ML20235Z372

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Confirmatory Radiological Survey,Nuclear Matls Development Facility (Bldg T-055) Rockwell Intl,Santa Susana,Ca, Final Rept
ML20235Z372
Person / Time
Site: 07000025
Issue date: 07/31/1987
From: Styers D
OAK RIDGE ASSOCIATED UNIVERSITIES
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20235Z279 List:
References
CON-FIN-A-9076-3 NUDOCS 8710210116
Download: ML20235Z372 (72)
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{{#Wiki_filter:. p rr 1-j Ir 0) ~ n ( F 1 Prepared by i oa? Ridge Associated CONFIRMATORY. RADIOLOGICAL SURVEY-Universities Prepared for NUCLEAR MATERIALS DEVELOPMENT I U.S. Nuclear C Regulatory FACILITY (BUILDING T-055) commission's Region V Office ] Supported by ROCKWELL INTERNATIONAL l Safeguards and f l,an$'l'"' *** SANTA SUSANA, CALIFORNIA 't' Division of .nspection Programs; Office of j D.R.STYERS Inspection and Enforcement i ) i j 1 I e Radio' logical Site Assessment Program t i. Manpower Education, Research, and Training Division i FINAL REPORT JULY 1987 L i 8710210116 871007 PDR ADDCR 0700002:3 ,3 C PDR . ~ - - - - -

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CONFIRMATORY' RADIOLOGICAL SURVEY' NUCLEAR MATERIALS DEVELOPMENT FACILITY (BUILDING.T-055)- ROCKWELL INTERNATIONAL ' SANTA SUSANA, CALIFORNIA Prepared by D. R. Styers i Radiological Site' Assessment Program Manpower Education, Research, and Training. Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff! J.D. Berger G.L. Murphy R.D. Condra E.A.~Powell-M.A. Edwards R.C. Rookard F.T. Lange T.J. Sowell C.F. Weaver i Prepared for j Safeguards and Materials Programs Branch Division of Inspection Programs' 1 Office on Inspection and Enforcement U. S. Nuclear Regulatory Commission Region V Office FINAL PEPORT July 1987 I ( This report is' based on work performed under Interagency Agreement ~ DOE No. 40-816-83 NRC Fin. No. 'A-9076-3 between the' U.S. Nuclear' Regulatory -i Commission and the U.S. Depsrtment of Energy. Oak Ridge Associated Universities - performs complementary work under contract number DE-AC05-760R00033 - with the U.S. Department of Energy. I r

.w a-7~.. : [ 'l,s u -- t -[ TABLE-OF CONTENTS' Pg ,;f List of Figures -11, ' t. l List of Tables, ,1v l .....................~....z.- 1 Introduction.. 1 l ...............s. Site Description -1 , l1

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1 ..l Survey: Procedures .................L.1..- .;.t.t.. '..- 2- . j Results 6' 'O Comparison of Results with Guidelines....'.....,. .1..... .E.. 9 .c i 1 11., ~ f Summary s References.. '53 Appendices i l Appendix A: Major Sampling and Analytical Equipment ' Appendix B: Measurement and Analytical Procedures Appendix C: Guidelines for Decontamination.of Facilities'and: Equipment-i 4 Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material 1

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-?. ate, '~ ~ . Map:of Canoga Park, California Area Showing the Location 'of FIGURE 1: Rockwell International.s Nuclear Materials Development 3 Facility..........................'......- 12' j FIGURE 2: -Nuclear Materials-Development Facility Plot Plan.....'. .E. 13 q FIGURE 3: Nuclear Materials Development Laboratory -(Building T-055)- ~ Floor Plan.........................' 14-a, FIGURE 4: Grid System Established for Radiologically Pos'ted Areas 15 '16 FIGURE 5: Location of Measurements in Room ll6-Change-Room... FIGURE 6: Location of Measurements in' Room 119-Shower and Change Room. 17 -- FIGURE 7: Location of Measurements in Room 120-Airlock to Controlled Area. 1'8. FIGURE 8: Location of Measurements in Room 121-Health and Safety / .) t Counting Laboratory 19 -) ] FIGURE 9: Location of Measurements in Room 122-Photographic Darkroom... 20 FIGURE 10: Location of Measurements in Room 123-Instrument Laboratory...- 21 '1 FIGURE 11: Location of Measurements in Room 124-Chemistry Laboratory . 22 FIGURE 12: Location of Measurements in Room 125-Corridor.......... 23 FIGURE 13: Location of~ Measurement in Room 126-Process Laboratory .. '.. 24 j FIGURE 14: Location of Measurements in Room 127-Glove Box Laboratory 25 FIGURE 15: Location of Measurements in Room 129-Radioactive Exhaust Equipment Room.........~.....-.......-..-.... 26 FIGURE 16: Location of Measurements in Room 130-Airlock to Controlled Area...........................:... 27 ) i FIGURE 17: Location of Measurements in Room'131-Radioactive Materials- -l Storage Vault 28 FIGURE 18: Location of Paint Samples in Radiologically Posted: Areas. 29 FIGURE 19: Location of Interior Soil Samples from Excavated Trenches 30 i 11

4. .i 4 ^g h1 LIST OF. FIGURES '?*E* FIGURE.20: Location of Roof Surface Contamination Measurements 31 ~ FIGURE 21: Location of Exposure Rate Measurements Outside Building /- T-055 32 FIGURE 22: Location of Sampling from Waste Line Trench 33. 0 1 i i - 1 1 f 1 i { 4 i l l 111 1 - 1

4 I d LIST OF TABLES c, Pag,e,, TABLE ~ 1:' Summary of Surface Contamination Measurements'in Radiologically. Posted Areas of NMDF'..... 34 TABLE 2: Summary of Surface Contamination Measurements in Non-Radiological 17 Posted Areas:of NMDF 39 i TABLE 3: Plutonium Concentrations in Paint Samples from NMDF 46 TABLE 4: Radionuclides Concentrations in Soil Samples NMDF - Interior Trenches.. 47 TABLE 5: Radionuclides Concentrations in Soil Samples Selected for Confirmatory : Analysis NMDF - Interior Trenches......... 48 e TABLE 6: Plutonium Concentrations in Miscellaneous Residues - NMDF.. 49 j i -I TABLE 7: Summary of Surface Contamination Measurements from Roof l Locations and Exhadst Vents of NMDF ] 50 TABLE 8: Summary of Exposure Rate Measurements - NMDF....... 51 I i TABLE 9: Radionuclides Concentrations in Soil Samples from Exterior a j Trench - NMDF 52 l d 6 I iv -i )

.3 .r . c: o. i CONFIRMATORY RADIOLOGICAL SURVEY NUCLEAR MATERIALS-DEVELOPMENT FACILITY (BUILDING T-055) } f ROCKWELL INTERNATIONAL SANTA SUSANA, CALIFORNIA q INTRODUCTION 1 The' Nuclear Materials Development Facility, also known as Building :T-055, was designed, constructed, and operated.' by.the Rocketdyne Division of Rockwell-1 International Corporation for research,.- development, and -. production of nuclear ^" fuels and radioactive sources. - The final products were solid' ' reactor, fuel; materials, radionuclides heat : sources, -and other radioactive.' sources.-

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materials for these projects included; various forms l of plutonium and ' depleted uranium. Operation of the facility began in April 1956. and. continued under Nuclear' - Regulatory Commission (NRC) license ' number SNM-21, until November 1982.- At this time decontamination' and decommissioning of the facility.'were initiated by.- Rockwell International. Cleanup was completed in-August 1986 and a report to the NRC in December 1986 indicates that the facility meets the requirements 'for release from licensing restrictions.I l At the request of NRC' Region V, the Radiological Site Assessmen: ?rogram of Oak Ridge Associated ' Universities (ORAU) conducted a confirmatory radiological survey during February 2 thru 13,1987. This report describes the-procedures and results of that survey. SITE DESCRIPTION The Nuclear Materials Development Facility (NMDF) is located : at Rockwell International Corporation's Santa Susana Field Laboratories, northwesti: of Canoga Park, California (Figure 1). The facility consists of 'a' 61 mx 18 m, single-story building on. approximately 0.5 ha of land '(Figure 2). Buildingi j construction is of 15 cm precast concrete slab walls on a' concrete slab; the. roof-is lightweight. concrete, supported on steel deck panels and girders.' - The entire c, f acility was designed as a controlled access area; although, the ' building was 1

