ML20044F845
| ML20044F845 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 04/09/1993 |
| From: | Edge H, Hilsmeier A, Kaeppel S ARMY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20044F822 | List: |
| References | |
| 27-43-E352-93, NUDOCS 9306010116 | |
| Download: ML20044F845 (66) | |
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.-' DEPARTMENT OF THE ARMY g
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HSHB-MR-HI (40) MEMORANDUM FOR Commander, U.S. Army Corps of Engineers, New England Division, ATTN: CENED-PD-L, 424 Trapelo Road, Waltham, MA 02254-9149
SUBJECT:
Industrial Radiation Study No. 27-43-E352-93, Reactor License Termination Verification Study, Army Material Technology Laboratory, Watertown, MA, 1 October 1992 - 9 April 1993
- 1. Copies of subject report with Executive Summary are enclosed. Findings, recommendation, specific requests by the Army Material Technology Laboratory (AMTL) and the Corps of Engineers (COE) personnel were discussed throughout the project. In addition to findings and the recommendation, specific issues concerning the Nuclear Regulatory Commission license, regulations and decommissioning guidelines were staffed with AMTL and COE personnel to affect the release of Building 100 for unrestricted use.
, 2. The final laboratory analyses of wipe test samples, air and water samples were completed on 9 April 1993. Survey data and sample analysis results I needed by AMTL to expedite the decommissioning operations were provided by
. telephonic consultations.
- 3. A copy of this report has been provided to the Nuclear Regulatory Commission as per your request.
FOR THE COMMANDER: Encl huua S ' RIS EDGE Chief, Industrial Health Physics Branch. Health Physics Division CF (w/ encl): HQDA (SAILE-ESOH/Mr. Lewis Walker) CDR, CE, ATTN DAEN-ECS-I CDR, AMC, ATTN: AMCSG CDR, AMC, ATTN: AMCSF-P CDR, LABCOM, ATTN: AMSLC-MC
# CDR, MTL, ATTN: SLCMT-DD CDR, HSC, ATTN: HSCL-P CDR, AMEDD CTR & SCHOOL CDR, MEDDAC, FT DEVENS, ATTN: PVNTMED SVC CDR, WRAMC, ATTN: HSHL-H-HP Nationally Recognized as the Centerof Matrixed Occupational and Environmental Health Etcellence l
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%)r/ l INDUSTRIAL RADIATION STUDY NO. 27-43-E352-93 REACTOR LICENSE TERMINATION J VERIFICATION STUDY ARMY MATERIAL TECHNOLOGY LABORATORY WATERTOWN, MASSACHUSETTS 1 October 1992 - 9 April 1993 Distribution limited to U.S. Government agencies only; protection of privileged information evalua. ting another command; May 93. Requests for this cicewnent must be referred to Commander, U.S. Army Corps of Engineers, L New England Division, ATTN: CENED-PD-L, 424 Trapelo Road, Waltham, MA 02254-9149.
Nationally Recognized as the Center of Matrixed Occupational and Environmental Health Excellence dae r or e n e t or cc ns ru t n ti e u en _ _ - - - - - - - - - --- - i
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DEPARTMENT OF THE ARMY
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- ' ABERDEEN PROVING GROUND. MARYLAND 210144422 ,
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SUMMARY
INDUSTRIAL RADIATION STUDY NO. 27-43-E352-93 REACTOR LICENSE TERMINATION VERIFICATION STUDY ARMY MATERIAL TECHNOLOGY LABORATORY WATERTOWN, MASSACHUSETTS' 1 October 1992 - 9 April 1993
- 1. PURPOSE. This. study was conducted to determine the presence and extent of health hazards after decommissioning of the Research Reactor (Building 100) operated by AMTL and to verify >
that any residual radioactivity is in compliance with the Nuclear Regulatory Commission regulations and guidelines for decontamination of facilities and equipment prior to release for unrestricted use.
- 2. CONCLUSION. A review of the survey results indicate.that ,
there were no radiological health hazards identified as a result
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of the decommissioning operations of Building 100. All areas were effectively remediated by AMTL to comply with the Nuclear Regulatory Commission regulations and guidelines.
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- 3. RECOMMENDATION. Recommend Building 100, to exclude the grounds surrounding Building 100, be released for unrestricted use.
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- a. < e, DEPARTMENT OF THE ARMY N U. S. ARMY ENVIRONMENTAL HYGIENE AGENCY 3 . g ABERDEEN PROVING GROUND. MARYLAND 210104422 i ,
U T.IS er HSHB-MR-HI 'g 4 g g INDUSTRIAL RADIATION STUDY NO. 27-43-E352-93 REACTOR LICENSE TERMINATION VERIFICATION STUDY ARMY MATERIAL TECHNOLOGY LABORATORY WATERTOWN, MASSACHUSETTS 1 October 1992 - 9 April 1993 I. REFERENCES. See Appendix A for a list of references. II. AUTHORITY. A. AEHA Form 250-R, CENED, 28 July 1992. B. Memorandum, COE, CENED-PD-L, 19 September 1991,-subject: Decommissioning and Demolition of Research Reactor, Base Closure, Army Material Technology Laboratory-(MTL), Watertown, MA. III. PURPOSE.
