Text

Decontamination of `Hot Suite Area of Triga Fuel Fabrication Facility Located in Bldg 9 for Release to Unrestricted Use,Stage 1
	ML20248B811
Person / Time
Site:	07000734
Issue date:	01/27/1989
From:	; GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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ML20248B791	List: ML20248B785; ML20248B811;
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- c, 'i'ABLE & OCNIEN_TS L4 .Page I i LIST OF ATDCHMENTS....................................... i INIRODUCTI N............................................. 1 SI'IE NJ.CN.......................................... 3 i.) HIS'ItRICAL OVERVIEW OF PROCESSING ACTIVITIES.............. 5 - TARGET CRI'IERIA PIR RELEASE 'ID UNRES'IRICTED USE........... 6 - RADIATIN DETECTION EQUIPMENT............................. 6 INITIAL SURVET AND DECCNTAMINATICN ME'IBODS................ 8 I Tnitial Survey..................................... 8 Mn*="'i nation Methods............................ 9 Soil M1 4 ng..................................... 12 FINAL RADIATICN SURVEYS.................................. 13 - .2-FINAL CNTAMINATIN SURVEYS...... -........................ 14 CGGLIANCE WITH THE TARGET CRITERIA...................... 14 CCNCLUS ICN............................................... 15 REFERENCES.....'.......................................... 16 i i I

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i y y2 e-1 i g. LIST OF ATIA"fiMENTS AWA - - ' 1: Plan View of Site At*A'.. at 2:- First Floor TM=ntal Building sFcwing the Previous Location of the " Hot suite" area A*eh=nt 3: Current Status of Former " Hot Suite" Area At* eh=nt 4:. View Graph Showing the former " Hot Suite" Area (overlap with A& e h=nt 3)- A& eh= nt 5: Decontamination Stages for the " Hot Suite" area Atteh=nt 6A: Table I Guidelines for Release of Equignent and Feilities to Unrestricted Use (NRC) A& eh= nt 6B: Table I Giide14nes for Release of Equip:ent and Facilities to Unrestricted Use (State of FAlifornia) : Initial Survey of Rocros 39, 49A And 50 A&eh=nt 8: Final Survey of Roans 39, 49A And 50 Atte h=nt 8A: Initial and Final Surveys of the Walls of Rocan 49A (3 = pages) B: Final Surveys of the Walls _of Roam 48 A*eh=nt 8C: Final Surveys of the Walls of Roam 50 A*ehment 9: Initial Survey of Roam 48 0: Final Survey of Roan 48 Att eh=nt 11: Final Survey of Room 47A and Hallway 2: Initial and Final Survey of Roam 38 A& eh= nt 13: Soil Sample locations and Soil Surface Radiation levels 7tteh=nt 14A: Radiation Measurements (microR/hr) at 1 meter and the Surface At*A-hu--ni. 14B : Wipe Survey Incations Ahnt 15: Soil Sample Results Att e h = nt 16: Contamination Survey Results (3 pages) i a - A

?. s DERuuuunCN Until April 1975, 'IRIGA Fuel Fabrication activities licensed by the USNRC were emane ted in two locations in General Atamics' Experimental Building (Bnilding 9). One location was in the east side of the former " Pilot Plant" (high bay) area of the biilding and the other location was in the northwest corner of the building. This area in the northwest corner was then known as the " Hot Suite" area (See Attehmnt 2). TRIGA Fuel Fakieation activities were transferred in April 1975 to a new facility at GA (i.e. Building 22). Decontamination of the " Hot Suite" area began in April and continued until around July 1975. Tne area was decontaminated for nonradioactive use but was not "of#4eially" released by NRC to unrestricted use. Radioactive material was still being used in other areas of the building. General Atomics (G1) has no plans for conducting future activities involving the use of radioactive materials in the Experimental Building. 1ccordingly, over the last two years, GA has been involved in the process of decontaminating and ob* e g the release to unrestricted use of the Experimental Building (Bni1aing 9). Beginning in Octolxtr 1986, GA decontaminated the Experimental Building; except for the " Hot Suite" area. GA subnitted a report dated July 28, 1987 to the NRC and to the State of O lifornia (Reference 1) requesting the release of this building to unrestricted use. This report included the former " Pilot Plant" area where a portion of TRIGA Fuel Fabrication activities were conducted but did not include the " Hot Suite" area which was occupied by GA's l telecmuunication group at that time. After confirmatory surveys were completed and the building was found to meet the release criteria, the State of a lifornia released I the building to unrestricted use (Arsedrent #87 of GA's Radioactive l I l

1 1 e I y 1 i Materials ti m nae #0145-80, Reference 2). The NRC also released the i btilt'ing to unrestricted use on October 1,1988 (Reference 3) after i I completion of conf 4= tory surveys, with the exception of the small area where TRIGA Fuel Fabrication activities had been located herein ) called the " Hot Scite" area. Please note: not all portions of the area referred to here as the " Hot Suite" area involved the use of rMi-tive materials. As mentioned above, GA has no plans for conducting any future activities involving radioactive materials in the " Hot Suite" area of the Experi m ntal Building and would like to release the area to unrestricted use. However, since it was not feasible to move the telecommunications equipment and activities all at the same time, GA is curveying and pursuing the release of the " Hot Suite" area in three (3) stages. The total area of the " Hot Suite" area is conservatively estimated at 4036 ft. Stage 1 (2880 ft ) includes Roams 39, 48, 49A, 50, 47A, a hallway area east and south of roa:n 47A and the rooms which previously housed the forner " Clean Machine Shop" area (these are: "est of Rootn 38, a hallway area east of roa:n 38, and rooms 34 and 35). Stage 2 (587 ft ) includes roams 40, 41, 42, 43 and 47. Stage 3 is reatn 49 (569 ft ). In late 1988 and January 1989, GA surveyed and decontaminated Stage 1 (2880 ft ) of the " Hot Suite" area for release to unrestricted use. This report su:miarizes the surveys completed for Stage 1. All the equipment (primarily telecmmnications equipmnt) fra:n the Stage 1 area was transferred to a tmru.cu.y location. The carpet installed over the original concrete floor was renoved in nost areas and the concrete below it was surveyed for contamination. Sa:re areas of the concrete floor were found to be slightly contaminated and two floor drains were also found to have scme slight contamination. The only observed con nminant was uranium; U-235 enrichment varied fra:n e 2