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t i divided into posted (radiologically controlled) and nonposte'd (nonradiologically controlled) areas (Figure 3). The building housed an' administration area, change l i rooms, chemistry and service laboratories, glove' box room, vault, and maintenance 1 equipment rooms. A liquid waste holding tank and concrete retention well were 4 located southeast of the building. During decontamination, all contaminated equipment and surfaces, drain lines, and ventilation ducts were removed from the facility. The waste holding i tank was removed, and the retention well was decontaminated. SURVEY PROCEDURES Obiective The objective of the survey was to determine the radiological conditions of the site, relative to the licensee's data and the NRC guidelines for release for unrestricted use. Radiological information obtained included: L. direct radiation levels inside and outside the building, 2. contamination levels on building surfaces, and 3. concentrations of radionuclides d.n surfact and subsurf ace soil. l l ?roceduret i Document Review Rockvell's final survey report and suppor:tt$ docucan:Atic; concmry.ng decontamination and decommissioning of the NMCf vera reviewed. i Facility Survey i Gridding i ? 1 Confirmatory measurements we re referenced to a grid system established by 3 l ORAU. A2mx 2 m grid was established on the floors and lower walls in the radiologically posted areas of Building T-055 (Figure 4). The unposted areas and i 2

rooms with a floor area ' f less than-10 m2 o were not gridded, Measurements and esmples from ungridded surfaces were referenced to the floor and lower grid, or to pertinent building features. I Surface Scans Alpha, beta gamma, and gamma scans were performed on floors, using an alpha / beta gas proportional floor monitor and NaI(T1) gamma scintillation detectors. Floor surfaces not accessable to the floor monitor, lower walls (up j to 2 m), upper walls, ceilings, and overhead surfaces such as ledges, beams, l piping, fixtures, equipment, and ductwork were scanned using hand held alpha and l l beta gamma detectors. Areas of elevated, radiation levels were marked for 1 additional measurements. Measurement of ' Surface Contamination $evels s l Sixty-three grid blocks on the floors and lower walls in the radiologically controlled areas of the NMDF were randomly selected for surface contamination measu rement s. ' Measurements of total alpha and beta-gamma contamination levels were systematically perf ormed at the center and four points, midway betwe'en the center and corners of each of the grid blocks. Smears for removable alpha and bete contam. nation were perf ormed at the location in each grid block having the i highes: direct s1 pac reading. Total and removable contamination levels were also sensured at 90 1.o ce:f.ont et the upper walls, ceilings, and miscellaneous overhead e,' ecn. Ten :. ate:f.ons or the roo3, sneluding roof erhaust vents, were selected ?n msu.nmn:. k

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Locations of surf ace contasiaation masuramnes are indicated on Tigares 5 i through 17 1 l ) l 1 I 3 8 3

1 Exposure Rate Measurements Gamma exposure rates at one meter above the floor were measured throughout the facility, using a NaI(T1) gamma scintillation detector and ratemeter, cross-calibrated with a pressurized ionization chamber (PIC). I i Paint Sampling 2 Seventeen paint samples were collected from approximately 200 cm areas of the walls, at rendem locations throughout the facility, using commercial paint stripper (Figure 18). j i Soil Sampling I i Six soil samples were collected from the backfilled trench, dug to remove contaminated subfloor drain lines (Figure 19). In addition, five samples, ~ s Ii collected by Rockwell from the excavated trench before backfi111ng, were obtained ,l for independent, confirmatory analyses. l Miscellaneous Media Sampling k 1 Samples of residue were obtained from four anchor bolt holes in the floor of I the radiologically controlled area of the building, using moistened cotton swabs; samples of dust were also collected from a trench, an air duct, and a ceiling j f area. ] Outside Area Survey Surface Scans i l l Surface scans of the outside area adjacent to the building were performed using MaI(TI) gamma scintillation detectors and ratemeters. 1 Roof j l Beta gamma and gamma scans were conducted on the roof, exhaust vents, and gutters of t.he NMDF (Figure 20). l 4 1 \\ ~

Waste Tank Area Alpha, beta-gamma,. and - gamma sc::ns of the waste tank retention well were. ~ conducted. Total and removable alpha.end beta gamma contamination levels were ) 1 measured on retention well surf aces. 1 Exposure Rate Measurements l r I l q Gamma exposure rates at one meter above the surface were measured at j eight locations (Figure 21) in the vicinity of the building. e Soil Sampling Seven shallow boreholes (up to one meter) were dug in the backfilled trench area leading to the liquid waste retention well (Figure 22). Subsurface soil q samples were collected from each borehole at the interface between the backfill material and the bottom of the criginal excavation. Water Sampling A water sample was collected from the waste tank retention well. l Sample Analysis and Interpretation of Resulto i Smears for the determination of removable contamination were counted for l gross alpha and beta activity. Soils were analyzed by gamma spectroscopy for uranium 235/238, americium 241, and other identifiable-photopeaks. Paint samples, soils, and miscellaneous residues were analyzed for isotopic plutonium. The water sample was' analyzed for gross alpha ~ and gross beta concentrations. Major analytical equipment used in support of this survey is listed in Appendix A, while Appendix B describes the measurement and analytical procedures. j Results were compared with guidelines established by the Nuclear Regulatory .l Commission for release of facilities for unrestricted use (Appendix C). a 5

1 1 RESULTS l l l Document Review Rockwell's decommissioning plan appears adequately developed and implemented 1 to ensure that NRC guidelines were met. ORAU's review indicates that the procedures and instrumentation were consistent with industry accepted practices, and that the data support the final conclusions of the report. / ) Facility Survey \\ Surface Scans l No areas of elevated beta gamma or gamma contamination were identified by building surface scans. One small area of elevated direct alpha activity was identified in Room 127, at grid coordinate ON, 10.5E along the south wall } (Figure 14). Measurement of Surface Contamination Levels i i Table 1 summarizes the results of surface contamination measurements i performed in the radiologically controlled areas of Bu11 ding. T-055. The total contamination data presented in this table are direct measurements which include \\ removable and non-removable activity. The total alpha activity ranged from a minimum detectable activity (MDA) of 18 to 390 dpm/100 cm. The maximum alpha 2 level (south wall of Room 127 at ON, 10.5E) was reduced to 120 dpm/100 cm2 after a smear was taken. All other measurements indicated total alpha levels below 2 100 dpm/100 cm, l The highest average grid block results (64 dpm/100 cm ) for alpha activity 2 occurred along the lower east wall (24N, 18.4E) of Room 127. Removable alpha 2 activity ranged f rom a MDA of 3 to 140 dpm/100 cm. The maximum removable alpha I level cecurred along the south wall of Room 127 (ON, 10.5E); a resurvey of this location after cleanup indicated a MDA of 3 dpm/100 cm. The total beta activity 2 2 ranged from a MDA of 480 to 3900 dpm/100 cm. The maximum individual measurement and highest grid block average (1700 dpm/100 cm ) occurred in Room 126 at 2 coordinates 30N, OE. Removable beta activity ranged from a MDA of 6 to 2 23 dpm/100 cm, I 6 \\

Table 2 presents the results of the surface contamination measurements performed in the non-radiologically controlled areas' of the ' building. The total ) 2 alpha activity ranged from. a MDA of 22 to 110 dpm/100 cm. The highest total 1 alpha activity was. measured near the floor drain -in. Room.109. . All smears for 3 2 removable alpha activity were less than the MDA of 3'dpm/100 cm. The total beta 2 activity' ranged from a MDA of 450 to 1400 dpm/100 cm. The maximum total. beta activity was measured along the lower east _ wall of Room 101 and.on a sink top in 4 Room 110. Smears for the determination -of removable _ beta activity ranged from a 2 MDA of 6 to 10 dpm/100 cm, q Exposure Rate Measurement 1 j Exposure rate measurements inside Building T-055 ranged from 12 to '14 ' uR/h at one' meter above the surface. Paint Samples ~ i Plutonium concentrations in paint samples are presented in Table 3. Isotopic plutonium analyses revealed that the concentration of Pu-238 for all 2 samples were less than 1 dpm/100 cm, while the concentration ' of Pu-239/240 2 ranged from an MDA of 1 to 2 dpm/100 cm, Radionuclides Concentrations in Trench Soil Table 4 presents the results of the analyses performed on soil samples from excavated drain line trenches. With the. exception of locations 1 : and 2, the trenches had been backfilled ' with the original material taken from the trench. Because the soil had been mixed before and during backfilling, surface samples were considered representative of the average conditions of the ' backfill material. In most cases, the measured concentrations ' of the radionuclides of concern were less than the minimum detectable levels for that radionuclides. The concentrations are typical of these normally associated with surface soil samples. }' sq N h___m _a