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A. To assess radiological contamination remaining in Building 100 after decontamination was performed by AMTL. B. To determine if any residual radioactivity remaining after decontamination is in compliance with the Nuclear Regulatory Commission (NRC) standards for clean-up of buildings potentially contaminated with residual radioactive materials. IV. GENERAL. A. Meetings and briefings were conducted with Mr. Peter Cornetta, Department of the Army Civilian (DAC), Radiation Protection Officer (RPO), AMTL; CPT Joy Howard, MS, Alternate RPO, AMTL; Mr. Dennis Waskiewicz, Project Engineer, Life Cycle Project Management Section, Corps of Engineers, New England Division (CENED) ; Mr. Francis Donovan, Assistant Area Engineer, Eastern Area Office, CENED; and Ms. Laura Brodman, Base Realignment and Closure Office (BRAC), to discuss findings'and the recommendation. B. The study was performed by Mr. Allen Hilsmeier, DAC, Team Leader; 2LT Scott Kaeppel, MS, Onsite Team Leader;
, SFC Scott Goodison, USA, Senior Technician; 1LT John Cuellar, MS; and CPT Robert Gibbons, MS, during the period 1 October 1992 -
9 April 1993. (
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Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 C. The above mentioned survey personnel are qualified Health ! Physicists and have varied expertise in radiological health issues. Each individual was provided all occupational health and safety , training at AEHA and at AMTL to effect a' safe working environment. D. Laboratory analyses were performed by the Radiochemistry Analysis Branch (RAB) of the Directorate of Laboratory Services i (DLS) of USAEHA. E. The verification study is a Quality Assurance / Quality Control (QA/QC) instrument. It is used to verify an NRC licensee's - final termination survey or a close-out study of operations involving radioactive material. A verification study is an independent sampling of the licensee's or installation's more elaborate study (termination or close-out), and not a~ complete duplication. The study is intended.to supplement the termination survey and collectively ensure compliance with all applicable i Federal, State, and Local radiological regulations. i F. A' the time of this study, the reactor grounds and the surroundi J grounds on which the reactor building is located , (Building 100, reactor ground) still had on going activities involving radioactive materials. The on going activities consisted of scabbling of concrete and radioactive waste storage. A , verification study of the site grounds will be performed upon l termination of the current on going operations and the completion of any further required decommissioning. Therefore only the. decommissioning of the interior of building 100, which was
- decommissioned and evaluate'd so the structure could be dismantled and ultimately released for unrestricted use, is. included in this report. The reactor grounds will be surveyed later and its release will be in conjunction with release of the facility grounds for t
unrestricted use. G. This verification study does not include the surveys'of the open excavated areas outside of the reactor building where Cistern ' 242, the Pipe Chase, and the Secondary Coolant Pumps had been removed. These locations are small isolated areas of the entire reactor grounds. However these areas will be included in the site decommissioning and a recommendation for release will be provided , with the facility grounds.
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V. BACKGROUND. A. CHRONOLOGY. 2 ; i l __ _ , _ _ , _ _ .1
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'. '. i - Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93
- 1. The AMTL open_ pool materials research reactor, housed in Building 100, was built in the late 1950s. It was operational between June 1960 and March 1970. The AMTL NRC License Number R-65 allowed AMTL to study molecular and atomic material structures and solid state physics. ,
- 2. The reactor was deactivated in 1970 and a :
deactivation report submitted to the Atomic Energy Commission ! (AEC) in December 1970. All the reactor fuel, exhaust filters, l' the radioactive waste processing system, and many of the reactor components were removed from Building 100 and disposed-in accordance with NRC and Army procedures. !
- 3. Project management for final decommissioning of the ;
facility was conducted through the U.S. Army Corps of Engineers, ! New England Division, which in turn contracted Morrison Knudsen Corporation (MK) as the prime contractor for the decommissioning. The MK contracted Scientific Ecological Group, Inc. (SEG) to , provide radiation protection support. 3
- 4. The reactor building had a radiological characterization survey performed in 1990 to assess the residual radioactive waste. The physical decommissioning-of the AMTL -
reactor commenced in June 1992.
- 5. The USAEHA started its document review and preliminary site investigation in October 1992.
- 6. Decommissioning of the reactor by the licensee was. ;
completed in January 1993. In January of 1993, USAEHA began
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reviewing SEG's working termination files of the reactor. These ; files were the raw data and field notes recorded by the termination survey teams.
- 7. In February and March 1993, USAEHA conducted a verification study. The verification study consisted of an independent survey of 10 percent of the grid system surveyed by SEG. In addition, a biased sampling was conducted of special areas where residual radioactivity could have accumulated.
- 8. The USAEHA provided preliminary results of the verification study to AMTL on 30 March 1993. This telephonic I communication stated that all measurements and samples were below NRC guideline values.
- B. SITE CONDITION AT TIME OF VERIFICATION STUDY.
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. I j Industrial Radn Study.No. 27-43-E352-93, 1 Oct 92-9 Apr 93 1 1
- 1. Before MK began decommissioning Building 100, it housed
- the control room, the reactor vessel, a coolant system, a gamma 1
well facility, two platforms above ground level to conduct
- experiments, the bioshield made of high density concrete j impregnated with lead shot, the walls on each floor, floor areas 4 and equipment (see Diagram la).
- 2. After decommissioning, the only remaining areas were the outer walls of Building 100, a basement, a gamma well, a sump, several excavated ditches in the floor of the basement, two ,
airlocks, the newly constructed equipment shed, and the 10-ton rotatable crane (see Diagram lb) . ,
- 3. The walls and the crane were lined.with scaffolding for ,
easy access to all survey grids. The survey grids covered the entire surface of all walls and ceilings.