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i g.L g i about three (3) percent to about ten (10) pet.ent. The cosci.e was 2 decontaminated by scraping / eahbling the surface. About 256 ft gg 2 the 2880 ft floor area required h ntamination; which represents about 9% of the Stage 1 area. Three leal 4 ad areas of the wall in rocan 49A (a total of about 5 ft ) were also decontantsated. In the process of removing the drain line, concrete was removed in localized areas to the point of exposing the nnchrlying soil. The results of the analyses of the soil samples collected in these areas t showed only natural background radionuclides concentrations. GA has decontaminated the Stage 1 areas consistent with the State of california's and U. S. Nuclear Regulatory Comission's gnidalines for Release of Feilities and Equipnent to Unrestricted Use. The results of the final radiation and contamination surveys as well as the soil sample results are included in this report to demonstrate crum14ance with the gnidalines. SITE DESCRIPTION The location of the Experimental Building (Enilding 9) with respect to other facilities on the GA Site is shown in At+ehmant 1. A layout of the Building showing the " Hot Suite" area is shown in Ate rhmant 2. The entire hnilaing, including seconc; floors and mezzanines is almost 59,648 2 ft. Of this area, the fornur " Hot Srite" occupies lets than 4036 ft, A++ehmant 3 shows the current status of the roczns which now occupy the former " Hot Suite" area. Attachment 4A shows the " Hot Suite" area as it existed when TRIGA Fuel Fabrication activities were conducted there. Att ehmant 4 is a view graph of this drawing widch can be overlaid on the drawing showing the current status (Att e hmant 3). A comparison of the two drawings reveals that same of the original walls of the " Hot Suite" arr were runoved during the reconstruction of the area and new walls were 2 installed. Because of these differences, the area (ft ) is conservatively estimated to ensure that all previous " Hot Suite" areas are included in the final release surveys. 3

g-n;- - p p 47 ;,. - t. o \\, The former " Hot Stite" area contained a " Hydride Roam" (currently Rooms 39 and 50), 'a " Hot Machim" shop (currently Rocas 49A, 49, 40, _47 and portions of'47A, 41, 42 and 43), a " Hot Furnace" or " Melt Roam" (currently Rocan 48), a " Change Roan" (currently a portion of rocan 47A and a portion of the hallway east and south of room 47A) and a " Clean Machine Shop" '(most of roan 38, a' portion of the hallway east of rocan 38, and rooms 34 and 35). .) 2 The total area of the " Hot Suite" (4036 ft ) is being released in three' stages. Atwh=nt 5 shows the various rooms involved in each of the three (3) decontamination stages. 2 Stage 1 (2800 ft ) includes Rocus 39, 48, 49A, 50, 47A, a hallway east and south of roan 47A, and the rooms which previously housed the " Clean Machine shop" (most of roan 38, the hallway east of room 38 and 2 rooms 34 and 35). Stage 2 (587 ft ) includes roams 40, 41,.42, 43 and 47. 2 Stage 3 is room 49 (569 ft ), 2 The q;p.wdmate area in ft for each room to be released to unrestricted use,is provided below as well as the stage it is in. Rocrn Imwdmate area (ft-) Staae 1 Roan 39 246 Roczn 48 528 Roan 49A 456 Roan 50 174 Room 47A 137 Hallway (east and south of room 47A) 330 Former " Clean Machine Shop" Area Roan 38 182 Roan 34 286 Roan 35 370 Hallway area east of room 38 171 Tbtal Stage 1 2880 4

v j. s Stage 2 Room 40 106 Room 41 81 Roam 42 94 Room 43 94 Room 47 212 Total Stage 2 587 Stace 3 Rocan 49 569 Total Stage 3 569 'IUIAL (All Stages) 4036 The surveys in this report are limited to the rooms identified as Stage 1. HIS'IORICAL OVERVIEW OF PROCESSDG ACTIVITIES The Hot Suite's existence began in 1958 primarily for the research, develognent, and manufacturing of TRIGA fuel elements in accordance with NRC (previously AEC) licenses SNM-69 and SIM-696. This work involved primarily the use of 20% anrit-hed uranium (U-235). A review of past Wark Authorizations revealed that it was also used for stall test runs of prototype and non-TRIGA reactor fuel using mostly depleted uranium. In addition, a large batch of fuel was fabricated for the Massachusetts Institute of Technology using " normal" uranium. A new TRIGA Miel Fabrication Facility was constructed at General Atomics, and in April 1975, transfer of usable equignent from the " Hot Suite" to the new building began. In May 1975, contaminated ccruponents were removed from the Hot Suite and disposed of as contaminated waste and facility decontamination efforts began. The building was decontaminated to very low levels; less than 500 counts per minute alpha fixed conenmination (measurements were made on a grid with a portable alpha 2 counter) and less than 20 dpn/100 cm removable contamination (Reference 5). 5

La .y* 9; TARGET CRITERIA FOR UNRESTRICTED RELEASE The following wvvui target criteria have been taken fran Reference 4. Table 1 (At+ehnts 6A and 6B) is taken fran USNRC's and State of California's (respectively) criteria for releasing f eilities and equipnent to unrestricted use. It has been incorporated into our SNM-696. and State of California licenses. The limits in this table were used for releasing concrete and other surfaces at the facility to unrestricted use. RADIATION DETECTICN EQUIPMENI' The following radiation detection equipent was used for the various surveys and analysis of soil samples. 1. Beta /ganma counters

a. Model TBM 28 geiger counters manufact;.m.cd by Tehn%1 Associates were used to survey surfaces for beta /ganma contananation. The instruments contain a mnmke geiger mueller (G4) detector which 2

has a window thickness of less than 7 mg/cm. The instrument has three ranges covering fran 0-50,000 counts per minute (cpn).

b. Model 3 ratemeter with a model ifP-210 tungsten shielded pancake G4 detector manufactured by Ludlum Measurements, Inc. The instrument has three scales covering fran 0-400,000 cpn.

2. Alpha counters

a. Model 12 rate meters with Model 43-44 air proportional alpha probes manufactured by Ludlum Measurements Inc. were used to survey equipnent and surfacea for alpha contamination. The instrument has four ranges covering fran 0-500,000 counts per minute.

.b. Model 12 rate meters with Model 43-1 scintillation alpha probes manufactured by Ludlum Measurements Inc. were used to survey l equignent and surfaces for alpha contamination. The instrument has four ranges covering fran 0-500,000 counts per minute. 6

b t 3. Gama Detectors

a. Model 19 microR meters (containing a NaI scintillation detector) manufzuudi Ludlum Measurements Inc. were used to survey the localized areas wher" All was raachad after the removal of the drain line and for.posure rate measurements on the surface of the concrete and at one meter above the surface.

b. Gama Eghal analysis on selected samples of concrete and soil sanples were done using a high purity germanium detector manufactured by canberra Industries, Inc.

