remedial action was performed.

Rescanning the identified areas indicated no residual elevated radiation levels.

Exposure Rate Measurements Canma exposure rate data are presented in Table 2.

The indoor measurements at one meter ranged from 13 to 29 pR/h with an average of 17 pR/h.

The exposure rate in Rnom 20 was elevated due to the presence of 7

P' packaged waste, which was stored approximately 10 meters beyond the north wall of the room.

With the exception of this area, the exposure rates in the building ranged from 13 to 19 pR/h, with an average of 16 pR/h.

Additionel measurements in April 1988 indicated exposure rates in the storage shed ranged from 63 to 130 pR/h, and 24 to 31 pR/h at six locations in Room 20 (Figure 106),

Measurement of Total and Removable Contamination Results of total and removable contamination measurements are summarized in Tables 3 (HPC areas) and 4 (LPC areas). Alpha and beta gamma levels were generally well below the release criteria, and, in many instances, less than the detection sensitivities of the procedures.

The maximum alpha measurement 2

was 400 dpm/100 cm, measured on the upper wall vent of the acn's change room.

The vent was removed by the licensee and packaged as vaste.

The maximum alpha 2

measurement after vent removal was 180 dpm/100 cm, measured on the floor of the East Vaste/ Sump tank in Room 19.

The maximum beta-gamma reading was 2

13000 dpm/100 cm, measured on the north wall of the storage shad and the east vaste/ sump tank in Room 19.

The stcrage shed (Figure 5) is located on the north wall of Building C.

Approximately 10 meters due north of the storage

shed, is a controlled access radioactive waste storage area. All beta gamma measurements in this area are elevated due to the radiation levels from the vaste.

The levels are not uniform because of shielding from materials stored in the shed.

Additional remedial action was performed in the east vaste/ sump

tank, reducing both the alpha and beta. gamma contamination levels within the NRC guidelines.

The maximum removable alpha and beta contamination levels 2

2 were 10 dpm/100 cm and 21 dpm/100 cm, respectively.

Radionuclide Concentrations in Trench Soil The radionuclide concentrations in 51 trench soil samples are presented in Table 5.

In general the concentrations are similar to baseline concentrations from the surrounding soil.

The sample from Room 1 had slight 1v elevated concentrations as follows:

Co 60, 13 pCi/g; Cs 137, 2.9 pCi/g; U 235, 0.2 pCi/g; U 238, 5.7 pCi/g; and Th 232, 0.7 pCi/g.

8

l Drain Samples The radionuclide concentrations in "cold" drain residues are presented in Table 6.

The maximum residue concentration was collected from the drain in Room 50, grid block F 1: Co 60, 0.4 pCi/g; Cs 137 0.2 pCi/g; U 235, 0.9 pCi/g; U 238, 8.3 pCi/g; and Th 232, 1.3 pCi/g.

Plutonium 238 concentrations ranged from

<0.1 to 0.2 pCi/g and Pu 239/240 concentratians rcnged from 2.4 to 4.5 pCi/g.

Swipes were collected from 9 "cold" drain lines and scanned for gross alpha and gross beta contamination.

No removable activity was detected.

Water Sample The water sample irom the pit in Room 52 was analyzed for gross alpha (60 1 10 pCi/1) and gross beta (490 1 17 pCi/1) concentratient.

Camma spectroscopy indicated the presence of natural uranium.

Roof Systematic gamma scans of the roof crea indicated generally elevated exposure rates.

The general levels decreased when going from the north to tta south edge of the roof.

This is attributed to the vaste stored along the north side of the building.

No elevated areas, which could be associated with contamination on the roof surface or other structures, were detected.

4 Results of contamination measurements on roof structures and ventilation stacks are presented in Tablo 7.

The maximum total contamination measurement 2

was 8200 dpm/100 cm, at the base of a stack on the north edge of the roof.

This measurement is elevated due to the vaste stored approximately 15 meters north.

Table 8 presents the results of radionuclide concentrations in gravel samples collected from the roof of Building C.

The concentrations were typical of natural background soil samples.

Plutonium measurements were not determined for the background soils; however, the plutonium concentrations in the gravel samples are insignificant in comparison with the soil release guidelines.

9

Outdoor Survey Surface Scans and Exposure Rate Measuroments Elevated radiation levels were found on the west, north and east sides of Building C.

A large volume of waste is stored approximately 7 noters north of the building, and elevated radiation levels from this area increased the difficulty of identifying potential surface contamination.

Figure 104 presents the direct radiation levels measured around Building C in the initial survey.

14vels ranged from 22 to 450 pR/h. A follow.up survey was performed en April 26.

Although radiation levels remained elevated, use of a shielded detector

system, a pressurized ion chamber and an in situ gamma ray spectrometry system pe rmitted ORA?) to collect additional data. Figure 105 presents isopleth exposure rate levels associated with the vaste stored in and cround Building J.

Levels outside Building C ranged from 150 to 460 pR/h (Figure 106).

Rcdionuclide Concentrations in Surface Soil The radionuclide concentrations in 16 soil samples collected around the cutside of Building C are presented in Table 9.

The concentrations are within the ranges for baseline samples from the vicinity of the Babcock and Wilcox fccility.

An additional 10 soil samples were collected during the April 1988 survey (Table 10 and Figure 107).

The concentrations are also within the rcnges for baseline samples.

Rcdionuclide Concentrations in Soil from Shallow Boreholes The radionuclide coacentrations measured in soil samples from 14 bsreholes along the vaste drain lines from Building C to the Liquid Vaste Building are presented in Table 11.

In general, the samples are within normal bcckground ranges.

However, samples 5A, 13A and 13B had Co 60 and Cs 137 i

l ccncentrations which were elevated.

The highest levels were Co 60, 1.9 pCi/g; and Cs 137, 11.5 pCi/g.

l l

10

COMPARISON OF RESULTS WITH GUIDELINES NRC surface contamination guidelines for release of facilities for unrestricted une are outlined in Appendix D.

Because the principal redionuclides of interest are plutonium, thorium, uranium, Co 60, Cs 137 and fission products, the more restrictive criteria for plutonium have been cpplied for residual contamination:

Total Contamination 300 dpa/100 cm2 (maximum in a 100 cm2 area) 100 dpa/100 cm2 (nveraged over 1 m )

2 Re:sovable Contamination 2

20 dpa/100 cm For residual beta gamma contamination, the NRC guiotlines are:

Total Contamination 15,000 dpm/100 cm2 (maximum in a 100 cm2 area) 5,000 dpm/100 cm2 (averaged over 1 m )

2 i

Removable Contamination 2

1,000 dpm/100 cm All total and removable alpha and beta gamma contamination measurements ware within these guidelines, i

l Soil sample data was compared to the NRC guideline of 10 pCi/g of natural

thorium, 30 pCi/g of total uranium, and 25 pC1/g plutonium.