- 4. Every area within Building 100 was classified asfan affected area as defined in the decommissioning plan approved by the NRC. An affected area is defined as.an area that has potential or known radioactive contamination.
- 5. Building 100.is surrounded by grass ~and i:s connected to Building 97 through Airlock #1. Service piping from Building 100 to Building 97 was removed and the excavation, i.e.,fthe pipe chase, was left open for future survey. Cistern 242, and.the >
secondary coolant sump, with pumps and piping to the reactor, was also removed and the open excavation left uncovered for future surveys (see Diagram 2).
- 6. The survey data packets prepared by SEG of Building 100 and surrounding excavation sites showed that all residual radioactive contamination was below NRC guidelines.
C. IDENTITY OF POTENTIAL CONTAMINANTS / RELEASE GUIDELINES. .
- 1. As.a result of the characterization survey and the termination survey, the significant radiological contaminants were ,
determined to be cesium-137, isotopes of europium, cobalt-60, and tritium. On the basis of this combination of contaminants, the surface' contamination guideline values for the site are as stated in NRC Regulatory Guide 1.86 and Title 10 and Code of Federal Regulations (10 CFR), Part 20 (see Table la and lb). ; i p 4
Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 Table la. Acceptable surface Contamination Levels Excerpt from NRC Regulatory Guide 1.86 NUCLIDE' AVERAGE' b MAXIMUMbd REMOVABLEbe __. Transuranics, Ra-226, Ra-228 and other Alpha 100 dpm/100cm2 300 dpm/100cm2 20 dpm/100cm2 Emitters Beta-gamma emitters 5000 dpm/100cm2 15000 dpm/100cm2 1000 dpm/100cm2
*Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists,the limits established for alpha- and beta-ganuna-emitting nuclides should apply independently.
"As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
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' Measurements of average contaminant should not be averaged over more than i square meter. For objects of less surface area, the average should be derived for each such object.
. *The maximum contaminationlevel applies to an area of not more than 100cnf.
'The amount of removable radioactive material per 100 cn/ of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
Table Ib. , Concentrations in Air and Water - Above Natural Background Excerpt from 10 CFR Part 20 Appendix B Table 2 Isotope uCi/ml in Air uCi/ml in Water 4 cesium 137 2 x 10* 1x 10 cobalt 60 2x 10* 3 x 10 4 , l i Tritium (Hydrogen 3) l 1x 10 4 1 x 10 4 I Europium 154 3 x 10-" . 7x 10 4 4 . Europium 152 3 x 10~" 1x 10 5
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- Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 VI. RADIATION SURVEYS AND RESULTS.
A. INSTRUMENTATION / EQUIPMENT.
- 1. A list of instruments, parameters, efficiencies, and MDA are provided in Table 2. All survey meters were calibrated on a quarterly basis. Efficiencies were determined with a radioisotope traceable to National Institute of Standards and Technology (NIST) which had energies similar to the energies of the isotopes listed in paragraph V.c.1. above.
- 2. An efficiency factor was developed for alpha and beta instruments to correlate the meter reading to the actual radioactivity present.
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- 3. A conversion factor was applied to extrapolate from the l' l probe surface area to a norma.lized 100 square centimeter surface area.
- 4. The efficiency value of the instrument coupled with the ,
surface area conversion factor was used to record the final reading
- into standardized regulatory criteria expressed in disintegrations per minute (dpm) per 100 square centimeters. , ,
- 5. The sensitivity of the gamma survey meter was taken ;
from NUREG/CR-5849, Table 5-6. l
- 6. All portable survey meters were checked for operability prior to packaging and shipping to AMTL, upon arrival at the survey site, before each day of surveying, during the survey and after any malfunctions or repairs.
- a. Alpha. Operational instrument checks were performed >
with a NIST traceable thorium-230 source with an activity of 6780 dpm verified on 3 June 1992. All operational checks were made on ; contact with the alpha source. The same procedures were used for i cach check to assure reproducability. Each operational check was 2850 cpm / probe area i 16 %. ; t
- b. Beta. Operational instrument checks were performed with a NIST traceable technetium-99 source with an activity of 5990 dpm verified 4 June 1992. All operational checks were made at 1 cm from the beta source. Each operational check was 1200 cpm / probe
, area +10 %. l l
- c. Gamma. Opeiational instrument checks were performed i with a NIST traceable cesium-137 source with an activity of 1.1 pCi verified 12 June 1992. Each operational check was 320 pR/hr 110 %.
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. Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 I l
1 I i l Table 2 ; INSTRUMENTATION ! ALPHA BETA GAMMA Make Eberline Eberline Eberline Model ESP-2 E-520 PRM-7 Serial Number 00358 315 435 Calibration Date 13 Jan 93 4 Dec 92 17 Nov 92 Efficiency 41.3% 20.0% 11.8% Average Background 1 cpm 50 cpm 9 uR/hr
< Background >
MDA' 74 dpm/100cm2 2900 dpm/100cm2 .
- The Eberline PRM-7 sensitivity is approximately 1 yR/hr (reference 1, page 5.14).
The MDA of a ratemeter instrument for surface activity measurements can be , approximated by taking twice the time constant of the meter as the counting time and using the relationship: i MDA = 4.65 * (Ba/ (2 *t ri l r2 E* (A / 100) MDA = activity level in disintegrations / minute /100cm2 B, = background rate in counts / minute t, = meter time constant in minutes E = detector efficiency in counts / disintegration A = active probe area in cm2 l PROBES j Make Eberline Eberline Internal l Model AC-3 HP-210 1x1 NaI(Tl) l 10 l l l l
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Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 B. INSTRUMENTATION SURVEY.