4. Wipe Analysis Wipe saples collected throughout the facility after clean up operations were counted using two (2) ledel 2404 low-level alpha beta gama counting systems manufactured by canberra Industries, Inc. All portable instruments are calihrated semiannually using a nominal'30 curie Cs-137 sourre except the Ludlum Podel 19 which is. calihrated by the manufacturer. We alpha / beta systems and the ga-nium detector systems have been calibrated for the various types of samples. This calibration is checked on a daily or weekly basis depending on usage. The final survey results have been converted from cpn (counts per 2 minute) for a particular detector to dpm/100cm by correcting the counts per minute observed by ayyiveuiate detector raariings for bac. lug.vund, detector efficiency and gecircQ;ic factors associated with the instrumentation.

===1. Background=== A "stanciani" natural background was determined for each type of detector and subtrac?M from the survey readings.

2. Efficia 7 Porttle beta /gama (G4) and alpha counters were calibrated to deterrine their efficiencies for uranium after analyses of samples 7

.m. l ? of contaminated concrete from various parts of the building showed uranium contamination (the U-235 enrichmnt varied from 3-10%). t, In order to sinulate the conditions on the concrete surfaces, i concrete blocks having an area of cmwdmately 25 cm x 25 cm previously spiked with NBS traceable standard liquid solutions of depleted uranium, 20 percent and 93 percent enriched uranium to g the average allowable release levels listed in Table 1. The average allowable level for an area one meter by one meter or less is 5000 dpm/100 cm and the maximum allowable level is 15,000 dpn for an area less than 100 cm2 (Att h nts 6A and 6B). Surface measurements of the blocks were obtained with the instruments and percent efficiencies were obtained. Since the blocks were for depleted uranium, 20% and 93% enrichments, an activity correlation was used to estimate the limits for enrichments 3-10%. The readings were corrected for efficiency by multiplying by the appropriate correction fac~or. 3. Geometry Correction The values listed in Table 1 (Attac. hts 6A and 6B) are in dpn/100 2 cm, therefore, a correction factor was applied to the values to correct for the smaller area of the detector. The TBM-28 hat -5 cm clameter detector which neasures a 19.6 cm area. The reading is corrected by multiplying by 5.1. The alpha detec~ ors used for 2 the surveys "see", at any given time, an area of about 78.7 cm, which then requires a correction factor of 1.27. INITIAL SURVET AND DECONTIMINATICN EFFORTS INITIAL SURVEY An initial survey was conducted in the area to determine if there was any remaining contamination. Radiation measurements using a microR reter showed only natural background levels. A beta / gamma contamination survey on the surface of the carpeted floors and 8

? exposed concrete areas was conducted (measurements were made with Model TBM-28 geiger counters). Low (beta /gamra) levels were detected (~350 counts per minute (cpm) on same portions of the floor in roatn 49A. Portions of the the roll-up door (in room 48) had the highest level of contamination detected (up to 10,000 cpm beta-gamra). DECONTAMINATION m e ds All the equipnent (primarily telmmications equiprent) from the Stage 1 area was transferred to a temporarj location. The carpet installed over the original concrete floor was removed in nest of the rooms (i.e. those rooms where there had been potential for contannnation) and the concrete below it was surveyed for contamination. Same areas of the concrete floor were found to be slightly contaminated and two floor drains in roams 49A and 50 were also found to have same contamination. Samples of contaminated concrete frcm the floor areas were collected and gamma scanned. The only observed conomimmt was uranium (with U-235 enrichment varying fram about 3-10 percent). The concrete was decontaminated by scraping /scabbling the surface and the floor drains and underground piping from the floor drains were removed frun roams 49A and 50. The Stage 1 " Hot Suite" area has been conservatively estimated to be about 2880 ft. About 256 ft of the 2880 ft required decon* & tion; which represents about 9% of the Stage 1 area. The floor area decontaminated in each roam is provided in the table below: Approximate Approximate Total Area Room Area (ft-) {ft-) Decontaminated Staoe 1 l l Roam 39 246 1 I i Roam 48 528 50 i Room 49A 456 200 i 9

j c [ i p i Room 50 174 4 Room 47A 137 1 Hallways (east and south of roam 47A) 330 0 Former " Clean Machine Shop" Area Roam 38 182 2 Room 34 286 0 Room 35 370 0 Hallway area east of room 38 171 O_ 'Ibtal Stage 1 2880 256 ROOMS 49A, 50 and 39 The initial survey of roams 39, 49A and 50 was conducted after the removal of equipuent, carpet and carpet glue. The survey is provided in ) Attachnent 7 and a description of cleanup activities is provided below. j ROOM '49A About 50% of the concrete floor was scabbled after beta / gamma levels showed levels ranging from 200 to 2000 cpm. The floor drain and dra.ul pipe were renoved after levels showed about 300 cpm on the surface of the drain. About 2000 cpm were detected in the drain pipe. Soil samples were also collected in the exposed soil locations. i All of the original three walls of roam 49A (up to two meters) were surveyed after the removal of drywall panels which had been installed over the walls during refurbishment in 1975. The initial and final surveys of the three walls are provided in Attachment BA (3 pages). The south wall did not exist during " Hot Suite" operations. There were three small locations of contamination measuring about 300, 400 and 500 counts per minute (cpn) beta /ganna and located along the bottam two feet of the wall. These three small spots totaled an area of about 5 ft and were decontaminated to natural background levels. No other locations on the walls were found to te contaminated. ROml 50 Two small spots on the floor were scabbled when levels showed about 10 _a

+ 7 ? 2 2500 cpn beta /genma levels and about four (4) ft of the concrete area in the south eaa of the rocxn were scabbled when levels of about 500 cpn were detected. The floor drain and the drain pipe were also renoved (the drain was reading about 500 cyn). Soil samples were collected in the exposed areas. 'Iwo out of three (~66%) of the original walls were surveyed. The north wall was not in existence curing " Hot Suite" operations. No contamination was detected on any of the walls. These surveys are provided in Attehwmt 8C. Roam 39 2 About a 1 ft area of the concrete surface was scabbled when beta / gamma levels showed about 400 cpn in same isolated spots along the concrete floor. No other contamination was detected. A detailed survey of the walls in this room were not completed since surveys of the walls of roczn 50 did not reveal any contamination. Both room 39 and roam 50 had formerly.been the " hydride roam". ROCM 47A and Hallway area east and south of room 47A The north part of rocm 47A had been part of the " Hot Machine Shop" during " Hot Suite" operations. This roam and the hallway east and south of the room were formerly the " Change Roam" and had no record of contamination. The initial (and final) surveys were completed on the concrete surface in roczn 47A and on the carpeted hallway areas east and south of the roczn. The only contamination detected in this roam were two small localized areas in the north part of roam 47A which measured about 300 cpn 2 (beta / gamna) and represented less than a 1 ft area. The concrete in these two spots was scabbled until levels were at nonnal background levels. It appears that the spots were directly u.h eath the previous " Hot Machine Shop" wall. No other locations in room 47A were found to be contaminated. The hallway east and south of rocen 47A was surveyed with the carpeting in place since it was outside the previous " contamination control" boundary (former " Change Room" area) and the portion of room 47A (concrete floor) which was also part of the " Change Roam" was surveyed and no-CoM mi M tion Was detected. 11