All soil l

concentrations (surface and subsurface) collected inside and outside Building C were within the guideline levels.

The maximum soil concentrations for Co 60 (13 pCi/g) and Cs 137 (11.5 pCi/g) are comparable to guidelines developed by 11 l

I

the NRC (Co 60, 10 pCi/g and Cs-137, 15 pCi/g). Although the Co 60 (13 pCi/g) oxceeds the guidelines, this sample is one of three samples from the same

trench, and the average concentration over the trench length (-7 m) is 4.5 pCi/g, which meets the guidelines.

Vater sample data indicates the presence of alpha (60 pCi/1) and beta 3

(490 pCi/1) contamination, identified as uranium.

10 CFR 20, Appendix B, Tcble II provides uranium isotopic concentrations in water for unrestricted creas ranging from 30,000 to 40,000 pCi/1.

Elevated direct radiation levels associated with radioactive waste stored north of Building C, are responsible for elevated radiation levels detected in the storage shed and Room 20.

Additional data collected in April 1988, indicates that the radiation levels are directly related to the waste, not to surface contamination.

Isopleth exposure rate data generated in April correlates to exposure rates which would be attributed to the stored waste.

No evidence of anomalies are noted that would indicate surface contamination inside or outside the building. All radiation levels are within the units specified in 10 CFR 20.105 for an unrestricted area.

SUMMARY

On August 17 to September 2, 1987, and April 26, 1988, ORAU performed a confirmatory radiological survey of Building C, located at the Babcock and Ullcox Lynchburg Research Center. Lynchburg, Virginia.

The survey included surface alpha, gamma and beta gamma scans, measurement of direct and removable contamination levels, and the measurement of direct radiation levels and radionuclide concentrations in soil, gravel, and water samples.

The findings support the closeout survey performed by the licensee, and confirm that the radiological conditions satisfy the KRC guidelines established for r61 ease for unrestricted use.

12

REFERENCES 1.

Report, "Decontamination and Decommissioning of Building C Phase 1 at Lynchburg Research Center Lynchburg, Virginia," RDD:85:8604 01:01 May 1985.

Report, "Decontamination and Decommissioning of Building C Phase 2 at Lynchburg Research Center Lynchburg, Virginia," RDD:85:8604 01:02, October 1965.

Report, "Decontamination and Decommissioning of Building C Phase 3 at Lynchburg Research Center Lynchburg, Virginia," RDD:87:8604-01:03.

2.

Confirmatory Radiological Survey of the SNM 778 Area, But iding A Lynchburg Research Center Lynchburg, Virginia, by E.J. Deming, Oak Ridge Associated Universities, June 1987.

3.

Title 10, Code of Federal Regulations, Part 20, dated January 1, 1985.