- 1. The instrumentation survey was conducted in the pre-established area classification, as described by the decommissioning plan, and in the established grid system used by SEG in the Termination Survey. Building 100 was divided into smaller sections to allow easier manageability of data. The subsections are found in Appendix B with the survey results.
- 2. The AEHA reviewed SEG's data for each surveyed area, and evaluated elevated survey results in relationship to the survey grid system. Tne survey grid system used alpha numeric designator.
Rows would be designated by a letter and columns designated by a number. The AEHA randomly selected 10 % of the grids surveyed by SEG and included some biased grids which had elevated readings during the review of data. Field survey packets were assembled to include background values, flag values, and grids to be surveyed for each type of radiation.
- 3. Flag values, or action levels, were established for each type of survey instrument used. Flag values were established by taking 70%.of the guideline values found in Table la. If any instrument reading exceeded the flag values, then a more thorough investigation of that area would be conducted to determine if the detected radiation was above guidelines listed ir. Tables la and 1b.
- 4. Along with surveying 10% of the grids in Building 100, AEHA conducted independent surveys on areas where residual radioactivity would likely be found. The survey officers surveyed cracks in the floors, seams where walls met floors, holes in the walls, pipes entering Building 100, and other areas. All these independent surveys resulted in only background radiation being detected.
C. SURVEY RESULTS.
- 1. Background Results. Background measurements were taken from an unaffected area (as determined by the decommissioning plan I approved by the NRC) of a building located on MTL. Five background measurements were taken for each type of radiation to be monitored.
The average background values were established at a 95 % confidence level.
- a. Alpha. Background instrumentation readings varied from 0 to 2 counts per minute (cpm). The average background alpha activity was 1 cpm / probe area. After correction for probe area and efficiency, the background was established at 2 dpm/100 cm ,2 311
, alpha radiation measurements were taken at 1 centimeter (cm) or ! 1 11 I l 4 I
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. Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 less from the background surface. :
- b. Beta. Background instrumentation readings varied from f 40 to 60 cpm. The average background beta activity was-50 cpm / probe !
area. After correction for probe area and efficiency,-the l background was established at 1600 dpm/100 cm.2 All measurements i were taken at about 1 cm from the background surface. l
- c. Gamma. Background instrumentation readings varied from i 7 to 10 pR/hr. The average background gamma exposure was 9 pR/hr.
All gamma measurements were taken at 1 meter from the. background surface. .
- 2. Instrumentation Survey Results. ,
- a. Alpha Instrumentation Results. The fixed' alpha :
activity ranged from a low of less than MDA to a maximum of 208 [ dpm/100 cm above background. The average of 5 points within a 2 square meter around the 208 dpm/100cm2 was less than 100'dpm/100cm 2, 2 The MDA was determined to be 74 dpm/100 cm. All alpha activity results and locations of surveys aru presented in Appendix B. All readings were taken at 1 cm or less'from the surface for at least 4 seconds for each reading. One reading was.taken in the center of ; the survey grid.
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- b. Beta Instrument Results.. The beta activity ranged from a low of less than the MDA to a maximum of 2600 dpm/100 cm2 above 2
background. The average beta background was 1600 dpm/100cm. The 2 MDA was determined . to be 2900 dpm/100 cm . All beta-gamma survey results and locations are presented in Appendix B. A survey.was , first conducted over the survey grid to be monitored. Five meter l readings were then taken at 1 cm from the surface. The instrument was held stationary for 4 seconds for each reading. ,
- c. Gamma Instrument Results. Each grid was surveyed to ,
identify any potential hot spots. A gamma reading was taken from ( the location in the grid with the highest activity. The results i listed in Appendix B are the highest values recorded for the instrumentation survey. When the background of 9 pR/hr is subtracted from the highest value of 19 pR/hr at the surface, 10 pR/hr is the highest exposure above background. When the inverse j square law is applied to the 10 pR/hr at 1 meter, the highest l reading at 1 meter is well within the regulatory limits of 5 pR/hr ; above background. In addition to this more stringent analysis, I exposure rate measurements were taken at 1 meter above the surface ; Et o verify that a uniformly distributed low level of contamination 1 was not present on the surface. The instrumentation surveys i indicated only background readings. 12
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. Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 - 3. Wipe Test Surveys. Wipe test surveys were performed to determine the presence of removable contamination on surface areas. Wipe test surveys were performed in each grid surveyed in Building 100. All wipe test samples were collected and analyzed for gross alpha and gross beta activity. If any activity was found higher than 50 percent of the guideline values listed in the NRC Regulatory Guide 1.86, then a gamma spectral analysis was performed for that sample. Blank wipes were used to screen for cross contamination,
- a. The gross alpha activity ranged Thefromlower a lowlimit of less than '
1 dpm/100cm 2 to a high of 1 1 1 dpm/100cm. of detection at 95 % confidence level was determined to be less than 2 dpm/100 cm. All gross alpha activity results and locations 2 where wipe tests were taken are included in Appendix B.
- b. The pross beta-gamma activity ranged The 2 fromlower a lowlimit of less than 3 dpm/100cm to a high of 6 1 3 dpm/100 cm.
of detection at 95 % confidence level was determined to be less than 3 dpm/100 cm . All gross beta-gamma activity results and 2 locations where wipe tests were taken are included in Appendix B.