i + ROCH 48 The initial floor survey of the flocrs in room 48 is provided in l Att e h nt 9. Contamination was detected in the cracks along the concrete floor and in three other spots; measurements ranged from about 250 to 2000 1; cpu (beta /gama). All of these locations were scabbled. The roll-up door to roam 48 (which was located on the south side of the roam) measured up h to 8000 cpn (beta /gama). The roll-up door was removed on 8/10/88 and disposed of as radioactive waste. Most of the original walls (up to 2 meters) were also surveyed. These surveys are provided in Att e b nt 8B. There was no cont aination detected on any of the walls. "Old Machine Shoo" Area This area is now most of roczn 38, the hallway area east of roczn 38, and portions of rooms 34 and 35. (See Att e h nts 3, 4, and 5). The " Clean ' Machine Shop" area had no record of con *=ination. A portion of the area 2 (Roam 38 containing'~182 ft ) was selected for a detailed survey. This survey involved removing the equipoent and supplies, removing the carpet fram the concrete floor and surveying the concrete surface for alpha and beta /gan1ma contamination. Two small spots of con +mation were detected (See Art e b nt 12). One spot (about 1 ft ) was located in the southwest corner of the roam (on the other side of room 49A) and measured about 2 10,000 cpn beta /gama. The other spot (also about 1 ft ) was located in the west corner of the roczn (on the other side of room 40) and measured about 6,000 cpn beta /gama. Both spots appear to be the result of a spill (s)inroams49Aand/or40whichhousedthe"1[otMachineShop"and not as a result of contamination of the " Clean Machine Shop". This portion of room 38 was not part of the "Old Machine Shop" during operations (see Att e

nts 3 and 4). No other contamination was detected.

A cursory rurvey of the carpeted floor areas which previously housed the " Clean Machine Shop" was also completed. This included the , hallway area emot of rocra 38, and roczns 34 and 35. No contamination was detected. SOIL SAMPLING In the process of removing the two floor drains and drain pipes fram 12

i [1 rooms 49A and 50, concrete was removed in localized areas to the point of exposing the underlying soil. Three soil sanples were collected, including a "camposite" soil sample. The locations of these soil samples are shown in Attachment 13. The soil samples were analyzed by ganma ray s p uscopy using a high purity germanium detector system in accordance 'with written procedures. All gamma emitting radionuclides were identified and their concentrations were determined. The results of the analyses of the soil samples collected in these areas (Attachment 15) showed only natural background radionuclides concentrations. Radiation measurements on the surface of the soil were obtained using a microR meter. The readings were at normal background levels (Attachment 13). FINAL RADIATION SURVEYS Table 1 (Attachments 6A and 63) provida acceptable (approved) limits for fixed contamination levels. Final radiation surveys of the areas which were cleaned and/or scaboled were conducted. The measurements of 2 average contamination (in dgn/100 cm ) were averaged over 1 M area or 2 less. The mwimn contamination level (also in dyn/100 cm ) applies to an 2 area of not more than 100 cm. The final surveys for Stage 1 are provided in this report as follows: At'Ac h nt 8: Final Survey of Roams 39, 49A AND 50 Attar b ut 8A: Initial and Final Surveys of roam 49A walls Attc'chment 8B: Final Survey of room 48 walls Attachrent 8C: Final Survey of roam 50 walls Atenc b ut 10: Final Survey of Room 48 Athc h nt 11: Final Survey of Room 47A and Hallway 2: Initial and Final Survey of Roc'n 38 A microR meter was also used to survey the rorras and to measure radintion levels. The final surveys show the measurements obtained on the surface and at one meter above the surface. These levels were all within 13 i l

L ',s* nornal background levels. The results of this survey are provided in Attachtent 14A. Alpha counters were also used to carvey the rooms. Very low (if any) levels of alpha contamination were detected. The beta / gamma levels were used to determine allowable release levels for the uranium contaminated areas. FINAL CONT 1HINATION SURVEYS Table 1 (Attac. Lend.s 6A and 6B) provides limits for acceptable renovable surface contamination levels. Wipes were collected on the floors and the walls of the rooms. The wipe sample locations are shown in Attachments 14B for the floor locations and At w % nts 8A, 8B, and 8C for the wall locations. The results are provided in Attac. tent 16 (3 pages). The contamination levels in every location were ( 20 @ l00 cm area, and well below the Table 1 limits (Attach ent 6A and 6B) for removable contamination. COMPLIANCE WITH THE TARGET CRITERIA Fac4ities and Ecaipment Concrete and other surfaces of the bnilding were cleaned to levels below the limits in Table 1. The final surveye provided in this report demonstrate cmnlinnce. Direct Radiation The di:..ect radiation levels ir all areas of the Stage 1 areas are at or below nomal background levels. 14 ._ -_ __-_ _ ____--_ _ a

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't' j!' CCHCIUSICN-1 Stage 1 roams of the fonner TRIGA Fuel Fabricat: ion'" Hot Su3te" fonnerly located in the northwest corner of'the Experimental i . Bn41d45 (9141 dig 9) have been h eJ=m4n*M to levels:belcw the ' specified limits. and ther.efore meet the criteria for release to unrestricted use. k 1 4 h s 0 1 t l y 15

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L y. ,c ^ xt.rt.nt.NCES 1. As:tussen, Keith E., letter # CAL-1095 to Mr. Ben Kapel, "Fjaal Survey Report on the Decontamination of GA Technologies' Experimental Building", dated July 28, 1987. 2. Kapel, Ben R., letter to Keith E. Asmussen dated May 14, 1987. Docket #033087-0145, containing A *>* -nt #86 to GA's radioactive naterial license ntmber 0145-80. 3. Montgomery, James L., letter dated Oc*h 1,1987 to R. N. PM-her, " Inspection at GA Technologies, Inc. (confirmatory Survey), with Report No. 70-734/87-11, 4. Asmussen, Keith E., letter # CAL-1049 to Mr. Ben Kapel, " Decontamination of GA Technologies' Experimental Building," dated March 27, 1987. 5. Iatter dated 8/5/75, J. M. Keith to F. O. Bold. 1 16

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.,;-.) r L -5 ~ -( pt % y? ATTACHMENT 6B7 o 3pgg gq ACEPTABE SURFAE CONTAMINATION L&ELS1/2/ ~, t 3

1:

llJE.IE" ^ .A M E "' WIWW d mmb ~* [ b (dpm/100 c:s ) (dgm/100 cmk (dpm/100 c=2). M5 U-n c,c0-235, 0-238,fand; 5,000-15,000 1,000 0 icsacciated' decay products ~ .a m.. h b)$Trinsuranics, Ra-226, Ra-228, 100 300 20 iTh-230,1Tn-228,:Pa-231-Ac-227)'f-In '.I-170= "c)l Th-nat, Th-232, Sr-90 ' 1,000 J 3,000 200-

Ra-223, Ra-22 4,-.