O } 1 i Radionuclides Concentrations in Confirmatory Soil Sample 2 l Five soil ?amples, originally collected by the licensee from areas near the e i interior drain line, were chosen by ORAU for confirmatory analyses (Table 5). ) ORAU analyzed these samples by gamma spectroscopy techniques and wet chemist:fy for isotopic plutonium. Concentrations measured by ORAU were: U-235, <0.36 to <0.46 pCi/g; U-238, 1.7 to 5.1 pC1/g; Am-241, <0.11 to <0.13 pCi/g; Pu-238, <0.01 to 0.01 pCi/g; and Pu-239/240, <0.01 to 0.06 pC1/g. Rockwell did 5 not analyze those samples for uranium or Am-241; plutonium concentrations measured by the licensee were: Pu-238, 0.0003 to 0.0552 pC1/g and Pu-239/$40, 0.0007 to 0.6130 pCi/g. Both sets of analyses demonstrate that no significant concentrations of radionuclides are present in the trench soil. ) l Plutonium Concentrations in Miscellaneous Residue Samples Table 6 presents the results of plutonium analyses on residues from anchor bolt holes and other facility locations. Plutonium-238 content ranged from 0.1 to 0.5 pC1; Pu-239/240 content was 0.2 to 2.1 pCi. Outside Area Survey Surf ace Scans i No locations of elevated direct radiation levels were identified by gamma scans of the areas within 10 meters of the building, in the adjacent parking lots ] and drainage ditches, or in the waste retention well. l l Roof Survey The results of the contamination measurements on roof surfaces and exhaust i ventilation equipment are presented in Table 7. The hightest total contamination ] 2 2 measurements were: 120 dpm/100 cm alpha, and 890 dpm/100 cm beta gamma. The i smear analyses for removable contamination showed that the results were less than 1 the minimum detectable activity of 3 dpm/100 cm2 2 alpha, and 6 dpm/100 cm beta. l 8

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,~ .. Was te. Tank ' Area d l A Jg - Exposure! rates - in the retention ~well ranged 1 from 12 ;to 16' pR/h.' LNo ~ ~ locations - of elevate'd 'alphh, beta gamma. oragamma - radiation were noted. ' Total-1 '{' alpha measurements. ranged from a MDA of122 to 49 dpm/100 em ; removable alpha ;was 2 2 less than.the MDA of. 3 dpm/100' cm,\\. Total and removable b' eta gamma levels were. 2 2 .p 470 tol1200 dom /100Lem and less than a MDA~of.6 dpm/100 cm,,,,p,,ggy,77, .t 1 Exposure Rate Measurements ,f 4 J

The exposure rates measured at one meter abovef the surface ranged' from -12 to 14 nR/h (Table 8); this is comparable to the - background
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~ typicalLof the' middle California region. 1 4 Radionuclides Concentrations in Soil' Samples l ti Results of analyses on soil samples from - the outside drainline trenches' are : j presented in Table 9. Only photopeaks associated with naturally. occurring 1 radionuclides were detected and concentrations 3 were : generally : less. than the ' l l measurement sensitivities. The seven : samples were composited and the plutonium. concentrations were found to s be 0.01 pCi/g for. Pu-238 and was 'O.04. pC1/g.' for ~ Pu-239/240. j ,e Water Sample j

L The gross alpha and gross beta concentrations-in the water sample from the l

liquid waste retention well were 3.1 2 1.0 pCi/l '(picoeuries per liter) and g D 95.3 3.0 pC1/1, respectively. [t COMPARISON OF RESULTS WITH GUIDELINES NRC surface contamination guidelines for release of ' facilities for; unrestricted use are presented in Appendix C. The principal radioactive materials in this facility were plutonium and uranium. The~ guidelines for-plutonium alpha! contamination are the-most restrictive.and have been used for 'the NMDF' __ -M ~ '~~

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1 }y p 6 p 1-l . -s a. ,V \\ 4_: decommissioning'. These guidelines lare:. r V i.C e , 4 Totol Alpha Contamination-4 - .300 dpm/100 cm2 (maximum in aV100' cm l area)$ 2 100'dpm/100'cm2 (averaged over l'm ) d 2 j l', ' ~ Removable Alpha Contamination s 1 h 2 -[ (20'dpm/100 cm In addition to the alpha contamination ' guidelines', the: results were compared with. the: following NRC guidelines for beta gaarna contamination: '{ n Total Beta-gamma' Contamination: 'j +n s i \\ 15,000 dpm/100 cm2 (maximum:in ~a '.100 cm. area), 2 2 2 5,000 dpm/100 cm :(averaged.over 1~m ) + ,y s 1 Removable Beta gamma Contamination 2 1,000 dpm/100.cm i A review of survey results indicates that 'all. surface contamination levels are 'within the alpna and beta gamma guidelines. Soil samples, collected in and around i the < NMDF,. were compared to ' the. NRC j. guidelines for depleted. uranium (35. pci/g). ands for total plutonium.'(25 pCi/g). 'All samp'le s had concentrations well within these levels." In addition, ORAU's - \\

j analyses on the - samples collegted by the licensee. support ' the ' licensee 's.' sample data of no significant contamination, given the. inherent variability'of' sampling non-homogeneous materials and the very low concentrations being measur'ed.

tq .s The exposure. rate criteria for the site As 10 pR/h above background ~ at one meter above the surface. The average background determined in the ' area was-12 pR/h, giving a total' guideline level.of 22 pR/h. The exposure rate ' guideline ' q was met by all; measurements performed. 10 ,...e _ - ' - - - ^ - - - - ^ - - ' - - - - - " " - - - - - - - - ' ' '

[- i ? ' The water sample-collected from the liquid waste ' retention well was : compared: to the Environmental Protection Agency.(EPA).' drinking water ' screening' guidelines n. i, of 15 pC1/1, gross alpha, and 50 pC1/1, gross beta. 'The gross alpha result'was approximately 20% of the EPA value, while the ' gross : beta' concentration was .j ,7 approximately twice the EPA value. The elevated beta concentration is believed f q due to natural activity-leached from the concrete. (It should also 'be noted that - 'l the EPA drinking water guidelines are used only for comparison purposes. and 'are. '9 r; t.:i not applicable to this site, because the water -is not used for J a community. i drinking water system). i

SUMMARY

. d 'l At the request of the Nuclear Regulatory Commission, Region.V10ffice, <J . Oak Ridge Associated Universities conducted.a confirmatory radiological survey of Rockwell International Corporation's Nuclear Materials' Development -Facility. 1 (Building T-055), located in Santa Susana, California. Based on the results of I -l I this survey and a review of the decommissioning documentation, ~ it is ' 0RAU's i! I opinion that the remedial action has been effective in satisfying the NRC's 1 radiological guidelines for release for unrestricted use and that the documentation accurately describes the radiological status of the NMDF. ) ,o l 1 E 4 T .~, 11

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f O 5 PotNT WEASUREWENTS -' SINGLE POINT MEASUREMENTS-4 CDUNG o UPPER WALL N - 0 4 0 ~1-1 I METE 95 i FIGURE 11: Location of. Measurements in-Room 124-Chemistry Laboratory 3 q 22' i e q ___---_-_____J

m m ~ n 1g S m R I E Nl T E 0g M i U . S S . T T T N N A M oM G w E l E W N a i1 R E PE N E T R R uP NU EU I l OS LS E P PA G A C U m N E NE SM SM a o I s n i I l 0 s m t n 7 2 e O m O a e ~ r r C / uo '/ .~ sd ai r er / s Mo - C O f - o5 / 2 s / n a 1 o / i am t f co m 5 \\ k oo s LR \\ \\ \\ \\ t \\ / 2 m 1 A o E / 1 R U m G I F u ~ O g \\x l m c n c c m