- 4. Water Samples. The floor of Building 100 is all concrete. There is a gamma well and a sump well located in the
. basement. Both wells had water in them at the time of the survey.
The water was first stirred and then a sample was collected. The water samples were analyzed for tritium, and by gamma spectral analysis to determine the presence of tritium or any gamma radiation emitters. The results of the tritium analysis and the gamma spectrum analysis are found in Table 3. The water sample results indicate that the activities for all interested isotopes were less than the minimum detectable activities.
- 5. Air Samples. Building 100 was one large open area after the contractors removed all contamination. The air sample was collected at breathing zone level from the center of the floor area in Building 100. The sample was analyzed for gross alpha and gross beta activity. The results indicated that the gross alpha and gross beta-gamma activities were less than the minimum detectable activities. The air sample results show that radioactivity in the air was lower than the most restrictive ;
isotope listed in Table Ib. 13
. Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93 TABLE 3 WATER SAMPLES RESULTS Liquid Scintillation RESULTS OF GAMMA SPECTRAL ANALYSIS Results Sample Microcuries per Milliliter as of Collection Date Identification at 95 % confidence level H-3 I-131 Cs-137 Eu-154 Co-60
# 2-Reactor Gamma Well < 4.7 x 10 4 < 3 x 10-' <2x 10' ' < 6 x 10 ' < 2 x 10
# 3-Reactor
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Sump < 4.8 x 10 4 < 3 x 10~' <2x 10 < 5 x 10 < 2 x 10-7 The < in the above results indicates < MDA. The values given are the MDA for that isotope for that type of analysis. Table 4 RESULTS OF GROSS ALPHA AND GROSS BETA OF THE AIR FILTER ANALYSIS Sample Microcuries per Milliliter of Air Identification at 95 % confidencelevel
#1-Reactor Gross Alpha Gross Beta Air Sample
< 1.3 x 10" < 3 x 10'"
The < in the above results indicates < MDA. The values given are the MDA for that isotope for that type of analysis. 14
Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93
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VII. CONCLUSIONS. A review of the survey results indicate that - there were no radiological health hazards identified as a result of the decommissioning operations involved with Building 100. VIII. RECOMMENDATIONS. Recommend Building 100, to exclude the , surrounding grounds, be released for unrestricted use and the surrounding grounds transferred over to one of the other facility licenses. 1 fbps { l'JMf/3 ALLEN E. HILSMEIER Health Physicist Health Physics Division SCOTT J. KA[PPEL 2LT, MS Nuclear Medical Science Officer Hea)th Physics Division ' fI . l$:l u . . /n COTT G. GOODI3ON SFC, USA Health Physics Specialist Health Physics Division AP ROVED: e/
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1 IS EDGE ' Chief, Industrial Health Physics Branch Health Physics Division i l i I 15
i I s Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9 Apr 93
. APPENDIX A REFERENCES
- 1. NUREG/CR-5849, Manual for Conducting Radiological Surveys in support of License Termination, Draft Report for Comment, June ,
1992.
- 2. NRC Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, June 1974.
- 3. U. S. Army Materials Technology Laboratory Research Reactor Decommissioning, Final Survey Report, Volume 1 cf 1, March 1993.
- 4. The Health Physics and Radiological Health Handbook, Nucleon Lectern Associates, 1984.
- 5. Title 10, Code of Federal Regulations (CFR), 1992 Rev., Parts 30.36 and 70.38, Nuclear Regulatory Commission (NRC).
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- 6. Title 40, CFR, 1991 Rev., Chapters 260 and 261, Environmental Protection Agency (EPA).
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- 7. NUREG/CR-2082, Monitoring for Compliance with Decommissioning Termination Survey Criteria, June 1981.
- 8. AR 385-11, May 1980, Ionizing Radiation Protection (Licensing, Control, Transportation, Disposal, and Radiation Safety).
- 9. Federal Register, Part VI, Nuclear Regulatory Commission, 10 CFR Part 20 et. al., Standards for Protection Against Radiation; '
Final Rule, Tuesday May 21, 1991. i i I i A-1
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Industrial Radn Study No. 27-43-E352-93, 1 Oct 92-9.Apr 93 e t a t APPENDIX B L RADIOLOGICAL SURVEY RESULTS
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I Reactor Building 100 l Interior of the Ceiling Dome , 4 February 1993 l laation Gross
- Gross Gross Beta Removable Removable Smear Code alpha Gamma Gross Alpha Gross Beta #
Units = = > [dpm/100cm'] uR/hr [dpm/100cm'l Idpm/100cm'l MDAs = = > MDA = 79 MDA = 2900 f,2 standard deviations A43 <MDA 5 <MDA <MDA <MDA <MDA 3200 <1 <3 70 E03 <MDA 4 <MDA <MDA <MDA <MDA <MDA <l <3 57 D17 <MDA 5 <MDA < MDA <MDA <MDA <MDA <1 <3 58 D23 <MDA 4 < MDA <MDA <MDA <MDA <MDA <1 <3 59 D04 < MDA 3 <MDA < MDA <MDA <MDA <MDA <1 <3 60 C09 <MDA 4 <MDA - < MDA <MDA <MDA < MDA <1 <3 61 C29 <MDA 3 <MDA < MDA <MDA <MDA <MDA <1 <3 64 Cl4 <MDA 4 < MDA <MDA <MDA < MDA <MDA <1 <3 62 C21 100 3 < MDA < MDA <MDA < MDA <MDA <l <3 63 A28 <MDA 5 < M DA <MDA <MDA <MDA <MDA <1 <3 71 A08 <MDA 4 < MDA <MDA <MDA <MDA <MDA <1 <3 68 A51 <MDA 4 <MDA 3900 3500 3200 <MDA <1 <3 69 B30 110 3 <MDA <MDA <MDA <MDA < MDA <1 <3 65 B21 <MDA 3 <MDA <MDA <MDA <MDA <MDA <1 <3 66 B07 <MDA 4 < MDA <MDA <MDA <MDA <MDA <1 <3 67
- Maximum in ! quare meter Background was not subtractedfrom above data.