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i VUERS FIGURE 74: Penthouse (Above Lcdies' Change Room) Showing Locations of Single-point Measurements 87
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FIGURE 108: Outdoor Area Showing Storm Drain and Shallow Borehole Locations
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TABLE 1 DIRECT RADIATION IIVELS AND RADIONUCLIDE CONCENTRATIONS MEASURED AT BASELINE SAMPLING LOCATIONS BABCOCK AND UILCOX COMPANY LYNCHBURG, VIRGINIA j
i I
Camna Exposure Rates Radionuclide Concentrations (pCi/g) j Location" at I e Above the Surface Co-60 Cs-137 U-238 U-235 Th-232 1
(pR/h) l b
1 11
<0.1
<0.1 2.1 11.8
<0.3 2.8 10.7 2
8
<0.1
<0.1 0.3 10.2
<0.2 0.4 t 0.2 3
10
<0.1 (0.2
<2.4
<0.2 0.9 t U.4 4
10 (0.1
<0.1
<0.4
<0.1 0.5 1 0.3 5
11
<0.1
<0.1
<l.4 (0.3 1.3 1 0.5 6
10
<0.1 (0.2
<0.8
<0.2 1.2 10.4 C
w Reproduced from ORAU report dated June 1987.2 aRefer to Figure 109.
buncertainties represent the 95% confidence level, based only on counting statistics; additional laboratory uncertainties of 1 6 to 10% have not been propagated into these data.
TABLE 2 INDOOR CA'. cia EXPOSURE RATE MEASUREMENTS BUILDING C BABCOCK AND WILCOX COMPANY LYNCMBURG, VIRGINIA Locationa pR/h at 1m Above Surface 1
17 2
29 3
17 4
17 5
~~i. 7 6~~
15 7
14 8
19 9
19 10 13 11 14 12 18 aRefer to Figust 7.
124
TABLE 3 SlMMARY & '.ARFACE CONTAMINATION DEAStREMENTS IN AREAS WI TH A HlOf PROBABILITY OF CCHTAMINATION (HFC)
DUILDIPC C BABCOCK APO WILCOX COMPANY LY?O BURG, VIRGINIA TOTAL CONTAM1 NATION Nwaber of 2
Number of Alpha (dpe/100 cm )
Beta-Geneus (dpm/100 cm )
REMOVAetE CONTAMINATION Grld Blocks location Figure Grid Blocks Highest Grld Range of Highest Grid Range of Alpha Ra Beta Ran Exceeding Surveyed Block Ave.
Measuressmts Block Ave.
Measurements (dpe/100 cm ) (dpm/100 cm )
Criterla R0rM p3 Floors / lower walls 8
2 37
<26 - 55 560
<430 - 740
<2
<5 - 12 0
Upper walls /
U ceilings 9
2 VA
<26 - 55 VA
<430 - 770
<2
<5 - 14 0
a ROOM #15 Floors / lower walls 10 15 70
<35 - 150 1600
<480 - 2200
<2 - 7
<5 4 21 0
Upper walis/
a collings 11 4
VA 44 - 97 WA
<470 - 1200
<2 - 3
<5 - 7 0
QOOM #16 Floors / lower walls 12 8
49
<35 - 70 1100
<470 - 2200
<2 - 3
<5 - 6 0
Uppper walls /
8 ceilings 13 4
VA
<35 - 79 VA
<470 - 1500
<2
<5 - 9 0
i
VABLE 5 (Continued)
SIM4ARY OF SURFACE CONTAMINATION KASUREMENTS IN AREAS WITH A HIG4 FROBABILITY & CONTAMINAfl0N IHPC)
BUILDING C BABCOOC Ato WILCOX COMPN 4Y LYPOetEG, VIRGINI A TOTAL CONTAMINATION Number of Number of AIpha (ope /100 cm2)
Beta-Canona (don /100 on2)
REMOVABLE CONTAMINATION Grid BIochs Location Figure Grid Blocks Highest Gris Range of Highest Grid Range of Alpha Ran Beta Range Exceeding Surveyed Block Ave.
Measurements Block Ave.
Measurements idpe/100 cm ) (spm/100 cm )
Criteria R@M #17 Fl ers/ lower walls 14 28 41
<l9 - 65 2000
<470 - 2300
<2 - 5
<5 - 15 0
Upper walls /
ceilings
~~15 10 MrA~~
<35 - 70 WA
<450 - 1500
<2
<S - 9 0
$ RCDM #19 Fle rs/ lower walls 16 16 34
<19 - 65 1500
<470 - 2200
<2 - 10
<5 - 8 0
Uppor walis/
a celllegs 17 7
WA
<19 - 56 WA
<470 - 2100
<2 - 3
<5 - 16 0
ROOM #19 IEast waste /
Sump Tank)
Flews / lower walls 18 3
240
<!9 - 610 2700
<440 - 13000
<2 - 3
<5 2
Ficors/ lower walls b
Resurvey 2
96
<19 - 180 3500
<440 - 11000
<2
<5 0
HCDN #19 (West Waste /
Sump Tank)
F loor/ lower walls 19 3
40
<35 - 88 920 460 - 1200
<2
<5 - 7 0
1 l
TABLE 5 (Continued)
SNRY OF StRFACE (DNTAM; NATION KASUREMENTS IN AREA 5 WITH A HIG4 PROBA8ILITY OF CONTAMINATION OFC)
BulLDitC C BAOCOCK AfD WILCOX COMPANY LY?O180RG, VIRGINIA
^
TOTAL CONTAMIMTION Number of 2
Number of Alpha (dpsm/100 cm )
Onta-Cow (opm/100 cm )
REMOVABLE COdTAMim il0N Grid Blocks location Figure Grid BlocAs Highest Grid Range of Highest Grid Range of Alpha Beta Ra Exceeding Surm A Block Ave.
Measurements Block Ave.
Measurements (ope /100 cm ) (dpm/100 cm )
Criteria ROOM 920 Floors / lower walls 20 28 61
<20 - 120 2200
<450 - 3100
<2 - 3
<5 - 14 0
g Upper walls /
e ceilings 21 12 WA
<19 - 56 WA
<430 - 3500
<2 - 5
<5-7 0
w ROOM #22 Floors / lower walls 22 4
45
<19 - 30 1100
<470 - 1900
<2
<5 0
Upper walls /
ceilings
~~23 3~~
WA
<t9 - 37 WA
<470 - 950
<2
<5 0
ROOM #26 Floors / lower walls 24 7
<26
< 19 - 65 1200
<450 - 1700
<2
<5-7 0
Upper wa1Is/
a ceilings 25 3
WA
<26 - 64 WA
<470 - 1600
<2
<5 0
1 i
.J
TABLE 3 (Continued)
~~SUMMARY~~
OF SURFACE CONTAMINATION KAStREMENTS IN AREAS wlTH A HIOi PROBA9ILITY OF CONTAMINATION ( E )
BUILDING C BAOCOCX AM) WILCCX COMPANY LP O OURG, VIRGINIA TOTAL CONTAMiNAT1ON Number of 2
Numter of AIpha (dpm/100 cm 1 Beta-Gasuas (dpa/100 cm )
REMOVABLE cod 7 AMINATION Grid OIock$
Location Figure Grid Blocks Highest Grid Range of Highest Grid Range of Alpha Beta Range Exceeding Surveyed Block Ave.
Measurements Block Ave.
Measurements (ope /100 on 3 (dpe/100 cm )
Criteria ROOM 921 Floors / lower walls 26 20 38
<!9 - 92 1100
<440 - 1500
<2 - 7
<5 - 13 0
Upper walls /
collings*
27 8
VA
<19 - 46 WA
<440 - 1700
<2 - 3
<5 - 6 0
oo ROOM #43 Floor / lower walls 28 17 33
<!9 - 56
<470
<430 - 980
<2 - 3
<5-7 0
Upper walls /
a callings 29 6
VA
<!9 - 28 N/A
<430 - 830
<2 - 3
<5 - 7 0
ROOM #50 Floor /lomar walls 30 12 29
<t9 - 47
<470
<430 - 750
<2 - 7
<5 - 10 0
Upper walls /
8 ceilings 31 6
VA
<t9 - 37 VA
<430 - 520
<2 - 3
<5 - 6 0
VABLE 3 (Con 93nued)
StM4ARY OF SLRFACE (IP4TAMINATION KASLREMENTS IN AREAS WITH A HIGH FHOBABILITY OF CONTAMINATION (FFC)
BUILDING C BABCOCX AfD WILCOX COMPANY LYNO43URG, VIRGINI A TOTAL CONTAMINATION humber of Number of A:pha idpm/100 cm2)
Beta-Csere f dp=/t00 cm2)
Rete 0VABLE CONTAMINATION C 1d 88ochs Location Figure Grid Blocks Highest Grid Range of Highest Grid Range of Alpha Ran Beta Range Enceeding 2
Survoyed B1ock Ave.
Mees ureewents B1od Avs.