U-23 2,- I-126, I-131,.I-133-Id)(Bats-gamma emitters - (nuclides .5,000 15,000-1,000-with decay modes other than 4 halpha. emission;or-spontaneous

fission).except Sr-90 and

.oth3rs noted above. I ks)'H-3,?C-14exceptaJ CNA .20,000 60,000 4,000 racursors '.f/ o 9 p 1Whe:s subface concaminacion by boch : alpha-and beca-ga:::ca-emit:ing nuclides exis:s, che ll=i:s as:ablished !ct alpha-and beta-gam.a-emit:ing nuclides 'should apply independen:1y. [3&Asluszd'in this cable, dpm (disintegrations per minu:e) means the : ace,o! emission by radioac:in ?m:erial-'as ^ de:e: mined by cc::ecting the coun:s per minu:e observed by an appropriate detec:o: !.:r background, e!!!ciency, and geomec:ic fac: cts asscciated wi:h the instrumencacion. TM2asurecents cf average concaminanc should noc be are:rged over mo:e chan 1 square mecer. Tc: [objec;s of less surface area,; the averasa should be derived !c: each such objec:. lThe{ maximum concaminacion level applies cc an area cf no: =cre chan 100 cm'. .,The amoun:: c! removable radioac:ive ma:erial pe: 100 c=' c! su:! ace area should be determined L [cy wiping ' chac f area with dry !! iter; or sof: absorben: paper, applying moderate pressure, and [assassirig,the ancunt of radioactive =aterial cn :he wipe with an appropriate inscrument ci known 1

e!!iciency.

When recavable cor.:aminacion on cbjec:s cf less' surface area is decermined, the .!per:inent levels should ; be : educed proportionally and :he enci:e su:! ace should be wiped. .s i !:0::A precursors mean nolecules. or compounds that ce direc:1y incorporated into the DNA colecule i < ?du:ing 'DNA _ biosynthesis, e.g. purine and pyrimidine bases and their analogs, nucleotides und j nucicosides. : The acceptable surface contamination levels for H-3 and C-14 in DNA precursors f a:a:as tabulaced in paragraph (d) for beta-gamma-emitters. ( 1 s_. j.D USNRC Regulacory Guide 1.86 Terndnation of Operacanc Licensas !ct Nuclear Reactors, Washing:on " D.C. - (June 1974) i l/ AliSI, Control 'of Radioac::ve Surface Concaminacicn on Materials. Ecuitmenc and racilicies_ ~ ~o IBe Released for Unconcr:11ed Use. final d:st. crcycsed imerican Na cional Standard N-328. I lAcomic Indust:ial Forum, :nc., NJ. (June 1974) p L--

_----------.-----------------------------------------------A

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g y 0 4 0 60 0 2 0) 89 0 9 79 89 3 9 31 1 1 21 31 9 1 63 05 03 13 63 08 03 L = 6 6 8 6 x 2 7 6 2 7 4 2 4 8 2~ 7 O1 04 O3 1 05 00 00 N6 AE R - 8 A 30 0 2 3 C 1 81 0 7 8 E 0O 00 67 02 T1 00 06 A A E F E 7 R R 1 U A U 2 8 8 0 S 85 2 8 1 8 N S 35 8 3 0 3 F F A' 00 00 62 03 06 07 06 8 O A 0 9 l 4 8 M R I / G C O 1 N F H 6 6 0 6 8 / I 0 JP C 87 6 9 7 0 81 1 LS0 H O O 32 4 1 2 4 30T 1 BS1 P R 61 00 04 03 01 02 67E BE/ D 0 - E AI H 5 ~ F D C I N E SRD I D 4 6 2 4, 85 I /O 81 87 85 81 8 0 81 R C.N O I M 39 32 35 39 3 4 301 I t 1I 61 61 62 61 06 02 672 P I F l I A 4 NRU D 9 Q AA1 A 4 O E 1 E 2 6 6 6 0 0 68 TD R I 85 87 87 86 9 8 71 C0A 9 35 32 32 34 1 3 20 A 0E T 3 62 61 61 64 03 06 17' E RER C R E E i 4 i A I EPSRMD /f'f Q 00 4 FEU'D SI O 77 81 .A[RE R / / RU 11 30 E8 1 33 61 00 T8R1I Y }! 0 Q O0 I/O DR R 0 S2I B% N E 00 O0 U6DY O f V 4 6 2 / F AG U 5 3 1 3 2 5 3I K E X ARA 8 0 8 7 5 8P f8 P f E/F ? 7 7 l S 4 00 06 05 06 01 02 06E DI GArUI L O I ?I f F " EiF/ A O i R ATB I N R 5 FNCErO f I 6 0 6 EiOMG ort 7 8 7 87 B0RBFU F 2 3 2 3 0I 0i M l 00 01 06 00 00 01 06 5L TEEI EF Ai GEXR 8 C DCGAARAU N RI I 1 E 1 P 0 4 4 A)EPVDSET T 9 1 1 8 8 8 2 T 1 9 9 3 3 A3RT AYl E IM 00 00 03 01 01 06 06 92UE B7 l 42SSE I C 9AEl fS l r A ,17R' I C I I 4 6 6 8 9 P O 1 T 1 7 8 7 2 38 ESFEE A 9 2 3 2 8 2ERI J 00 00 01 01 06 01 03 S - R EU T OBWIDRVQlMME EE OT NI H 9 2 6 0 F R(SUATMTXE 3 8 8 85 8 7 67 8 L V O 3 3 35 3 2 35 32 FREI ASI M 06 06 62 06 01 69 061 OEVDP I O EAONOAP I O SNLESIBRAE R Y0 4 E0 8 8 0 8 V0 3 3 1 3 R 123 4 00 00 OO 06 06 05 06 - U4 SG -4 LOS Al E NI I I S 7 g K FUI 7