-v. 's.. X r.' I, l .g .ll-i o ~ g\\ 4 g x q.. l .Q t 4 5 POINT ~ ' P' MEASUREMENTS i-SINGLE POINT MEASUREMENTS - ) o a CEluNC ' o UPPER WALL .j N-h - t-0 1 l l METERS i l 1 'i .t.' i L. FIGURE 13: Location of Measurements in Room '126-Process Laboratory 2 4 --

o +. I C O {,. p.'- 5 \\

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l \\. \\. MEZZANINE AREA g g OVE5t 8t00M 128 7 0 3 (3.5M. DEEP) s -Q ._a \\ o -q o . 7 H A ~ i O d \\ o i o i 7

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\\ NN Q i i \\ A q AREA.0F ELEVATED. 1 \\ ALPHA ACTIVITY O u A IDENTIFIED BY SURFACE SCANS 5 POINT A o \\ MEASUREMENTS - 7 A SINGLE POINT MEASUREMENTS o 7 4 COUNG i s L o UPPER WALL v I N \\ {o 'N s ma a n 4 \\ 0 1 METERS O f FIGURE 14: Location of Measurements in Room 127-Glove Box Laboratory 25 O _...___m__m-

) o O 4 N N N \\ \\. l A \\ N" ~ j l 'N TO AIR VENT \\ \\ N\\ \\ 5 PGNT MEASUREMENTS \\ SNGLE PolNT \\ MEASUREMENTS 4 COUNG o UPPER WALL ] N Ji h l 0 1 1 i f i uErtRs FIGURE 15: Location of Measurements in Room 129-Radioactive Exhaust Equipment Room 26 -_____________________-__m

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i o .N N\\ - i' \\ s. [.. O 1.. a. L \\ 5 PolNT -' MEASUREMENTS \\ , MEASUREMENTS. - SINGLE' POINT. - 'A CEluNC f.- o UPPER WALL. N 0'. 4 O 1 r:< 1_ I .t.1 4 METERS n., c -) FIGURE 16: Location of Measurements in Rcom 130- Airlock to Controlled Area r. 27

2.

r-9 ?. h n -l ' r:- ~ O \\ i yx i 5 POINT MEASUREMENTS 5%CLE PotNT - MEASUREMENTS A CEluNC o UPPER WALL. 4 N n 0 1 1 I METERS v .d FIGURE 17: Location of Measurements 'in Room 131-Radioactive Materials Storage Vault 28 --_--a----_

l 3

i; 199l120l i sees I i 125 1 1 3 y I s . - ~ 7) Os ,f 126 'Q 123 124 g .;a b n. .1 g_ ,j t 127 l '.i lI 1 f l 6 l @131 g g PAINT SAMPUNG f , g., O LOCATIONS q l; l l l i n. J l l>. 130 129 0 2 I I METERS 4 TDG G A -l ) FIGURE 18: Location of Paint Samples in Radiologically Posted Areas l l> 29 ~ 1 1

'] I i I owoom 119 l130 I r-a A 125 _ TO x x x x N+A x x ig Ah. EXTERIOR TRENCH I s s 123 124 ~- s 131x x u l l j i 127 J i 131 g_w;n 50ll SAMPUNG r LOCATIONS N d' 130 129 0 2 l l METERS L '- FIGURE 19: Location of Interior Soil Samples from Excavated Trenches 30 I

pm ? i M. l e l' i 'YENT W.NT o l' B 6. I n. SAMPUNG _g LOCATIONS 3 H 1 vcur a y n ~ ~ ROOF /*"*$ ff 63 utn.as FIGURE 20: Location of Roof Surface Contamination Measurements 31 -___________m_ _.-s_

) ' @ ~ @ $ s'uR h tNTf u i E n // ASPHALT 1' +--+- FENCE BUILDING [. T-055 N 3 / h r 1 l M )c 3 7 O S l METERS I / / l.... l N"Ro" l E E,TAcx// " //eW~' *n%N / 2 / m. PAD / PIT j l l l FIGURE 21: Location of Exposure Rate Measurements Outside Building T-055 32 'I

[.,.. l e. i na e o u v v v 3 ,c I BOREHOLE SAMPUNG J Oj ~ n7 /, v LOCATIONS y o // ASPHALT l f 17 ] x x { / X X FENCE BUILDING T-055 g (3b d 7 !?, C5T o 3 l 1 weTras ) Y (j) / f &$c^? tenon v o o c-n PAD / PIT l l J l i i FIGURE 22: Location of Sompling from Waste Line Trench i 33 '~ .l j

u i x N 'r E C'r G ^ . k e N g s O n a I e T R 0 ~ 7 A I 'a 0 6 6 6 6 6 N t M e ai J 6 t / A B p T d U N ( O C b e E g a L n c 7' B a A R 0 '5 V 0 3 3 3 3 3 O a 1 3 M h / R lp e E p A d( = N I S' T s N b t 0 E m f n 0 0 30 M F a o e 3 2 E D m 7 0 1 0 8 0 R M 0 e e 4 4 4 U N 0 g r 0 4 0 4 0 4 S 1 n u 4 4 4 A F A A l / a s 4 4 4 KO L a R a d p e S N iR d. M t N A 1 F 0 O ( / O E d' I R T I a T A A L m A N A N m r g 0 a 0 a '0 i 1 N D R C I G A 5 n 8 n 6 n a O e G v 7 / 4 / 5 / E I E E M T T T t L A S N A A a s k B T O I N N t e c A N P A T O L S I e h o M ig l B C Y L U B L W$ T H E L N C A K A O A C C T C s F I O N t R G R A L f n U O S A ) o e 5 9 2 2 6 2 S L T m 4 8 6 6 3 6 O O m e e F I T c g r 5 5 8 5 5 5 O D n u 2 4 1 2 2 2 A 0 a s Y R 0 R a R 1 e A / M 4 e M p d t d l S ( r g d a G v a a a h A 2 / 1 / 8 / lp t 3 n 4 n 2 n s k A e c h o g l B i H s f k o c d o e r l y e B e ~ b v 2 3 2 5 2 5 m d r u i u N r S b h b G s s s I l i l l l e a a w ' w w r/ r/ r / e sc e sC e Isc w i s w i s w s ol g e l e n lol g oig e n n / wI / wi l e n / wi o s 8 s l s l 6 r r1 9 r rl 0 r ri i t 1 o e e 1 o e o 2 o e e o p c a 1 o p c o p c 1 1 c l p l U M F U p F l p o M 'I U l i L O e O O 0 O R R R U 1 ~ r' r

u x r i N r E C G eb N g m O I n c a T R 0 7 A 0 6 6 6 6 6 N a 1 6 ~< l t / l e e M B p T d N ( O C b e E g m L n c B a A R 0 V 0 3 3 3 3 3 3 0 e 1 D lp e e h / R p A d( N I S _2) t 0 0 T s N EF o o e 0 0 n f n 0 0 0 1 0 3 0 E D m 1 4 1 4 8 8 R M 0 e e 4 4 4 U N 0 g r 0 0 0 S 1 n u 4 4 4 A F A A I / a s 4 4 4 L' MO a R a ) S N R d M N p e d G A 0 O E 1 O i e I R T F u i T A A I = d _ c n L = i A N A N = r g 0 a 0 a 0 a t N DR C 0 a G v 1 / 0 / 2 / ( T O I A A a s ~k n E E o IMT T 71 A A 8 n 7 n 6 n t .. s C A S N N N N P A I t e c e h o I O L S M B g l C Y L U A i B H. E L E S T L E L W N B C A K A O A A C C T C s T F I O N t R G R A L f n U O S A ) o e 4 6 4 1 2 2 S L T 2 m 5 3 5 7 6 6 O O n e e F I T a g r 5 5 5 5 8 8 O D n u 2 2 2 2 l A 0 a s Y R 0 R e R 1 e A / M M m M p L d i g d S ( r e G v a a a h A 5 / / 1 / 1 Alp t 3 n 3 n '4 n r k e c h lo g i B H s f k o c d o e Bl e r y e b v 2 5 2 5 '2 5 m d r u i u ^ N r S b b b G s s s I l l i l l a a a w. w w r / r/ ' - r/. e sC e lol g oiIsC esc w l s w s wI s g n / wi l e n loi g e n e a i 1 r ril / wi / wt s o s s l 3' r rll 2 r rl t 2 o e e 2 o e o 2 o e e a 1 o p c 1 o p c l p o p c 1 c l p l U M F U o p 4 F U M F L 0 O O 0 O O R R R w" 5