Measurements (dpe/100 cm ) (dpavi00 cm )
Criteria MEN'S CHAtR ROOM Floor / lower walls 32 14 30
<19 - 73 1400
<470 - 1900
<2 - 5
<5 - 8 0
Upper walls /
G ceilings
~~33 5~~
VA
<t9 - 400 VA
<470 - 1600
<2 - 3
<5 - 7 i
Upper Walls /
collings**C 35 4
VA
<19 - 47 VA
<470 - 1100
<2 - 3
<5 0
DRflNG OVEN Floor / lower walls 34 10 44
<25 - 110 1600
<470 - 2000
<2 - 5
<5 - 12 0
Upper walls /
ceilings
~~35 3~~
VA
<26 VA
<470 - 1500
<2 - 3
<S - 7 0
HALLWAf (Area 24)
Ffoor/ lower walls 36 to 51
<26 - 73 1300
<430 - 1700
<2
<5 - 15 0
Upper walls /
ceilings
~~37 5~~
VA
<26 - 92 VA 750 - 1900
<2 - 3
<5 - 7 0
s f
k g o
c n a r
loI i
d r e B e e 0
0 0
0 b
et m
d ei u i m r N
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n 6
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5 5
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B o M
(
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s s a n y netc e i d s
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e
/
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r s e
r s n
e e o
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l a
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l a
l n ei I
A
=
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(
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/
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r ri u
/
l w
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oel G
L l
p e L
l p o C
ly st L
o pi L
opl a n n r e OA v A
F U c A
F U c s
~~b C H~~
H t
o
TABLE 4 StMWTY OF SINGLE FCINT SURFACE CONTAMINATION f(ASUREMENTS FRO
~~LOW PROBABILITY OF CONTAMINATION AREAS (LFC)~~
BulLDING C BAOCO(X APO WILCOX COMPANf LY?O(KRG, ViROIN1 A TOTAL CONTAMINATION N W of Alpha (ope /100 cm2)
Date-Cm (dpm/100 cm )
RDe0VABLE CONTAMINATION Measurements 2
trxation FIgwre Nweber of Range of Range of Alpha Range Beta Range Enceeding Measurmannt s Measurements Nasurements (dpe/100 cm#3 (dpm/100 cm )
Criteria 2
ROM 1 42 S
< 19 - 47
<470 - 610
<2 - 3
<S 0
ROOM 2 43 S
<19 - 39
<470 - 920
<2 - 9
<S - 7 0
RWM 4 44 5
<!9 - 23
< 4 70 - 740
<2
<S - 6 0
RCIN 5 45 S
<t9 - 47
<470 - 1300
<2
<S - 8 0
C ROOM 6 46 5
<19 - 25
<470 - 740
<2
<S 0
Rc34 7 47 5
<26 - 64
<430 - 1100
<2 - 3
<5 - 7 0
R0rN 8 48 5
<19 - 38
<470 - 900
<2
<S - 6 0
ROOM 9 49 5
<26 - 73
<430 - 660
<2 - 3
<S - 6 0
RCDs 10 50 5
<19
<470 - 1600
<2
<S 0
RCDs 11 51 S
<19 - 38
<470 - 1200 (2
<S 0
ROOM 12 52 5
<19 - 19 4470 - 1200
<2
<S - 7 0
RCD 4 01 53 S
<f9 - 38
<480 - 790
<2 - 3
<S - 12 0
RCM 02 "A
S
<!9 - 47
<480 - 1500
<2 - 3
<S - 8 0
ROM 05 55 5
<l9
<480 - 1100
<2
<S - 7 0
RCat 04
~~A S~~
< 19 - 47
<480 - 880
<2
<S - 7 0
RCse OS 57 5
<19 - 19
<480 - 880
<2 - 3
<5 - 7 0
ROOM 06 58 5
< 19 - 38
<480 - 620
<2
<S - 7 0
ROOM 25 59 5
<t9 - 66 750 - 1000
<2 - 7
<S - 9 0
RCDM 44 f.0 7
<t9 - 85
<470 - 1000
<2 - 3
<S - 9 0
RCIM 52 61 5
<?6 - 46
<470
<2 - 3
<S - 12 0
l, l
l' ll1 i
s t
f n g o en a mii r
ed r e r e e 0 00 000 0 000 00 0 000 0 0 b
u et m s ci u
a x r N
aE C M
)
2, e n N
g :<
O n
6 698 6 662 9 69 8
a0 1
B T
R 0 A
1 5 - - - - -
5 - 5 N
a/
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e 5
55 5 5 5 5 5 5 5 5 5
M e p A
B s T
(
N O
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g m L
n c B
a 33 7
3 3 3 3 3
A R 0 V
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0 0 0 00 0 0 0 0 000 00 O A a
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p f
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1 A O N
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m 0 0 0
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A e e 7 3 3
d I
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a g r 4 4 - - - - - - -
M A n
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T C
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M DA CX G I
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4 4 4 3 4 4 4 4 4 4 4 2 4 4 4 t
9
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1
I TABLE 4 (Con 0 laced)
StMmRY & $1NCLE 00lNT $URFACE CONTAMINATION 9(ASUREMENTS F804 LOW FHOBASILITY OF CONTAMINAfl0N AREAS (LPC)
IRJILDatC C BA8COCX MO WILCOM COMPANY LYNCH)URG, WlRGINIA TOTAL CONTAMINATION Number of Alpha (ope /100 cm2)
Beta-Ganana (dpm/100 on2)
REMOVABLE CONTAMINATION Measurements Location Figure Number of Range of Range of Alpha Range Beta Range Exceeding 2
2 Measurements Measurements Measurements (dpav100 cm ) (opsm/100 cm )
Criteria HALLWAY (AREA 25) 80 5
<26 - 82
<430 - 1400
<2 - 5
<5 - 10 0
HALLWAY (AREA 27E) 81 5
<19 - 28
<480 - 1200
<2 - 3
<5 - 15 0
C4ALLWAY ( AREA 27W) 82 3
<26
<430
<2 - 3
<5 - 6 0
ftALLwAY (AREA 57) 83 5
<19 - 28
<470 - 490
<2
<5 - 13 0
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TACLE 6 RADIONUCLIDE CONCENTRATIONS IN RESIDUE COLLECTED FROM "COLD" DRAINS BABCOCK AND VILCOX COMPANT LYNCllBURC, VIRGINIA a
Location Radionuclide Concentration (pC1/g)
Co-60 Cs-137 U-235 U-238 Th-232 Pu-238 Pu-239/240 Cl!ANCE ROOM (CR)
<0.I
<0.2
<0.8 3.4 1 2.9b
<0.6
<0.1 2.4 1 0.3 ROOM 50 (F1) 0.4 1 0.4 0.2 1 0.5 0.9 1 0.4 8.3 1 3.7 1.3 1 0.8 0.2 1 0.1 4.5 1 0.3 ROOM 50 (F4)
<0.2 0.'t 1 0.2 0.4 1 0.4 5.6 1 3.2 1.2 i 1.0
<0.1 3.3 1 0.4 C
~
CRefer to Figure 102.
bUncertainties represent the 95% confidence level, baset! only on counting statistics; additional laboratory uncertainties of i 6 to 10% have not been propagsted into these data.
i i
J TABLE 7 i
~~SUMMARY~~
OF BETA-CAMMA SURFACE CONTAMINATION MEASUREMENTS FROM THE ROOP OF BUILDING C BABCOCK AND WILCOX LYNCHBURG, VIRGINIA Locations TotalContaminagion Removable Contam{ nation (dpm/100 cm )
(dpm/100 cm )
1 3200
<5 2
510
<5 3
<500
<5 4
<500 7
5 640
<5 6
<500
<5 7
2300
<5
)
8 1600
<5
~~Refer to Figure 103.~~
l l
l
}
l 1
,o 1
138
TABLE R RADIONUCLI3E CONCENTRATIONS IN CRAVEL COLLECTED FRO'1 THE ROOF OF BUILDINC C BARCOCK AND WILCOX LYNCH 3URC, VIRCINIA