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TC D E i ~ E E R 00 ST E I AA R D N NR H O a. B TT A I AI C 4 T 9L EY M A 00 0 4A RB A C C I G O M DR / I S O8 E A* O3 AT T2E R2 NE E I T 2 M BmP E F9 M M E O - GE N0A) F M /N h LB AO i 0SS 1 T } 5 LT T I (EL 00 0 A EA X PU 1 W0 B AAIS S 2 N MEWE L l TI EI R R /O T R SS G EAE M EU R R i TN1 D ) W J I 1 O W D L 9 EO A E A 9 I E8 V S S A / A0 IRI 6 4 M 13 0S D 1 1 2 E1S EEE H 00 0 T F/ 1 /E U T I C S O1 7MI LMC N O E P APR E R h Yi SDR VDI N EQ I O C F S I V N N C 1 O 00 0 RD EIA0I NA OE U E4 I T Y SI 8LGRI G T Y ( E E8ANAONRA E V LI/VI BIE V R AP6 Df DBE R UA N1 2PA0EAME f U S9 I0/DE01 EUS S 4 SF08' RE7RN( I L E L AN f l A N X 0 N S I N1 2 3 4 W I R FI F ^2E v T D E N M A 4 L D N E T A T W E I L E T 7 I C R I P 1 N 0 0 4 S 1 1 I 6 6 Q A CD W A E ST L N A AA L .I B 0 0 WR AD 6 6 B NE0 T J LI Nl N LL FAI S M N E AA OED L/ S N WC LA A ACE IC T T8 E R A G S S3 RD I E E2 ANTE T T W2 AS I A E 9 D EI 0 0 E E E-E) A 6 0 F M RSGV 1 I 3 1 TB ANI 5 T UOHT F QI O 1 OO STEO 2 A 1 F l Y YI TC7 E ES EO E V VU EI SE RA R F IR U9 U9 2 l 0 S4 S8 i

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[D R S O E O O T o2i N1 2 345 6 T l l

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[E'. J t er \\,-. i ATTACBMENT 9: INITIAL SDRVEY OFiROOM 48 3 20 FEET ? ^ i j. 3C 0 1 30 N d' 50 40 i 50 300 50 a $1 -_ t' n 'b -k_ 300 300 y 3_ e 40 m N 550-h 1000 60h e 0 00 R2000'750 y Roll-up door (100 - 14000 cpm; removed roll-up docr) NOTkS: 1. The initial survey was completed 5/24/88 using TBM-28 (#92238), calibrated 4/21/88. 2. Values are present in counts per minute (cpm); (beta / gamma activity) 3. Contamination was detected in cracks along the concrete floor. Values ranged from 250 to 1000 cpm except for the roll-up door which measured as high as 10,000 cpm. The roll-up door was removed andLdisposed of as " hot waste. 4. -Other areas on concrete floor read around 200 cpm.

- Unable to survey.(eluctrical equipment for computers)-- to be L,

done with Stage 3. =___:___-__-____ _ - - _ _ _ _ _ _ _ - - _ _.

j. Q:[. '

+ $/ LATTACHMENTE10: FINAL 1 SURVEY OF ROOM 48 i J-----.f------------20 FEET----------------------------1 <1250 1250 1500 1250: 1250 1250 1250 Small area along 1250 '1250 2500-2500 5000 1250 1250 the north wall to be done with-Stage 3 - 2 6. -1250 1250' 1250-1250 1250 1250 1250 1250 .1250 1250

1250 1250 1250.

1250 'FT' 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250-1250 N A v. 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1250 1875 n 1250 1250 1250 1250. 1250 1250 1625 1250 1250 1250 1250 1250 1250 1625 L1250 1250 1250. 1250 1250 1250 1625 1250 1250 1250 1500 1250 1250 1625 1250 1250-1250 1250 1875 1250 1250 1250 1250 1250 1250 '1875 5000 1250 1875 1250 1250 1250 1250 1250 1250 3750 1250 1250 1250 1250 5500 1250 1500 1500. 1500 1500 1500 1500 1250 1500 1500 3000 1500 1500 5000 1250' Concrete along the area where the roll-up door was located was scabbled as well as some areas outside. 1. FINAL SURVEY OF ROLL UP. DOOR AREA COMPLETED 8/18/88 USING TBM-28 (#2759) CALIBRATED 6/24/88. 2.~ FINAL SURVEY OF THE REST OF THE ROOM COMPLETED ON 1/9/89 AND 1/12/89 USING TBM-28 (#108113) CALIBRATE 1 10/31/88. 3.- LEVELS WERE MEASURED ON CONCRETL FLOOR AFTER SCABBLING (WHEN NECgSSARY). -4.; TOP VALUE IS THE AVERAGE BETA / GAMMA DIRECT READING IN DPM/100 CM IN A .THREE FOOT BY THREE FOOT AREA OR LESS. 5.. BOTTOM VALUE IS THE MAXIMUM BETA / GAMMA DIRECT READING IN DPM FOR AN 2 ' AREA (100 CM L, t6.'. THE CONCRETE ALONG THE CRACKS IN THE FLOOR WAS SCABBLED TO LEVELS BELOW THE TABLE 1 LIMITS. (

[Q;W ';y: [ ~' '-'T3 y, ,,s- .c q .*J 1-3 ATTACHMENT'll: FINAL SURVEY OF ROOM 47A AND HALWAY EAST AND SOUTH.OF ROOM 47A

--- - - - ---- - - - - -- RO OM - 0 7 A- - - - --

b .i. 0 0 0 0 0 0 0 0 ---> Z ^ 4 0; O O O ~0 0e0 0 +- FEET. 0 0 0 0' O O 'O O [ j 0 0 0 .0 0 0 0 0 16.5 ~ ^ FEET HALLWAY-O' O O O O O O .0 0-0 -0 0 12'5 O. 0 0 0 0- .0 FEET-0 0 0 .0 0 0 0 0 DN O O O O-0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 v v NOTES: . 1. - FINAL'. SURVEY OF ROOM 47A AND HALLWAY AREAS COMPLETED 1/13/89-USING TEM #108113, CALIBRATED.10/31/88.. 2. READINGS IN ROOM 47A WERE TAKEN ON' CONCRETE; READINGS IN HALLWAY WERE TAKEN ON CARPET.. THESE-AREAS WERE PREVIOUSLY THE " CHANGE ROOM" DURING " HOT SUITE" OPERATIONS. 3. INITIAL SURVEY SHOWED TWO SPOTS IN ROOM 47 (NOTED AS) m READINGS ABOUT 300 COUNTS PER MINUTE (CPM). THESE SPOTS WERE SCABBLED UNTIL' READINGS WERE AT BACKGROUND LEVELS. 4. tog VALUE IS THE AVERAGE BETA / GAMMA DIRECT READING IN DPM/100 CM-IN A THREE FOOT BY THREE FOOT AREA OR.LESS. 5. BOTTOM VALUE IS THE MAXIMUM BETA / GAMMA DIRECT READING IN DPM 2 FOR AN: AREA (100 CM ___.__m _ _.. _ _ _.. = _ _. _. _. _ _ _ _ _ _ _ _ _.. _. _