d c u i x r 7 N r E C G h e ~ N g n +. O n a I a T R 0 9 A 0 6 6 6 6 6 N e 1 I t / 6 M o e A B p T d N ( O C . b e E g a L n c B a A R 0 V 0 3 3 3 3 3 3 O e 1 M h / E n R lp ep A d( N I 7 S _ 7 T s 2 N b t 0 0 0 E a f n 0 0 0 M F c o e 6 0 4 '0 9 0 E 0 m R P 1 8 0 e e 4 1 4 3 4 4 4 U N 0 g r 0 0 0 S 1 n u 8 4 4 A F A L I / a s 4 4 4 EO e R a A N p e ) S N R d M O O ( d N A I F e O E u R T I e d n TI A A L m f i A N A N m r g 0 a 0 a 0 a t N D R C I G A 9 n 9 n 7 n O e G v 8 / 8 / 0 / n IMT T T t E E o 1 C A S N A A a s k ( T O I N N t e c N P A I e h o 1 O L S M B g l C Y L U A i B E L E S T H L E L W N B C A K A O C A A I C T C s T F O N t R G R A L f n U O S A ) o e 1 4 9 2 0 4 S L T m 7 4 8 6 8 5 0 O n e e F l T o g r 8 O D n u 1 8 8 5 8 5 1 1 2 A 0 a s l 2 Y R 0 R a _ q. R 1 e A / M 4 e M p t d d S ( i r g a G v a a a h A 3 / 2 / 4 / __ g. lp t 4 n 6 n 4 n A e c s k h o g l B i H s f k o c d o r l e y e B e b v 3 6 4 8 4 7 m d r u i u N r S D b b G s s l i s l l a I i e s w w u r/ r/ 'r / e sc e sC e sC w l s w I s w I s n lol g oi g o s l / ui loi g a n / w i I m n e n s l / wI s l i 4 r ri 5 r rl 6 r rl t 2 o e e 2 o e o 2 o e e a 1 o p c I o p c 1 o M F U M F lo p c c l p 1 U 4 F U p p _ s. L O O 0 O O 0 R R R u* __ s l

N r E C ~ - G b 7' N g a ~ e O n 0 8 I a ' c 3 0 1 ~ 2 1 T R 0 ~ 6 6 7 A 0 N a 1 6 6 6 6 I t / i M e e A B p g-~ T ~ (d N O C ~ k e E g a ~_ B e 4 L a c 0 A R 0 1 3 3 3 3 3 M h / VO ~ 0 2 a 1 3 R lp s E p A d ( N I S T N b s ~ t 0 0 0 0 0 E - a f n 0 0 0 3 0 M F c o e 0 3 3 8 5 0 E D m 2 1 1 1 8 R M O e e 4 U N D g r 0 0 0 0 0 S I n u 4 2 5 8 8 A F A M A I / a s 4 4 4 4 4 E O L m R a + N p e ) S N R d M d N A I F O O ( e O E u I R T I e d ~,t I E E I G A 0 / 9 / 0 / n T A A L m i A N A N m r g i 0' t N D R C O e G v ( T O I N N t e c 1 a 0 a 0 a no M T T T t 2 n 9 n 1 n C A S N A A a s k 1 N P A I B g l e h o I O L S M C Y L U A i B L E S T H L L W N B A A O A AC GT C s T f I O N t ~6 4 R G R A L f n '0 0 2 4 U O S A ) o e 9 8 8 8 6 4 S L T m 3 0 O m e e F l T c g r 8 8 8 8 e 8 O D n u l 1 t t l 1 A 0 a s ( c R 1 e Y R 0 R a A / M - r M m M p G U d d S ( i r g a G v lp t h A G a a s k 4 / 7 f 4 / ig l i A e c 6 n 3 o 3 n h o s. B , H s f k o c d r lo e ^ y e B e b v 9 0 6 7 3 6 3-L m d r 2 3 u i u ~ H r S G c e, b b b s s s l l I l l l a a e 1 w w w e, r / r / r/ - n e sc e o w l s w 1sc e sc s w i s f lol g oig ol g l f a n e n / wi 9 l wI 0 /l e n e / wi c 2 s l 2 s l 3 s .l 2 o L o e e o e e o e o 1 r rl i r rl 1 r rl M o p c M l p 0 l p o p c 4 o p c O l p - O F U 0 F U O O F U R R R ~ _ s u" ,a

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u i x r N r E C G v4 ) e ,4 N g m 0 n c 1 a T R 0 9 0 A 0 6 6 0 N a 1 6 0 M e e 1 l t / r A B p T d r-N ( e O C 'e b E g a L n c B a A R 0 V 0 3 3 3 0 O a 1 2 M h / R lp s E p A d ( l N i I e c-l S ba T 3 s N 2 T t 0 0 0 E m f n 0 6 0 f MF c o e 3 8 0 0 o 0 m E 1 2 0 R 4 0 e e 0 d U 0 g r 0 0 0 5 n f S 1 n u 4 6 4 1 y-A F A e E O L I / a s 4 7 4 a R a t M A N p e a ) S N R d M d N A O O ( u I R T I a d d e O E I F e n T A A L n i t A N A N m r g 0 a 0 0 e u n i t N D R C OI G A a G v 0 / 0 0 s n I E E 1 n 2 0 e o M T T T t 1 1 5 r C A S N A A a s k p ( T O I N I e h o N f e c N P A I O L S M B ig l ta C T L U A B i E L E S T H a L E L W N d B C A ( A O A A C 0T C s l T F I 0 N t a R G t A L f n 0 n t U O S A ) o e 4 4 2 i S L T m 5 5 1 f 0 O O m e e 0 h F I T c g r 8 1 l i 8 8 3 t O D n u 1 A 0 a s w T R 0 R a R e 1 A t / M d e e p y t d d e S v ( i g r r a G v u a 0 s h A 6 / 4 0 e a< 1p t 3 n 6 1 r s k A e c h o a .e ig l 6 r B H 2 A 1 m. s o d f k o e .t o c d r m o r r l e ) r c y n ef e B e o 9 v r b v 3 2 i 2 e e m d r t s p u u N i S b i b 7 s n e n a .t r G s d s 1 t e e o l e l - e e e ct m l n m .ri l a e a m rl c w R w 5 e ub e a r s a n r/ r r ~s u a cil esc e e e s ei n ia w l s t w r a ml a n /lol g f o u e p z d a n A g mt n z e o s I /l S i n e e m wI ( s E F t i m e 1 i I r ri 7 r I oi p o s N n ot r t 3 o e e 2 o 1 a 1 o p c 1 o L t o n e r c l U M F l r lg l t p E P e d ie t F l D = u t o , i L O O e e O O u f v nA c r R R G eii/ t F n u R f S N e b. cd eI u3 u* i

~ u s x r N a E C u* e M ) e ~ N g m O n c I R 0 8 6 a T A 0 6 6 6 6 NI t / ( a 1 6 6 M e e r. A B y T . b ?=+ N OC eb E g a L n c B a .L A R O V O 3 3 3 3 3 3 O a l M h / 4 R lp e E p A d ( N I S T b N F E 0 m M o P E N ~ R 0 U F 0 S O 1 s A A / t KA S L I e f n 0 0 0 40 A N p o e 0 0 9 E N R d m 4 1 9 0 0 7 N R O O ( e e O A I F g r 4 4 1 1 2 2 I T I a n u 0 0 0 0 T D A L a m a s 5 9 4 2 A E N A N m R a 5 9 6 4 2 N T R C I G M O e e S E E I O T T M L A P N B T I A A a N N t A N Y A I N e T O L L S M I C L L U A A E S T E C C I W N K A O A G C T C F O O N R L R A L U O S I S A ) T D O m F A O t T c s H 0 t Y P 0 f n =.-. R O 1 o e A N / m 7 7 5 8 5 c N m e e 2 6 6 8 5 6 P p g r 2 U d n u 2 0 7 1 0 S ( a s 2 4 6 3 4 R a a e ,4 h M p l A s t f n o em r e e r b u 2 2 2 2 2 2 m m s u s N e 6 t H i i I s s s l i l e a e w w w r / r/ r / e s e s e s e loig oiI s w l 's wI s v g e n e n lol g n / wi I wi / wie n / io s l s l s l 1 r ri 2 r rl 3 r rl t 0 o e e 0 o e o 0 o e o a 1 o p c 1 c p c 1 o p c c l p p l p o M F U I I U 4 L O G F. G F U O O O R R R ,t w* ,i