~
Radionuclide Concentration (pCi/g)
Location' Co-60 Cs-137 U-235 U-238 Th-232 Pu-233 Pu-239/240 1
<0.2
<0.1 (0.1
<1.4 (0.2 2
<0.1 1.0 2 0.2b
<0.7 1.7 1 1.3
<0.2 3
<0.1 0.3 1 0.2
<0.2
<l.4
<0.3 0.006 t 0.001c 0.006 2 0.001c 4
<0.1 0.6 t 0.2 (0.3 2.8 t 1.2
<0.3
$CRefer to Figure 103.
bUnce rt a i nit i es represent the 95% confidence level, based only on counting statistics; additional laboratory uncertainties of t 6 to 10% have not been propagated into these data.
cComposite of all samples (1-4).
i
,i "ABLE 9 RADIONUCLIDE CONCENTRATIONS IN SURFACE SOIL SAMPLES COLLECTED AROUND BUILDING C BABCOCK AND WILCOX LYNCHBURG, VIRGIN!A Radionuelfde Concentration (pCi/g)
Lecottona co-60 Cs-13/
U-235 U-238 Th-232 1
<0.1 0.2 t 0.lb
<0.4 0.f 1 0.7 1.1 1 0.3 2
(0.1 0.2 2 0.1 0.2 t 0.1 1.3 2 1.1 1.1 2 0.3 3
<0.1 0.3 1 0.1 0.3 t 0.2 1.3 2 1.1 1.3 2 0.4 4
<0.1 (0.1 (0.2 2.2 2 0.6 1.1 2 0.4 5
<0.1
<0.1 0.2
~~0.1 1.0 2 0.4 0.8 2 0.3 6~~
<0.1
<0.!
<0.2 1.0 2 0.7 0.5 2 0.2 7
<0.1 0.4 2 0.1 0.2 2 0.1 2.1 2 0.7 1.2 * ).4 8
0.2 t 0.1
<0.1 0.2 2 0.1 1.3 t 0.9 1.1 1 ).3 9
<0.1
<0.1 0.2 1 0.1 3.5 1 0.9 1.5 2 0.4 10
<0.1 0.3 2 0.1 0.3 2 0.1
<0.1 1.3 1t.4 11
<0.1
<0.1 0.2 2 0.1 3.0 1 1.4 1.6 t (.4 12
<0.1 0.3 t 0.1 0.2 1 0.1
<!.8 1.4
~~C.4 13~~
<0.1 0.3 2 0.2 0.2 1 0.1 2.8 2 0.8 1.220,3 14
<0.1 0.3 1 0.1 (0.2 1.8 2 0.7 1.5 t O. 3 15
<0.1 0.2 2 0.1
<0.5 2.5 2 0.7 1.4 2 0.4 16
<0.1 0.2 t 0.1 0.5 2 0.4 1.2 2 1.1 0.9 2 0.4 1GRofor to Figure 104
!bUncortainties represent the 95% confidence level, based only on counting statistiest l coditional laboratory uncertainties of 2 6 to 10% have not been propagated into these data.
1
'l i
1 1
1 140
~~J A~~
.A iABLE 10 RADIONUCLIDE CONCENTRATIONS IN SURFACE SOIL COLLECTED NORT!! OF BUILDING C BABCOCK AND WILCOX COMPANY LYNCHBURG, VIRGINIA a
Location Radionuclide Concentration (pCi/g)
Co-60 Cs-137 U-235 U-238 Th-232 l
l 1
<0.1 0.2 1 0.1
<0.3 1.510.7 1.510.5 2~
<0.1
<0.1
<0.3
<l.0 1.0 1 0.5 3
<0.1 0.2 1 0.1
<0.3 2.3 1 0.7 1.6 1 0.5 4
<0.1 0.3 1 0.1
<0.3
<l.0 1.3 10.4
)
5
<0.1
<0.1
<0.2 1.1 1 0.9 0.9 10.4 6
<0.1 0.2 1 0.1
<0.3
<0.9 1.3 10.4 7
<0.1 0.7 1 0.2
<0.4 2.4 i 1.9 1.4 1 0.6
[
8
<0.1
<0.1
<0.3
<l.0 0.4 9
(0.1 0.4 1 0.1
<0.3
<1.0 1.7107 10
<0.1 0.4 1 0.1
<0.3 (0.9 1.5 i C.4 aRefer to Figure 107 buntertainties represent the Via confidence level, based only on counting statistics; additional laboratories uncertainties of 16 to 10% have not been propagated into these data.
x
TABIE I1 RADIR2CLIIE CJUNIRATIGS IN SDIL FTOi SITM1 IRAIN AND SilALIIU KED01ES FBQt FDP 1EP. IfCATIOS O' MtSIE IRAIN LL43a IUIIDI!C C E.VOXX AND UIIOOK IXOFIRC, VIRGINIA R,w'iorurlide Conmntration (rCf/g) i b
location,c Co-6)
Cs-137 U-235 U-233 Th-232 lb-233 lb-239/240 1A 0.5 1 0.1d 0.610.2 0.2 1 0.1 2.5 1 0.6 0.9 10.3 2A G.1 O. I G.2
<4.8 1.1 1 0.4 3A G.1
<D.1 3).2 2.4 1 0.7 1.1 1 0.5 4A O.2 G.1 0.3 t 0.1 2.4 1 0.7 0.9 10.3 5A 1.9 1 0.3 1.8 1 0.3 0.5 1 0.5 4.0 1 2.0 1.2 1 0.5 6A O.1 O.1 0.2 1 0.I 3.3 1 0.8 1.3 1 0.4 3
6B
<0.1
<D.1 0.2 1 0.1 3.4 1 2.3 1.310.5 7A G. I G.1 0.220.I 2.6 1 0.8 1.0 1 0.5 7B
<D.1 (0.1 0.2 1 0.1 3.0 t 1.6 1.5 1 0.4 8A G.1 G.1 0.6 1 0.5 1.9 1 0.8 1.1 1 0.4 8B
<D.1
<0.1 0.2 1 0.1 4.4 1 0.8 1.410.5 9A O.1 G.1 G.2 3.1 1 1.5 1.1 1 0.4 9B G. I G.1 0.2 1 0.I 2.I 1 1.5 1.I i 0.4 0.005 1 0.003'?
0.056 : 0.010' 10 A O.2 0.1 0.3 1 0.1 1.7 C.8 1.3 10.4 l
10 B G.1 G.1
<0.2 3.1 1 0.7 1.2 1 0.6 11 7.
@.1 G.1 0.2 1 0.!
1.6 1 0.9 1.0 1 0.6 11 B W.1
<D.1 0.3 1 0.1 1.3 1 0.5 1.8 1 0.4 12 A O. I G.1 0.2 1 0.I 1.7 11.0 1.2 1 0.4 12 B
<0.1
<D.1 0.2 1 0.1
<5.3 1.0 i 0.4 13 A 0.7 t 0.2 11.5 t 0.5 GJ O.8 1.7 10.4 13 B
<D.1 4.4 1 0.3 0.4 1 0.2 2.2 i 1.1 1.5 1 0.5
TABIE I1 (ContLml)
RADIO.1 CLUE OYU'NIRATIOS IN SOIL FROI SITR1 IPAIN AND SIA! JIM IIFBHES FRm Im1R IfrATIRS (F LASIE LEAIN LIES 3 IUIIDI'C C PAfKIXK AND W11DIT LY'UELEC, VIRCINIA Ithilonuclide Concentration (pCi/g) b Incatlon,c GcKO Cs-137 U-235 U-238 Th-232 lb-238 Pu-239/240 14 A G.1 G.1 G.2 1.5 1 0.5 1.0 1 0.4 e
e 14 B G.1 G.1 0.310.1 1.4 1 0.9 0.9 1 0.5 e
e SIU71 FAIN 0-15 c:
0.1 1 0.1 0.310.1 1.2
'.5 0.2 1 0.1 C.8 1 0.2 f
f SITntFAI'd 30-45 m 0.2 1 0.1 0.3 1 0.1 OJ t
0.1 1 0.1 0.8 1 0.3 f
f C
athste drain lines ini las n etcavated, ruanui an! Inckfilled.
bPcfer to Figure 108.
C.nple A collected frm tx>ttin of lule (POO m); Saraple B collect M frm sidewall of tole (S 15 m).
S dUncertainties represent the 95% amfidence level, insed only on sounting statistics; additional laboratory (n ertsic!!es of i 6 to 10% luve mt been propagated into tNse data.
Crrposite of all sacples location 1-14.
IPlutonhn analyws wre not n9 masted on stom drain soIIca nt.
APPENDIX A PROPOSED CONFIRMATORY RADIOIDGICAL SURVEY PIAN FOR BUILDING C LYNCHBURG RESEARCH CENTER BABCOCK AND WILCOX CC:!PANY LYNCHBURG, VIRGINIA DATED JULY 16, 1987
APPENDIX A PROPOSED CdNFIRMATORY RADIOLOGICAL SURVEY PLAN FOR BUILDING C LYNCHBURG RESEARCH CENTER BABCOCK AND WILCOX COMPANY LYNCHBURG, VIRGINIA I.
Site History and Description The Lynchburg Research Center, located on the Babcock and Wilcox Comnany site, is located 16 kilometers east of Lynchburg, Virginia along the James River.
The Lynchburg Research Center is a facility used to perforn research and development studies of nuclear fuel cycles.
Building C of the Lynchburg Research Center was formerly used as a research and development f acility for urantun, thorium, and plutonium fuels. The existing structure is the result of several additions to an original laboratory constructed in 1962.
The building consisted of approximately 952.2 m2 (sauare meters) of laboratories for the handling and use of radioactive material.
Building C also contains two vaults fo rme r ly used for the storage of special nuclear naterial and two waste tanks underneath one of the laboratories.