Alpha background = 2 dpm/100cnf Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr i l B-2
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e . Reactor BuilJmg 100 Interior Retainment Wall 4 February 1993 1;xation Grous* Gross Gross Beta Removable Removable Smear Cale alpha Gamma Gross Alpha Gross Beta # Unita = = > jdpm/100cm'] uR/hr [dpm/100enfj [dpm/100cnfi M D Aa = = > MDA = 79 MDA = 2900 12 standard deviations All <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 72 A26 <MDA 10 <MDA < MDA <MDA <MDA <MDA <1 <3 73 A36 86 10 3200 <MDA <MDA < MDA < MDA <1 <3 74 A51 98 9 <MDA < MDA 3200 <MDA 3200 <1 <3 75 A65 < MDA 9 <MDA < MDA 3200 3200 3200 <1 <3 76 B3 78 9 <MDA 32(0 <MDA <MDA < MDA <1 <3 77 B23 <MDA 9 <MDA < MDA < MDA <MDA < MDA <1 <3 78 B31 <MDA 8 <MDA < MD A 3200 <MDA <MDA <1 <3 79 B44 <MDA 10 <MDA < MDA < MDA <MDA <MDA <1 <3 80 B58 <MDA 10 < MDA < MDA < MDA 3200 < MDA <l <3 81 B71 < p rs . 10 <MDA < MDA 3200 <MDA <MDA <l <3 82 C3 <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 83 CS <MDA 10 <MDA <MDA 3200 <MDA <MDA <1 <3 84 C16 <MDA R <MDA <MDA <MDA <MDA <MDA <1 <3 85 C23 <MDA 9 <MDA <MDA <MDA < MDA <MDA <1 <3 86 Di < MDA 10 <MDA <MDA <MDA <MDA <MDA <1 <3 90 D9 <MDA 9 <MDA <MDA <MDA 3200 <MDA <1 <3 89 D19 94 10 <MDA <MDA <MDA <MDA <MDA <1 <3 88 D21 <MDA 10 <MDA < MDA <MDA <MDA <MDA <1 <3 87 D25 <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 91 E5 <MDA 8 < MDA < MDA 3200 < MDA <MDA 1ii <3 92 E13 <MDA 10 < MDA <MDA <MDA <MDA < MDA <l <3 93 E14 lho 13 3200 < MDA <MDA <MDA <MDA <1 <3 94 E18 <MDA 8 <MDA < MDA <MDA <MDA <MDA <l <3 95 F2 130 9 <MDA 3200 <MDA <MDA <MDA <1 <3 97
- Maximum in i square meter llackground was not subtractedfrom above data.
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Alpha background = 2 dpm/lO0enf Beta backgmund = 1600 dpm/100cn/ l Gamma background = 9 uR/hr ii-4 l
l Rescior Building 100 Interior Retainment Wall 4 February 1993 U c ation Gross
- Gross Gross Beta Removable Removabic Smear Ccx!c alpha Gamma Gross Alpha Gross Beta #
Units = = > [dpm/100cnfj uR/hr [dpm/100cm'l [dpm/100cm'] MDAs = = > MDA = 79 MDA = 2900 12 standard deviation I7 94 17 <MDA 3500 <MDA 3500 <MDA <1 <3 98 F10 <MDA 17 <MDA <MDA <MDA <MDA <MDA <1 <3 99 F21 < MDA 19 <MDA <MDA <MDA < MDA <MDA <1 <3 100 F26 <MDA 9 <MDA <MDA 3200 <MDA <MDA <l <3 96
- Manimum in I squass sneur kckground was mot subtractedfrom above data Alpi.s hackground = 2 dem/100cnf Beta backgmnd = 1600 dpm/100cm' Gamma i ackground = 9 uk/hr l
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Reactor Building 100 Interior Operation Deck Floors I and 2 9 February 1993 Loc ation Gross' Gross Gross Beta Renv>vable Removable Smear Cmie alpha Gamma Gross Alpha Gross Beta # Units = = > (dpm/100cm'l uR/hr [dpm/100cm'] [dpm/100cm'l MDAs = = > MDA = 79 MDA = 2900 f.2 standard deviations F01-C2 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 til F01- A5 <MDA 9 <MDA 3200 <MDA <MDA <MDA <2 <3 110
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F01-D4 <MDA 9 <MDA 3200 <MDA <MDA <MDA <2 <3 109 F01-F3 < MDA 8 3200 <MDA <MDA < MDA <MDA <2 <3 108 F01 F6 <MDA 8 <MDA <MDA <MDA <MDA <MDA <2 <3 107 F01-G8 <MDA 9 <MDA <MDA 3700 <MDA <MDA <2 <3 106 F01-17 <MDA 10 <MDA <MDA <u t <MDA <MDA <2 <3 105 F01-310 < MDA 10 <MDA <MDA < M v.; <MDA <MDA <2 <3 103 F01-K8 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 104 F01-Lil < MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 10'2 F01-M 13 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 101 F02-M2 <MDA 9 <MDA <MDA <MDA < MDA < MDA <2 <3 112 F0243 < MDA 9 <MDA <MDA <MDA <MDA < MDA <2 <3 113 F02-15 < MDA B <MDA <MDA <MDA <MDA <MDA <2 <3 115 F02-17 <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 116 F02-G10 <MDA 9 < MDA <MDA <MDA <MDA <MDA <2 <3 117 F02-F4 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 118 F02-F7 <MDA 8 <MDA <MDA <MDA <MDA < MDA <2 <3 119 F02-D6 <MDA 9 <MDA <MDA <MDA < MDA <MDA <2 <3 120 F02-D12 <MDA 9 <MDA <MDA <MDA < MDA <MDA <2 <3 114 F02-Cl3 <MDA 9 <MDA <MDA <MDA < MDA <MDA <2 <3 121 F02-A9 <MDA 8 < MDA <MDA <MDA <MDA <MDA <2 <3 122
- Maximum in I muare meter llackground was not subtractedfrom above data.