/anbb af 0goa m 1 acct me so ae 4 def o gr 9 etosf /h 8t e a at - 00 00 00 00 00 0O 0000 /arewe t 2rcr e ea 1bnal r b /i oulh n 00 1l cqat ei T 55 a sw g 8 E 22 dcf a g s 3 E00 00 00 00 00 0O 0011 e ott rm F t3 oss ecl M 8 e1 eoet v O 8 3 l1 rfwn.a0rh O 00 p8 a hes 0 R 55 M m0 u1tsse1 22 O o1 q ueeh/as F 00 00 0 0 00 00 0O 0011 O c# s d o rl t M ei O s-R nsp P y8 ta ersDaei Y F e2 o eroi E O v-olh n V rM flttaeioae R Y uB a ieu U E sT 1 wtnrl gf S V suaan R l gthn vie L U an utiht d A S ni ouacopart r N

is bogaooehoi I

L SFu AsaEfTrtBd F A E N T D I O N F N1 2 3 4 A L A .I r ) T a m I m p N 6 a c I g / 0 ad0 8 t e0d 2 8 et6 a 1 / ba~ e 1 ( n r T 3 id N emal / E 0dt ael M 1 eut ra l g 9 vnn w l C 8doiol A / emmcl t T - 0 0 0 0 0 0 0 0 2te as T - 0 0 0 0 0 0 0 0 1 arrewe A - 1 1 1 1 1 1 1 1 /r er w 1bepehh ir wtt dl es uu eawtsoo T0 0 0 0 0 0 0 0 tc nl ss E0 0 0 0 0 0 0 5' 8 e eul E1 1 1 1 1 1 1 1 ' 3 l3 uoaee F p1l cwhh M m1 g tt 8 ) O o8 nt

O c0distt

- 0 0 0 0 0 0 0 0' R 1 n nss - 0 0 0 0 0 0 0 5 y# a ei n n 1 1 1 1 1 1 1 1 F e raii O v8t agaa G 1 r2 e aggm Y u ps aap s E sMres c 3 T V Bauaaa ^ 2 F v mm R lTcl eee0 pp U a arrr0 cc S i grvaaa0 tne 00 L iitl oee0 00 A nsfl whh1 00 I SI uaATTt~ T E 06 I T 1 N O I N1 23

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j*j nq s

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ATTACHMENT.13:

SOIL SAMPLE LOCATIONS AND RADIAT' ION READINGS ON' SOIL _/N,._, g _.9 l.2., ass osr [ l e >4 og oc. /bl 1,og$ N 22* 20 25 5 g g\\ q 2 oso k ~~ e 20 g g -.- Y =' 16W

W A

YE to i J 1T l N 049A ',=, { 22 .g \\,,, ,7 \\,,,, ea, .d y ss a ere-l! c. -(,a.,^ c.:c s u -un g; '. N, ,.e (/'N. I -.. s.: / _.. < s _. _ J. 1 = g! = i.: il M,,I il il !.I ) A 4.a ~ u e. b l NNN Ex :csed Soil Locations f d 048 Soil Samples "A" and "B" collected at 1 l' these locations (See Attachment 14 for 3 results) i Composite Sample "C" collected at ' these locations (See Attachment 14 for results) i Values from 17-25 are surface radiation i levels in microR/ hour (on the surface of the exposed soil). All readings are at natural background soil levels.

~

e

. g. 4 .~ s ATTACHMENT'14A: RADIATION MEASUREMENTS AT 1 METER AND SURFACE

N 039 oss -

osr .2.2.i OO?A OCa l[ 1 1 l 12 12 1 1 14 /h 10 12 12 12 12 s. 12 12 -I 32 12 12 12 14 12 77-10 ' 12 12 12 12 \\, -l ( Ik 13 13 f g 10 12 'h lN \\/ ~) 03? t 24e \\/ 04r ces o r-1 3 i 12 ~ 12 12 ,53.3 12 14 .. N N o=o a:s ,e y o,c. 10 "#2 12 cm 12 12 14 Il' ~ =49 Ore-m 3 !i 'H s' 04c 'N, \\ a u-(c 10 10. q ce akl \\ n 10 \\/C\\' /.. o'4 (/ \\ ' %IV --. L/ n-e 10 - =- ~ 10 10 4 i 10 10 i i 3g to l We.i ) Jl l!. l !l il ~ lm; 8 10 12: 1 8 10 14 i ATTACHMENT 14A: RADIATION MEASUREMENTS 0 AT 1 METER AND SURFACE 4 5 048 1 15

Top measurement is microR/hr reading 3

at 1 meter. Bottom measurement is ~"\\ microR/hr reading at the surface. 10 10 11 j 12 12 14 All measurements were made with the Ludlum l model 19 microR meter (#33545, calibrated i on 2/11/881. 1 1 ( i

,.4.- ijg. o l )) c i L f-

ATTACHMENT;14B: . WIPE. SURVEY LOCATIONS

=m-r!

N 039_

ass psr es4 03 Oct. ' L A 4 3 l 5 2 /h_ J r e r . Ch ( [1% '( 7 g, 1 . ( / h 032 ar-7 '(/h 9-m \\/ c4a cv I f 11 12 ,g p _c h J 13 = h 14 ~~ ~~ ~ .u.s . = = = l! e r c-fl

.h Cec N

m.__ -/.ii i I O

=

\\. j s9s 15 c d.c i w \\/ ; \\. e- s'd (/--\\ f[I 16 f N. \\., i e ,k N h N k! i t l 17 ATTACHMENT 14B: WIPE SURVEY LOCATIONS i 't i 19 18 'lI 048

s

'l All wipes taken on floor locations. 21 20 ) See attachment 16 for results. N. See attachments 8A and 8B for wipe locations n the walls. Also includes 8C. 23 22 (

L 4 4 4 5 0 0 0 0 5 0 0 0 0 32 1 1 i 1 U-0 0 8 9 1 1 0 0 0 0 0 0 9 3 0 4, 1 0 8 1 0 2 3 D 2 1 1 N 1 U 3 7 0 )'q 2 6 0 / 2 1 2 i Cp ( 5 5 6 0 no 0 0 0 2 i 6 0 0 0 0 t 2 a 2 1 1 1 1 r t a 8 8 7 0 S n R 0 7 0 9 e I c 0 0 1 0 U n S o E C 5 R 6 1 7 2 e 1 E d 0 1 0 0 E i 8 0 0 0 0 N M l 2 c 2 + 1 u 1 1 E M B S n a 0 1 6 0 D o R 1 9 3 4 5 A E i 3 d 1 0 1 1 1 T M a I R R M 48 S 3 3 4 L 0 0 0 2 Q .s R I 8 0 0 0 0 n I O 2 o S 2 1 'i 1 1 i e t c .h 2 5 6 0 a n 0 3 4 c e 'l 1 o r 1 0 1 1 l e f e e l r 1 1 9 p 0 0 0 n e a e 7 0 0 0 s s 3 D 1 N 1 1 1 l i s 2 2 4 o s s C 0 0 1 s n m m m e a a a a l 0 0 O r e r r r p o m g g g n f / // a e i ii s 3 l C C C 1 b p p p l a i 0

t t 1

1 o 6 D D D 'D n c 0 0 0 S N N N N e e o m t 0 0 3 d C h e ( ( ( n c D u a = = = o d t t r n t o 7 g u