The decommissioning of Building C occurred in three phases.
Phase I consisted of former laboratories 25 (health physics office),
26 (technician's office), 27. 43, 44, 50, 51, 52, 53, and 54 Also included were offices associated with labs 43, 44, and 50; the western portion of hallway 23; and an area known as the Old Central Stores.
Research conducted in these locations involved uranium. thortun, and plutonian solutions and powde' 9.
Phase II included forner laboratories 15, 16, and 17; of fices and hallways along the frout of the building; and of fices adjacent to labs 15 and 16 The eastern portion of hallway 23 and a connecting hallway were also included.
Projects in these locations utilized plutonion and uranium oxide powders.
Prepared under Interagency Agreement DOE No. 40-816-8 3 Fin. No. A-9076-3 hetween the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.
.fulv 16, 1487 A-1
Phase III included former laboratories 19 and 20, two waste tanks, two special nuclear material vaults, hallway 24, part of hallway 23, the change rooms for men and women, ventilation equipment, penthouse, and adjacent areas in which very little or no radioactive materials use occurred.
The primary use of these areas was for analytical chemistry on plutonium fuels.
The licensee has completed decontamination of Building C and has requested release of the facility for unrestricted use.
Oak Ridge Associated Universities (0RAU),
has been requested by the Nuclear Regulatory Commission (NRC), Region II, to conduct an independent confirmatory survey of Building C.
II.
Pu rnose The purpose of the survey is to verify the adequacy and accuracy of the licensee's final survey by providing data necessary to evaluate the radiolozical conditions of Building C,
relative to NRC guidelines for release for unrestricted use.
III. Responsibility Work described in this survey plan will be performed under the supervision of Mr.
J.D.
Berger, Manager, and Mr. G.L.
Murphy, Assistant Manager, with the Radiological Site Assessment Program of ORAU.
Site activities will be coordinated through Mr. Arne F.
Olsen, Senior License Administrator for Babcock & Wilcox's Lynchburg Research Center.
IV.
Procedure A.
Document Review 1.
ORAU will review and assess background documentation and the Babcock and Wilcox's decommissioning plans.
A-2
2.
ORAU will review documentation of final survey procedures, survey instrumentation, instrunent calibration procedures, and any other pertinent information supporting the decommissioning plan.
3.
ORAU will review the close-out survey reports by Babcock and Wilcox.
Information will be evaluated to assure that areas exceeding site guidelines were identified and have undergone decontanination.
B.
Facility Survey 1.
Gridding 1
Confirmatory measurements will be referenced to the initial grid system established by the licensee.
ORAU will reestablish this grid where necessary.
Measurenents or samples collected from ungridded surfaces will be referenced to the floor and lower wall grf d, or to prominent building features.
2.
Surf ace Scanning Accessible areas on the floors and lower walls (up to 2 m) will be surface scanned to identify and docunent locations of residual contanination using the NaI(TI) scintillation detectors for elevated gamma radiation levels and for alpha and beta-gamma contamination utilizing ZnS scintillators, G?! detectors, and gas proportional dete: tors.
Expogure rate measurements will be made I m above the surface and at representative locations throughout the building. A minimum of 12 locations will be selected for such neasurenents.
3.
Surface Contamination Measurements Measurements of total and removable alpha and beta gamna contamination will be perforned on approxinately 10% of randonly selected floor and lower wall grid biccks. One set of five direct A-3
measurements will be obtained f rom each surveyed grid block, and one smear will be taken for each set of five measurements, corresponding to the location of highest total (direct) measu rene nt.
A mininum of 30 direct measurements and snears will be obtained on accessible areas of the upper walls and ceilings.
Particular attention will be given to cracks, beams, piping, ledges, ducts, overhead crane, and other surf aces where material night settle or accumulate.
Direct neasurements and smears will be obtained at locations of elevated contact radiation levels identified by the surface scans.
4.
Additional Measurements and Sampling a.
Drains, pipes, and ventilation ducts will be scanned, and direct measurenents and smears will be obtained.
Samples of scale or residue will be collected, where possible, using standard drain cleaning equipment.
b.
Residue samples and smears will be collected from the liquid waste retention tanks.
c.
Paint scrapings will be obtained, as required, from surfaces considered representative of the f acility in general, and f rom surfaces having a high potential for surface contamination.
l l
d.
The roof will be scanned and direct neasurements, smears and/or samples will be obtained from locations of elevated contact radiation levels.
e.
Outdoor areas around the building will be scanned.
Direct measurements and soil samples will be obtained from 10-15 random locations and fron locations of elevated contact radiation levels.
A-4
f.
Subsurface soil samples will be collected from the area immediately adjacent to external drain lines between Building C and the Liquid Waste Building.
V.
Data and Sample Analysis Sanples and direct measurement data will be returned to Oak Ridge, Tennessee, for analysis and interpretation.
Soil will be analyzed by solid state gamma spectrometry.