Il l 1 ~ v _-m z p ) ~ s. f t g o n n a e i i r ) d r e e e e T._ s b. t 0 0 'O e. ,0 0 m o I u s x eE W 7 H e M - sk A. N o e O n c m. I e 6 T R 0 7 1 A 0 6 _6 6 6 N a I 6 l t / l e s M B p g_. T d N ( O l, C ~ a e 1 Y ~~ E g e B a s L n e = y-A R 0 V 0 3 3 3 3-3 3 h ~. f O a 1 M h / a y. E p a R l p A d ( 'p m. N I S 7. T NF b E D M4 m R E R 0 U F 0 S O 1 s A A / t 0 i KA S L I e f n 0 0 0 A N p o e 4 0 0 0 5 2 ) E N R d e '1 5 5 5 7 9 d N R 0O ( e n 4 4 4 e O A F g r 0 0 1 u I T I a n u 5 n T D AL a a s 4 5 5 A E N A N m R a i 4 4 i t NT R C O n e Y n S E I O M C A P N A A e 2 l_ o IMOT, T - ( T N N t I NY A e 1 2 OL LS IM B C L LU A E A E S T L EC G N B C A O A AGI 0T C T F O 0 N R L R A L U 0 S l S A ) T D O m F A T c OR s O t Y N O f n ~ RO o e 4 0 9 9 5 0 7 l UN / m 8 4 4 4 7 4 y O n e e p p g r 2 2 2 ,3 2~ 2 + t d n u 2 2 2 3 . 2 2 S ( a s R a a e h M p fA e. __ ~. t. t f e o w r e r b u 3 2 . 3 2 7 5 m s u a N e p. M s s s i l i t l l s a -e w w w r/ r/ ,/ es es es wI s wl s 5 wE s oi g t e n lol g 1 ot g a n s I s l 3 ,/ 1 l s n m / wI / wi / u i s l I 0 r rI ? r rl 1 .iowl i t 1 oe e o eo 1 a o a 1 o p c 1 o p c c c l p l p S o M F U l 4._ F U M fU L O O O 6 O R R R ,r ,N ~~ f p ll ,l ~

m u c l ,4'. u s x r N a E O e ,*g M ' ~ h e N g o O n c g; I R 0 8 a T A . 0 6 6 6 6 6 N e 1 6 I t / M e e 4g A B p T J N ( 7* Q ) ) WQ R e E 0 m L n c B a A R 0 ~ V 0 3 3 3 3 3 3 O a 1 M h / E p ep l A d ( N 3 I S ~ T ) N D E m M M c E f 0 R 1 F 0 t S O. AI / t 1 s A ES L e f n A A N p o e ) E N R d m 90 d N R 1 F g r 0 0 0 0 4 0 _.l'_ 0 O ( e e e 0 n l A u T 7, i Y D A i e n u 2 2 2 2 2 L m a s 4 4 4 4 0 4 AE N A N m R a 2 t N T R C O e e 4 n S E I G M o I O T T M C A P I A A a N ( T N NI t N Y A e 2 O L LS M B C L 1U A E A t S T C EI N N t A O fA A G C' T C T F O O N R L R A L U 0 S A ) S T D O m I A T c O s t4 0 t Y N 0 f n %1 R O 1 o e 0 9 0 A N / m 0 9 0 f N p g r 1 4 7 2 M m e e 4 4 2 2 d n u 1 1 0 0 2 t S ( a s 3 3 9 4 R a s N t ip A c s t f n o em r e u e e r b u 2 2 2 2 3 2 m s N e M s s s l l l l l l a a a w w w. r/ r/ r/ e s e l s w l s s e s ~ wI s w n lo1 g o / wi lol g s / wI lol g e n a n a n / wI s 4 r rll 6 r rI 7 r rl s I s l a 1 o e o o e e o e e 1 1 L M l U M l U M F U - m c i o p c 1 o p c 1 o p c o p p l p F F O O O O O O R R R . + ~ d c L l r

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TABLE:3; I

PLUT0NIUM: CONCENTRATIONS IN PAINT' SAMPLES-FROM NMDF I ROCKWELL IRIERNATIONAL SANTA SifSANA,-CALIFORNIA-r., T. Location. RadionuclideConcentrations-(dpm/100'emb 77 . Room Numbera ' Surface Grid Pu-238 Pu-239/240 { ,4 3 i 1-119 ' West Wall b- <1 <1 2-126 West Wall

29N, OE

<1 <1 l-3-125 East Wall b <1 .<1 .4-126 West Wall 32.5N, OE~ <1 2 t 'lc - 4-5-123 W. est Wall' 32.5N,10E. <1 <l. [, 6-124 East Wall 30N, - 18.5E <1 .< 11 7-127 East Wall

20N, 18.5E

<1 <1 8-127 . East Wall-ON,.18.6E_ <1- <l' 9-127 ~ West Wall. 12L5N, OE < 1. <1 10-127 West Wall = 25.5N, OE .< l -

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q 11-130 South Wall 12.5S, 6.2E <1- <1 r 1 iI 12-130 South Wall -12.5S, 8E <1- <1 - ld 13-129 South Wall 12.5S,10E. <1' <1 14-129 South Wall 12.5S,13E <1 <l ) r,r 15-131 East Wall IN, OE <1 .<1 'I 16-131 West Wall 2.5N, 3W <1 <1 ~ 17-131 East Wall SN, .0E <1 <1 -~ aRefer to Figure 18. [~ bNo associated grid number. [, Uncertainty is 2a based only on. counting statistics. I J $.h 1 o.; \\ i c. 46 1 } - - U

AB p T d N ( OC ) e2 Egm L nc B a AR0 V 0 3 3 0 Oa1 2 Mh/ Epa Rl p Ad ( ) 2 m ' e NM P'5 5F 0 YD s EN / - t i - cf n fEF poe 0 MO d m 9 0 0 U ( ee 8 5 0 SS gr 4 0 AT anu 0 5 EN A mas 5 1 MELI N mR a 4 V. AN O a e H - NR I G. M GTOO T I SI F A a TUTI N t AAAL I e NHNA M B 7 I XRC A MEE T E A T N L TDNA O B NNI N C A OA A T C LS L SLU A ) ENES T 2 COW O m AI K A T c FTCT RAON 0 s UCRA 0 t SO S 1 f n L /oe 0 F a m 5 2 OF pee 7 1 0 O d gr 0 Y O ( n u 2 2 3 RR as 2 2 AMM aR a h e MO p M UR l SF A s t f n oe m re er b u 4 6 ms ua Ne M 02 S e E r N u I g a L i n S E F o F T D i O N I o t O E U t a R V G c r o e L fe R i a j [ ,I

~ ! {'. _ >4 ,,) ..l. i ..g;. s o t, j u-TABLE 8 i1

SUMMARY

OF EXPOSURE RATE MEASUREMENTS ~ j NMDF . c. ,ROCKWELL~ INTERNATIONAL .o l ! SANTA:SUSANA,' CALIFORNIA-i. 1 .i 7,, ; Gamma Exposure RatesL ~ at'l m above.the Surface-a Location - (pR/h)- -l

j; 12 2

13-l

j

3 14 l 4 12 i 5 12 1 6 ~12-3.- I 7 13 8 12-s !/ - li 1- .I. .\\ aRefer to Figure 21. 4 1 f I i f 1 1 J..' l I i ,4 I lc 4 .1 q 1 T 51 % 6 __._ a

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.,[ . TABLE'9' RADIONUCLIDES. CONCENTRATIONS IN SOIL SAMPLES FROM EXTERIOR TRENCH. 'NMDF ROCKWELL INTERNATIONAL SANTA SUSANA, CALIFORNIA. 7 Radionuclides: Concentrations (pCi/g) Locationa U-235 U-238 Am-241 Pu-238 Pu-239/240 c., y 1 <0.'3 3 '<0.95 j 2 <0,.30 3.42 1.32b-. - <0. '24 <o,09 3~ <0.32 <0.99 <0.26 4 <0.31 <0.60' =<0.10 5. <0.33 <0.94 <0.27' r E. 6 <0.27 <0. 57 - <0.09- ' 0.25 7 '0.31 '<0.94 . Compositec n/a 'n/a n/a- -i.01.1 0.02 E ' 0.04 i 0.03c aRefer to Figure 22 j '." h, Uncertainties are 20 based only on counting statistics. i CComposite of samples 1 - 7.