A N 3 0 8 k o
1 6 3 c

e r

e =

2 a l#

g e D s o

- B p A B C k l S N C C U. nD c i aI a o S B S

P~.97 1 OF 3 / ATTACHMENT 16: GROSS ALPHA / BETA COUNTING RESOLTS.FOR WIPE SAMPLES SAMPLE COUNT ALPHA % ERROR BETA % ERROR I.D. LENGTH DFM/100 95% CL DPM/100 95% CL MIN SQ. CM. SQ. CM. 1 RM 38 FLOOR 1 <9.386e-03 95.00 <4.054e-01 95.00 2 RM 38 FLOOR 1 <9.386e-03 95.00 <1.447e-00 95.00 3 RM 39 FLOOR 1 <9.386e-03 95.00 <l.447e-00 95.00 4 RM 39 FLOOR 1 <9.386e-03 95.00 <9.520e-01 95.00 5 RM 39 FLOOR 1 2.897e-01 222.75 <3.167e-02 95.00 6 RM 39 FLOOR 1 <9.386e-03 95.00 '9.520e-01 95.00 7 RM 50 FLOOR 1 2.897e-01 222.75 <l.447e-00 95.00 8 RM 50 FLOOR 1 6.189e-01 147.45 1.435e+00 108.95 9 RM 49 A FLOCR 1 2.897e-01 222.75 <9.520e-01 95.00 10 RM 49A FLOOR 1 2.897e-01 222.75 <l.447e-00 95.00 11 FM 49A FLOOR 1 <9.386e-03 95.00 <9.520e-01 95.00 12 RM 49 A FLOOR 1 2.897e-01 222.75 <9.520e-01 95.00 13 RM 49 A FLOOR 1 2.897e-01 222.75 <4.054e-01 95.00 14 RM 49A FLOOR 1 <9.386c-03 95.00 <3.167e-02 95.00 15 RM 47A HALL 1 2.J97e-01 222.75 <4.054e-01 95.00 AND FLOOR 16 RM 47A HALL & 1 <9.386e-03 95.00 <9.520e-01 95.00 FLOOR NOTE: THE ERRORS DO NOT INCLUDE INHERENT EFFICIENCY CALIBRATION UNCERTAINTIES.

- =-

g

.v Pag 312.0F;3. A L, ATTACBMENT 16:: -GROSS ALPHA / BETA-COUNTING RESULTSiFOR WIPE SAMPLES SSAMPLE COUNT ALPHA % ERROR BETA % ERROR I.D. LENGTH DPM/100 95%-CL DPM/100 95% CL MIN SQ. CM. SQ. CM. ~_________________________________________________________________. l17;RM'47ALBALL-& 1 <9.386e-03 95.00 <4.054e-01 95.00 ^>

FLOOR-18.RM 48l FLOOR 1

<9.386e-03 95.00 <3.167e-02 95.00 19 RM 48 FLOOR 1 <9.386e-03 95.00 <3.167e-02' 95.00 20 RM 48~ FLOOR' l- <9.386e-03 95.00 <4.054e-01 95.00

21. RM 48 FLOOR 1

<9.386e-03 95.00 <4.054e-01 95.00 2:2 HRM 48 FLOOR 1 <9.386e-03 95.00 <9.520e-01 95.00 23 RM 48 FLOOR 1 2.897e-01 222.75 <9.520e-01 95.00 24 RM,48 WALLS 1 2.897e-01 222.75 <9.520e-01 95.00 .25 RM 48 WALLS 1 <9.386e-03 95.00 <4.054e-01 95.00 ~26-RM 48 WALL'S 1 <9.386e-03 95.00 <1.447e-00 95.00 27 RM 48 WALLS 'l <9.386e-03 95.00 <4.054e-01 95.00 28 RM 48 WALLS 1 <9.386e-03 95.00 <3.167e-02 95.00 29 RM 48 WALLS 1 <9.386e-03 95.00 <1.447e-00 95.00 30 RM 48 WALLS 1 <9.386e-03 95.00 <4.054e-01 95.00 31 RM 49A WALLS 1 2.897e-01 222.75 <4.054e-01 95.00 32 RM 49 A WALLS 1 <9.386e-03 95.00 <9.520e-01 95.00 NOTE: THE ERRORS DO NOT INCLUDE INHERENT EFFICIENCY . CALIBRATION UNCERTAINTIES. t____________----.

@...1J A '~~ fy, iQ** f . ;I f :P2gT 3 OF>3" a , J.o ', - ' ATTACHMENT 16: GROSS ALPBA/ BETA COUNTING.RESOLTSiFOR WIPE SAMPLES SAMPLE' COUNT ALPHA .% ERROR BETA %. ERROR ' I. D. - LENGTH DPM/100 95% CL DPM/100 95%'CL' MIN SQ. CM. SQ. CM. 33 RM 49A WALLS 1 . 9.386e-03 95.00 <9.520e-01 -95.00 34 RM 49A WALLS 1 2.897e-01 222.75 <3.167e-02 95.00 35'RM 49A WALLS. l' .<9.386e-03 95.00 <3.167e-02 95.00 f 36 RM 49A WALLS 1 <9.386e-03 95.00 <4.054e-01 95.00 37 RM'49A WALLS .1 2.897e-01 222.75 <9.520e-01 95.00 38 RM-49A WALLS 1 '<9.386e-03 95.00' <9.520e-01 95.00 39 RM 50 WALLS 1 -1.277e+00 101.03 1.049e+00 136.30 L 40:RM'50 WALLS' 1 <9.386c-03. 95.00. 1.821e+00 92.61 L IJ 41.RM'50 WALLS 1 6.189e-01 147.45 1.110e+00 128.64 42 AVERAGE 1.521e-01 7.599e-01 43 HIGH 1.277e+00 1.821e'00 44 LOW 9.386e-03 3.167e-02 NOTE: THE ERRORS DO NOT INCLUDE INHERENT EFFICIENCY CALIBRATION UNCERTAINTIES. ._}}

ML20248B811

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