Radioauclides of primary interest are Am-241,
~~urantun, and thorium;~~
~~however, spectra will be reviewed for other identifiable photopeaks.~~
Selected and composited samples of soil, paint, and residues will be analyzed f or An-241, plutonium, uranium, and thorium by alpha spectroscopy and/or neutron activation techniques.
Smears will be analyzed for gress alpha and beta.
Results will be compared to the l
licensee's survey findings and the NRC guidelines for release for unrestricted use (see attachment).
l t
VI.
Tentative Schedule Measurement and Sampling August 17-28, 1987 Sample Analysis August 31 - Se p t. 14, 1987 Draft Report October 30, 1987 A-5
APPENDIX B MAJOR SAMPLING AND ANALYTICAL EQUIPMENT 1
1
APPENDIX B MAJOR SAMPLING AND ANALYTICAI. EQUIPMENT The display or description of a specific product is not to be construed as cn endorsement of that product or its manufacturer by the authors or their scployer.
A.
Direct Radiation Measurements Eberline "RASCAL" Portable Ratemeter Scaler Model PRS 1 (Eberline, Santa Fe, NM)
Eberline PRM 6 Portable Ratemeter (Eberline, Santa Fe, NM)
Eberline Alpha Scintillation Detector Model AC 3 7 or AC 3 8 (Eberline, Santa Te, NM)
Eberline Beta Camma "Pancake" Detector Model HP 260 (Eberline, Santa Fe, NM)
Transpec Portable Spectroscopy System (Quantum Technology, Atlanta, GA)
EG&G ORTEC High Purity Germanium Detector Model CEM 13180 S, 13% Efficiency (EG&G ORTEC, Oak Ridge, TN) l l
Ludlum Alpha-Beta Floor Monitor Model 239-1 (Ludium, Sweetwater TX)
Ludlum Ratemeter Scaler Model 2220 (Ludlum, Sweetwater, TX)
Ludlum Ratemeter Model 16 (Sweetwater, TX) l B-1
Reuter-Stokes Pressurized Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)
Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
B.
Laboratory Analyses Low Background Alpha-Bota Counter Model LB-5110 (Tennelec, Oak Ridge, TN)
High Purity Germanium Detector Model GMX-23195 S, 234 efficiency l
(EG&G ORTEG, Oak Ridge, TN) l i
Used in conjunction with:
Lead Shield, G-16 (Gamma Products, Inc., Palos Hills, IL)
High Purity Germanium Coaxial Well Detector Model GWL 1102010-PWS S, 234 efficiency (EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G 16 (Applied Physical Technology, Atlanta, GA)
High Purity Germanium Detector Model IGC25, 25% efficiency (Princeton Gamma Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL)
Multichannel Analyzer ND 66/ND 680 System (Nuclear Data Inc., Schaumburg, IL)
Alpha Spectrometry System Tennelec Elee.tronics (Tennelec, Oak Ridge, TN)
Multichannel Analyzer Model ND 66 (Nuclear Data, Schaumburg, IL)
B-2
m.-
APPENDIX C MEASUREMENT AND ANALYTICAL PROCEDURES i
l
APPENDIX C Measurement and Analytical Procedures Surface Scans Surface scans in the facility were performed by passing the probes slowly over the surface.
The distance between the probes and the surface was ceintained at a minimum - nominally about 1 cm.
Identification of elevated 1svels was based on increases in the audible signal from the recording or indicating instrument.
Alpha and beta gamma scans of large surface areas on the floor of the facility were accomplished by use of a gas proportional floor ronitor, with a 600 cm2 sensitive area. The instrument was slowly moved in a oystematic pattern to cover 100% of the accessible area.
Combinations of datectors and instrument for the scans were:
Beta-Gamma - Pancake G-M probe with PRM 6 ratemeter.
Beta Gamma - Pancake G-M probe with PRS-1 scaler /ratemeter.
Camma
- NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM 6 ratemeter.
Alpha
- ZnS probe with PRS 1 scaler /ratemeter.
Alpha / Beta - Gas proportional floor monitor with Ludlum Model 16 ratemeter.
Alpha and Beta-gamma surface Contamination Measurements Measurements of total alpha radiation level were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC-3 7 alpha scintillation probes.
Measurements of total beta gamma radiation levels were performed using l
Eberline Model PRS 1 portable scaler /ratemeters with Model HP-260 thin window "pancake" G M probes.
Count rates (cpm) were converted to disintegration rates I
the active area of the detector.
Effective window areas were converted to 2
disintegration rates (dpm/100 cm ) by dividing the not rate by the 4
efficiency and correcting for the active area of the detector.
Effective vincow areas were 59 cm2 for the G M detectors.
The background count rate for 2nS alpha probes averaged approximately 2 cpm; the average background count rote was approximately 44 cpm for the G M detectors.
C-1
Removable Contamination Measurements Smear measurements were performed on numbered filter paper disks, 47 mm in diameter.
Smears were placed in labeled envelopes with the location and other pertinent information recorded.
Smears were counted on a low background proportional counter at the Oak Ridge laboratory.
Exposure Rate Measurements Measurements of gamma exposure rates were performed using an Eberline PRM 6 portable ratemeter with a Victoreen Model 489 55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(Tl) scintillation crystal.
Count rates were converted to exposure rates
( R/h) by cross-calibrating with a Reuter Stokes model RSS 111 pressurized ionization chamber at representative onsite locations.
Soil Sample Analysis Soil samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli beaker.
The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry and typically ranged from 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium detectors coupled to a Nuclear Data Model ND 680 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.
Spectra were reviewed I
for identifiable photopeaks which could be attributed to Babcock and Wilcox 1
l operations.