l n,

9 s m 4 F4 52 E. i

r-a ^) 'a k. A REFERENCES l i.: r i 1. " Final Radiation Survey of the NMDF" NIO4SRR990027, Rockwell International, December'1986. t b l f, ) s. 'S 4 4 l l 1 n 1 (' o f f 3 1 e ') i l 1 J l i l i i 53

g . g r -e a - l i 1 ? i APPENDIX A j i .i MAJOR SAMPLING AND ANALYTICAL EQUIPMENT 1 i l l 5 I l f i j e i e b m__ m __d

3 ) .s .. n - t .j ', ' APPENDIX A Major Sampling.and. Analytical' Equipment The display or description of:a specific product is not to be construed as an endorsement of that. product or its manufacturer by the authors ;or their employer. l A. Direct Radiation Measurements Eber11ne " RASCAL" Portable Ratemeter-Scaler j Model PRS-1 ) (Eber11ne, Santa Fe, NM) Eberline PRM-6 Portable Ratemeter (Eberline, Santa Fe, NM) Eberline Alpha Scintillation Detector Model AC-3-7 (Eberline, Santa Fe, NM) ,~ Eberline Beta-Gamna <" Pancake" Detector l Model RP-260 l (Eberline, Santa Fe, NM) Ludlum Alpha-Beta Floor Monitor Model 239-1 (Ludlum, Sweetwater, TX) 6 Ludlum Ratemeter-Scaler Model 2220 (Ludlum, Sweetwater, TX) Victoreen Beta-Gamma " Pancake" Detector o Model 489-110 (Victoreen, Cleveland, OH) Victoreen NaI Scintillation Detector Model 489-55 Lj (Victoreen, Cleveland, OH) ? i B. Laboratory Analyses Low Background Alpha-Beta Counter Model LB-5110 (Tennelec, Oak Ridge, TN) A-1 j,

j 't 1a l $6- ~ 'j i 'I( . ;f ' ' Ge(L1) Detector j Model LGCC2220SD, 23% 2fficiency ,j (Princeton' Gamma-Tech, Princeton,. NJ)

e.

used in ' conjunction withs. I Lead Shield Model SPG-16 i , ';I (Applied Physical Technology, Atlanta, GA) i> High Purity Germanium Detector I; Model GMX-23195-S, 23% Efficiency '[ .(EGG &G ORTEC, Oak Ridge, TN) used-in conjunction with: c Lead Shield Model G-16 i-(Gamma Products, Palos E111s, IL) i: High Purity. Germanium Coaxial Well Detector b. Model GWL-110210-PWS-S, 23% Efficiency. (EG6G ORTEC, Oak Ridge, TN) i used in conjuction with: Lead Shield Model'G-16 l (Applied Physical Technology, Atlanta, GA) High Purity Germanium Detector Model IGC25, 25% Efficiency T' (Princeton Gamma-Tech, Princeton, NJ) used in conjunction with: Lead Shield (Nuclear Data, Schaumburg, IL) Multichannel Analyzer '!2 ND66/680 System (Nuclear Data, Schaumburg, IL) Alpha Spectrometry System j k Tennelec Electronics (Tennelec, Oak Ridge, TN) -l 1 Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN) p Multichannel Analyzer 1 ,j. Model ND-66 (Nuclear Data, Schaumburg, IL) 1. .A-2

1 .I e 4 i ? 4 9 e m ? { APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES s l,r * \\ o , I ~_ I 1. 1 i I l l l l l v i I I' l

1 r. APPENDIX B Measurement and Analytical Procedures Surface Scans Surface scans were performed by passing the probes slowly over the surface. The distance between the probe and the surface was maintained at a minimum - r p nominally about 1 cm. Identification of elevated levels was based on increases in the audible signal from the recording or indicating instrument. Alpha and beta-gamma scans of large floor surface areas were performed using a gas 2 proportional ficor monitor, with a 600 cm sensitive area. The instrument is slowly moved in a systematic pattern to cover 100% of the accessible area. i Combinations of detectors and instruments for the scans were: 7 Beta-Ga ima - G-M probe with PRM-6 ratemeter. Beta-Gamma - G-M probe with " RASCAL" scaler /ratemeter. Gamma - NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 ratemeter. Alpha - ZnS probe with " RASCAL" scaler /ratemeter. Alpha / Beta - Gas proportional floor monitor with Ludlum Model 2220 scaler /ratemeter. Alpha and Beta-gamma Measurements I Measurements of total alpha radiation levels were performed using Eberline { Model PRS-1 portable scaler /ratemeters with Model AC-3-7 alpha scintillation f probes. Measurements of direct beta gamma radiation levels were performed using l l Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window j i " pancake" G-M probes. Count rates (cpm) were converted to disintegration rates ( 2 (dpm/100 cm ) by dividing the net rate by the 4x efficiency and correcting for ) i the active area of the detector. Although other f actors (i.e. backscatter) can i affect the calibration, they are considered insignificant for the measurements 2 2 performed. Ef fective window areas were 59 cm for the Zns detectors and 15 cm for the G-M detectors. Background count rates for ZnS alpha probes averaged j ) approximately 1 cpm; the average background count rate was approximately 44 cpm ) tor the G-M detectors. B-1 j l )

4 'I .r n s H . Exposure Rate Measurements g i a er. \\ Measurements of gamma exposure rates were performed; using an Eberline - FRM-6 ' .{ portable.ratemeter with a 'Victoreen.Model. 489-551 gamma scintillation probe 'E .containing a 3.2 ' cm x 3.8 ' em. NaI(T1) scintillation ; crystal.. Count rates a were converted to exposure rates ~( uR/h) by cross-calibrating 1 with 'a Reuter Stokes. +

g model RSS-111 pressurized ionization chamber.

] . [ fi.. -Removable Contamination Measurements r Smear measurements ~ were performed on numbered filter paper disks' 47 ~ mm _in - 1 y e i_ diameter. Smears was sealed in a labeled envelope with the -location l and other ' -t pertinent information - recorded. . A ZnS ' alpha scintillation ' counting ' system was : I used' to evaluate individual smears 'at the site; smears. were.then returned to Cald

(

Ridge and recounted using a low-background ' alpha-beta proportional. system. ' j p O Soil Sample Analysis I q T' Gamma Spectrometry J Soil - samples were dried,. mixed, and a. portion placed in 0.5 1 Marinelli beaker. The quantity placed in each beaker was chosen to reproduce the rf, calibrated counting geometry and ranged from 600 to 800 g of soil. Net soil r. weights were determined and the samples counted using intrinsic ' germanium and Ge(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer Background and Compton stripping. peak search, peak identification, and system. concentration calculations were. performed using the computer capabilities inherent in the analyzer system. Energy peaks used for. determination of n radionuclides of concern were: .o 7-U-235 - 0.144 MeV U-238 - 0.094 MeV from Th-234. ' Secular' equilibrium was assumed. Am-241 - 0.059 Mev I M ~ r ' B-2 er

v i h X; g av y- _ F' o .were ' also < reviewed L for the presence of other radionuclides ' related -to ' Spectra ' fuel, activation, or fission products. l Isotopic Plutonium .t . Aliquots of. soil were. acidified and evaporated. to dryness.. The J residues ] were. then ' dissolved - by pyrosulfite' ~ fusion and. precipitated.' b' barium sulfate. h y- .. barium ~ sulface' precipitate was redissolved and plutonium sepersted' by, .{ W ' Thel liquid-liquid extraction.: The : purified plutonium was then. precipitated with?a.. 1." 'f, cerium fluoride carrier and. counted using : surface barrier detectors - (ORTEC), y alpha spectrometers (Tennelec), and : an -- ND-66 Multichannel Analyzer ; (Nuclear ~' t :- Data). i Water Sample Analysis .l 0 ..j Grosu Alpha and Gross Beta' ( I 'l The water samples were rough-filtered through Whatman No. 2' filter ' paper. d r, Remaining suspended solids were removed ' by subsequent filtration through 0.45 ta membrane filters. The filtrate.was acidified by ~ addition of 10 ml of concentrated nitric acid. A known volume of eac' _ ple was evaporated to dryness and counted for gross alpha and gross beta using a Tennelec Model LB-5100 'I low-background proportional counter. paint Samples Analysis "'l 1 Samples were dissolved by pyrosulfite fusion -and precipitated 'with barium a 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 Multichannel Analyzer (Nuclear Data). 1 .1 b.-, S*