Alpha background = 2 dpm/10(Am' Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr o D B-7
Reactor Building 100 Interior Operation Deck Floors 3 and 4 9 February 1993 lecation Gross
- Gross Gmss Beta Removable Removable Smear Cale alpha Gamma Gross Alpha Gross Ikta #
Units = = > (dpm/100c m') uR!br [dpm/100cm'] {dpm/100cm') MD As = = > MDA = 79 MDA = 2900 12 standard deviations F03-El <MDA 8 < MDA < MDA <MDA <MDA <MDA <2 <3 138 F03-B3 <MDA 9 < MDA <MDA 4200 <MDA <MDA <2 <3 139 F03-D6 120 9 <MDA <MDA <MDA <MDA <MDA <2 <3 140 F03-G7 <MDA 8 < MDA <MDA <MDA <MDA <MDA <2 <3 137 F03-H10 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 136 F03-13 <MDA 8 < MDA <MDA <MDA <MDA 3200 <2 <3 135 F0345 <MDA 9 <MDA <MDA <MDA <MDA 3200 <2 <3 134 F03-il2 <MDA 9 <MDA < MD A <MDA <MDA <MDA <2 <3 133 F03-K8 < MDA 8 <MDA 3200 <MDA <MDA <MDA <2 <3 132 F03-K12 < MDA 9 <MDA <MDA <MDA 3200 <MDA <2 <3 131 F03-M10 140 10 <MDA <MDA <MDA <MDA <MDA <2 <3 130 F04-M2 <MDA 9 <MDA <MDA <MDA < MDA <MDA <2 <3 150 F0443 <MDA 9 <MDA <MDA <MDA <MDA < MDA <2 <3 149 F04-G3 210 8 <MDA < MDA <MDA <MDA <MDA <2 <3 148 F04-E4 <MDA 9 < MDA < MDA <MDA <MDA <MDA <2 <3 147 F04-K5 <MDA 9 <MDA < MDA <MDA <MDA <MDA <2 <3 146 04-K5 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 145 F04-Il6 < MDA 7 <MDA <MDA <MDA <MDA <MDA <2 <3 144 F04-F6 <MDA 9 < MDA <MDA <MDA 3900 3200 <2 <3 143 i F04 F10 <MDA 9 < MDA 3900 3200 <MDA <MDA <2 <3 142 F04-B9 120 8 <MDA <MDA <MDA <MDA <MDA <2 <3 141
- Maximumin i square meter llackground was not subtractedfrom above data.
Alpha background = 2 dpm/100em 2 Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr I 0 3 B-8
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U.S. ARMY ENVIRONMENTAL HYGIENE' AGENCY SCALE NTS- -- - UNITED STATES ARMY MEDICAL DEPARTMENT l pt37e _ _ _ B-9. I
s .. Reactor Building 100 Basement Area I 9 February 1993 location Grod Gross Gross Beta Removable Removable Smear Code alpha Gamma Gmns Alpha Gmss Beta # Units = = > [dpm/100cnf] uR/hr [dpm/100cm'] Idpm/100cm2 ] MDAs = = > MDA = 79 MDA = 2900 12 standard deviations F01 A2 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 123 F01 B4 <MDA 12 <MDA 3900 <MDA (MDA < MDA <2 <3 124 F01-C6 <MDA 9 <MDA <MDA < MDA <MDA <MDA <2 <3 125 I F01-D8 <MDA 7 3200 <MDA <MDA <MDA < MDA <2 <3 126 F01 Ell <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 127 F01-Fl3 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 128 F01-G12 <MDA 10 3200 3900 <MDA <MDA < MDA <2 <3 129 F01 Ll3 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 150 F01 Kil < MDA B <MDA <MDA 3200 < MDA 3200 <2 <3 151 F0149 <MDA 9 3900 <MDA <MDA <MDA <MDA <2 <3 152 F01-09 <MDA 8 <MDA <MDA <MDA <MDA < MDA <2 <3 153 F01-l7 <MDA 10 <MDA <MDA 3200 3200 <MDA <2 <3 154 F01 F4 <MDA 8 3200 3200 <MDA < MDA <MDA <2 <3 155 W0l Al <MDA 8 <MDA <MDA <MDA <MDA <MDA <2 <3 156 W01-D3 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 184 W01-E5 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 185 W01-A6 <MDA 10 <MDA <MDA <MDA <MDA < MD A <2 <3 157 W0148 <MDA 12 <MDA <MDA <MDA <MDA <MDA <2 <3 161 W01-E10 < MDA 10 <MDA <MDA <MDA 3200 <MDA <2 <3 179 W01-Al2 < MDA 8 <MDA <MDA <MDA <MDA < MDA <2 <3 158 W01-Cl4 <MDA Il <MDA <MDA <MDA <MDA < MDA <2 <3 160
- Maximum in i square meter Bakround m not subtracted from above data.