Water Sample Analysis The water sample was rough-filtered through Whatman No. 2 filter paper.
Remaining suspended solids were removed by filtration through 0.45 m membrane filter.
The filtrate was acidified by the addition of 10 ml of concentrated nitric acid.
A known volume of sample was evaporated to dryness counted for gross alpha and gross beta using a Tennelec Model LB 5100 low background proportional counter.
C-2
Alpha Spectroscopy Samples were dissolved by pyrosulfate fusion and precipitated with barium sulfate.
The barium sulfate precipitate was redissolved and the plutonium separated by liquid liquid extraction. The plutonium was 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).
Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data.
These uncertainties were calculated based on both the gross sample count levels and the associated background count levels.
L' hen the net sample count was less than the 954 statistical deviation of the background count, the sample concentration was reported as less than the detection limits of the procedure.
Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument. Additional uncertainties of i 6 to 106, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
Calibration and Quality Assurance Laboratory and field survey procedures are documented in manuals developed specifically for the Oak Ridge Associated Universities' Radiological Site l
Assessment Program.
With the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated with NBS-traceable standards.
The calibration. procedures for the portable gamma instruments were performed by comparison with an NBS calibrated pressurized ionization chamber.
C-3
V l
Quality control procedures on all instruments daily background and check source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and the EPA Quality Assurance Programs.
6 k
l C-4 9
J APPENDIX D CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BY-PRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL i
l l
L ___
CUIDELINES FOR DECONTAMINATION Oc' FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR PATERIAL U.S. Nuclear Regulatory Commission Divison of Fuel Cycle & Material Safety Washington, D.C.
20555 l
l l
l July 1982 I
The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surf aces or premises and equipment prior to abandonment or release for unrestricted use.
The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different.
The release of such f acilities or items f rom regulatory control is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless conta=ination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination or the interior of the pipes, drain lines, or ductwork.
Surface. or premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or loc tion as to make the surface inaccessible for purposes of measure =ent shall be presumed to be contaminated in excess of the limits.
4 Upon request, the Commission may authorize a licensee to relinquish possession or control of pre =ises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such l
as razing of buildings, transf er of premises to another organization l
continuing vork with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
a.
Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety aralysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment ur scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5.
Prior to release of premises for unreatricted use, the licsnsee shall make a
comprehensive radiation surv ey which establishes that contamination is within the limits specified in Table 1.
A copy of 1
D-1
the survey report shall be filed with the Division of Fuel Cycle and Material
~~Safety, USNRC, Washington, D.C.-~~
~~20555, and also the~~
~ Administrator of the NRC Regional Office having jurisdiction.
The report should be filed at least 30 days prior to the planned date of abandonment. The survey report shall:
Identify the premises, a.
b.
Show that reasonable effort has been made to eliminate residual contamination, Describe the scope of the survey and general procedures followed.
c.
d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the f acilities to confirm the survey.
1
(
D-2
TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Average c,f Maximum,d,f Removableb e,f b
b Nuclidess U-nat, U-235 U-23 8, and 5,000 dpm a/100 cm2 15,000 dpa a /100 cm2 1,000 dpa a/100 cm2 associated decay products Transuranics, Ra-226, Ra-228, 100 dpm/100 cm2 300 dpm/100 cm2 20 dpe/100 cm2 Th-230 Th-228, Pa-231, Ac-227, 1-125, 1-129 Th-nat, Th-232, Sr-90, Ra-223 1000 dpm/100 cm2 3000 dpe/100 cm2 200 dpm/100 cm2 Ra-224, U-23 2, 1-126, 1-131, 1-133 Beta gamma cuitters (nuclides 5000 dpm Sy/100 c,2 15,000 dpm By/100 cm2 1000 dpm By/100 cm2 with decay modes other than
[
alpha emission or spontaneous fission) except Sr-90 and others noted above.
~~Where surface contamination by both alpha-and beta gamma-emitting nuclides exists, the limits established for alpha-and beta gamma-emitting nuclides should apply independently.~~
b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
C Hessurements of average contaminant should not be averaged over amore than I square meter. For objects of less surface area, the average should be derived for each such object.
d 2
the maximum contamination level applies to an area of not more than 100 cm,
e The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. 'When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
I The average and maximum radiation levels associated with surface contamination resulting f rom beta-gamma emitters should not exceed 0.2 mrad /h at I cm and 1.0 mead /h at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
_

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