e i l Residues from Anchor Bolt Holes and Miscellaneous Locations Samples were analyzed for isotopic plutonium using the sample procedure as described above for paint samples. ] 1 ( Uncertainties and Detection Limits v. I The uncertainties. associated with the analytical data presented in the tables of this report, represent the 95% (2o) confidence levels for that data. These values were calculated, based on both the gross sample count levels and the associated background count levels. Because of variations in sample weight, l detector efficiency, and contributions from other radionuclides in the samples, the Minimum Detectable Activity / Minimum Detectable Concentration for specific radionuclides differ from sample to sample. Calibration and Quality Assurance Laboratory and field survey procedures are documented in manuale developed j ,j,. specifically for the Oak Ridge Associated Universities' Radiological Site a l Assessment Program. With the exception of the measurements conducted with portable gamma scintillation survey meters, all instruments are calibrated with NBS-traceable j-standards. The calibration procedures for the portable gamma instruments are l; performed by comparison with an NBS calibrated pressurized ionization chamber. Quality control procedures on all instruments included daily background and i check-source measurements to confirm equipment operation within acceptable I statistical fluctuations. The ORAU laboratory participates in the EPA and EML l. Quality Assurance Programs. l l l 5 B-4 4

. n

/. + + p o D* -r: [. e.s e, .J g.,1 APPENDIX C if h - %e i ( GUIDELINES FOR' DECONTAMINATION OF FACILITIES'AND EQUIPMENT PRIOR TO-RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE l OR-SPECIAL' NUCLEAR MATERIAL N l ls - ~ .? tI ' I j l l - i -1 Sd tw o .t 4 ';

b..

1 e i .l h, I-i l, t i .m._---_--

} y;,; +. "I m .g ,e '" f.) l .- l .] - c. a .a

CUIDELINES.FOR DECONTAMINATION'0F FACILITIES AND EQUIPMENT '

] PRIOR TO RELEASE FOR UNRESTRICTED.USE~ 1 OR. TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE; I .OR SPECIAL--NUCLEAR MATERIAL.. r 1 t ( l. l l s 1,.. U.S. ' Nuclear. Regulatory Commissions l.., Division of Fuel Cycle-& Material Safety Washington, D.C. 20555 h .) \\. 1 t a N .a 1 l July 1982 it .}, l 'j (-. l-i 1 ~, 1 l- .j .j l I' i aw l l_, -rt.-

.. + The instructions in this guide, 'in -conjunction with Table 1, specify the radionuclides and radiation exposure cate limits which should be used in decontamination and survey of surfaces 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. j The release of such facilities or items from regulatory control is considered 1 on case-by-case basis. i 1. The licensee shall make a reasonable effort to eliminate residual contamination. k 2. Radioactivity on equipment or surfaces shall.not be covered by paint, 1 plating, or other, covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in f 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 lins.s, or j ductwork shall be determined by making measurements at all traps, and 1 other appropriate access points, provided that contamination at these l locations is likely to be representative of contamination on the interior l of the pipes,. drain lines, or ductwork. Surfaces or premises, equipment, t or scrap which are likely to be contaminated but are of such size, ] construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits. 4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstat ees such as rezing of buildings, transfer of premises to another organization continuing work ~ with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests muut: j { a. Provide detailed, specific information describing the premises, j equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination. j b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or .) scrap, are unlikely to result in an unreasonable risk to the health j and safety of the public. 5. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of C-1

s j 7.. 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 y should be filed at least 30 days prior to the planned date.of I abandonment. They survey report shall: i I a. Identify the premises. ( 'i b. Show that reasonable effort has been made to eliminate residual j-contamination. Describe the scope of the survey and general procedures followed. j c. i d. State the findings of the survey in units specified in the i instruction. Following review of the report, the NRC will consider visiting the

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facilities.to confirm the survey. 1 I 1 1 1 id l l, 9 .i i t. e [. C-2 i l: i l

e s h t W e 2 2 c b m m e g f, c c r j n .d eo b i yl e, 0 2 0 vf o yscu 0 2 m 0 i b sno b 1 m c 1 o t r r eeh e / c / t co o d si s l c 0 y i at F es c b 0 0 9. m oc nais a m 0 1 i i e i fl v p 1 / m l d t mdf e o d / m p ae r rnev m m p d e rd e ea e e 0 p d h t t nl R 0 d 0 t ye e e,w 0, 0 0 0 0 0 ,.bt m d eot a r nn 1 2 2 1 syni. e euk e t l ornr b s n st i poa sf i i nsoiu d eot xesrt q l r r 2 edi pas upt e 2 m nmpt , o np m c seean1 2 h ee c ep e est me 0 d ef nmn. c auh S 0 2 0 id oauat arrt f, 0 2 m 1 l n rh c0 eet LE 1 m c / cieyt t e0 rd s, V d, / e y u t b s j1 aond E a 0 S nya neb mie L b 0 0 l rdi r one n m o 0 1 m gp e o acgei N u r 1 / p npevemhh ant m O m d / m d i ah rh ct f iat I i m p t t et ru ryi e T x 0 p d 0 td s es eul rt. aao A a 0 d 0 il sbh v rsppedf N M r 0, 0 0, munot oh o pod erhb I 0 0 eoa i cmf ar pu/ M 5 0 0 5 - h eewd a o psisd A 1 3 3 1 asmt eet ,pi w T m ud g g ra h I 3 N ms) nearnme aet m E O L C aeeit ro cpnebi gdt maeff aar B 2 2 - iu iv o0 p ad A E m m al nrcad 0 h ld1 T C c c t cieo ea1 t t eue A 2 eumpseve nicot d F 0 2 m 0 b n sbi rr ewah a nr R f, 0 m c 0 r sa raeb f si U 1 c 1 d get t e pr er S c, / 0 / nnpnsod n opueome a 0 0 y ai urn al siscs cm E b 0 1 B t soo e ab w as L e m 1 / - t nct db oia sf ai B g p / m m aio cl t r esr A a d m p p h mieaud eth eust e T r p d d pethf ol etf tl sl ac P e 0 d l - at h ucao E v 0 0 0 asr csoimsnf evh e C A 0, 0 0 0 mggi hl oore/r C 0 0 0 h menrt s per il A 5 1 1 5 t at i t n pvol st ognt ea eai at nnrq b i cmng t riceoms as eoial cere i yt i remreat ejet 2 s b ed rgaevcl t bh a b( o t veiiaoti 0 p 3 s s n cd nal df m d 8 2, e u od m no a nd ad 2 21 dno i npyacenryeenre m 2 - 3 i ae t adb h o r v 'n a s a1 lh nd a ,et i edi dt a R - ct an n - ,d vg ,tl t oyuxg nc R I u t a i aeees abh cil me1 au 1 nrn mhl nnranat at li ,. d ,3 0 ( eo0 apbi e eeivioaaxt1 o 629 96 h p9 t l amivr mowinna ot 8 r 2 - 2 - 2 st s -. nat r caaa m di omne 3 p 2 a1 r1 ro t e o ei t ea ami 2 - P - S - e rS v crst f f enr eratdd7 - y a ,1 1 t so o oief oco r t rnl a U a R t e t b efhd e acf af noa un s c 3, 2, id npa c t sf o oop e ,e ,25 32 mooe ad s ,t r m t coehh d 5d s22 23 emicd f enad n uut at - rgst i 3 c-1 - 2 sxe rhi n esmnh nepa l 2d ih - h - a yset us l um i ut ul c - e nT1 TU mai o sid aoesxo obd e r u Ut a mcm) n l eir r snmgmaev e o N a r,, aeen eb srguea anavcat m ,i u07 t4 gd os rauek sl i ou t c s32 a23 air et t ca eepemd eit ao n22 n23 ahh s e h ssa aefhhih eeh mo ns a-1 t t psh W eA mbM oTT wt rrT en - s rh c h a - eil it U a TTA TR1 B waf o E b C d

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