Alpha background = 2 dpm/100cm' Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr i I i
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I l t *, j l i Reactor Buildmg 100 Basement Area 1 9 February 1993 Gross a Gmss Gross Beta Removable R e mov at,1c Smear Location Code alpha Gamma Gmss Alpha Gmss Beta # Umis = = > (dpm/100cm'l uR/hr [dpm/100cm'] [dpm/100cnfl MDAs= = > MDA = 79 MDA = 2900 + standard deviation l WOI-El6 <MDA 10 < MDA < MDA <MDA <MDA <MDA <2 <3 178 WOI-C18 <MDA II < MDA <MDA <MDA <MDA < MDA <2 <3 162 W01-A21 <MDA 9 < MDA < MDA <MDA <MDA <MDA <2 <3 159 W01 E09 <MDA 10 <MDA * * * * <2 <3 171 WOI-P16 < MDA 10 < MDA * * * * <2 <3 180 W01.E02 <MDA 9 <MDA * * * * <2 <3 170 W01-P02 <MDA 9 < MDA * * * * <2 <3 183 WO2-B2 < ML)A 11 < MDA < MDA <MDA <MDA <MDA <2 <3 175 , i WO2-B6 <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 176 WO2-12 <MDA Ii < MDA <MDA <MDA <MDA < MDA <2 <3 182 WO3-A2 <MDA 9 < MDA < MDA <MDA <MDA <MDA <2 <3 172 WO3-B6 <MDA 10 <MDA < MDA <MDA 3200 3200 <2 <3 173 WO3-Al l <MDA 10 < MDA (MDA <MDA < MDA < MDA <2 <3 174 WO4-C2 < MDA 4 < MDA <MDA <MDA < MDA 3200 <2 <3 166 WD4- A4 <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 165 , WOS-Al 120 12 < MDA <MDA <MDA <MDA <MDA <2 <3 163 l WOS-C4 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 164 i Cl B2 <MDA 10 < MDA < MDA <MDA <MDA <MDA <2 <3 181 i I Cl-A8 <MDA 10 <MDA < MDA <MDA < MDA <MDA <2 <3 177 F01-507 210 12 3200 * * * * <2 <3 167 F01-510 <MDA 11 <MDA * * * * <2 <3 168 F01-50) < MDA 12 < MDA * * * * <2 <3 169 !
' Maximum in I square meter flackground was not subtractedfrom above data.
Alpha backgmund = 2 dpm/100cm' Beta backgrnund = 1600 dpm/l(XAm' Gamma backgmund = 9 uR/hr
- Structure surveyed not large enough for five readings.
The structure was surveyed and the highest value recorded. B-11 l
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Units = = > Idpm/100cm2] uR/hr [dpm/100cm'] MDAs= = > MDA = 79 MDA = 2900 F01-A4 82 10 <MDA <MDA < MDA <MDA <MDA <2 <3 198 F01-B13 <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 199 F01-Cl <MDA 9 3900 <MDA <MDA <MDA <MDA <1 <3 207 F01-D9 <MDA 12 3200 <MDA <MDA <MDA <MDA <l <3 208 F01 E3 <MDA 10 3200 <MDA <MDA <MDA < MD A <1 <3 209 F01-E5 <MDA 13 <MDA <MDA <MDA <MDA 3900 <1 <3 210 F01-E12 <MDA 11 <MDA <MDA <MDA 3200 <MDA <1 <3 211 F01 F1 <MDA 10 <MDA <MDA <MDA <MDA < MDA <1 <3 214 F01-G6 <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 217 F01-Gil <MDA 10 3200 <MDA <MDA <MDA <MDA <1 <3 212 F01-13 < MDA 9 <MDA <MDA <MDA <MDA < MDA <1 <3 213 F01-17 <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 216 F01-Kl <MDA 10 <MDA <MDA <MDA <MDA <MDA <1 <3 215 F01-L5 <MDA 11 <MDA <MDA <MDA <MDA < MDA <1 <3 218 WOI-B1 <MDA 9 <MDA <MDA <MDA <MDA < MDA <1 <3 219 WOI-D3 <MDA 9 <MDA 3200 < MD A <MDA <MDA _
<2 <3 195 WOI-C5 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 194 WOI-A6 <MDA 9 <MDA 3200 <MDA < MDA <MDA <l <3 220 W01-A9 <MDA 11 <MDA <MDA <MDA <MDA <MDA <1 <3 221 WOI-B12 <MDA 9 <MDA <MDA <MDA <MDA < MDA <1 <3 222 W01-D14 <MDA 9 <MDA <MDA <MDA <MDA < MDA <2 <3 368 I i
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- Maximum in I square meter Alpha background = 2 dpm/10(km' f Beta background = 1600 dem/100cm' l Gamma background = 9 uR/hr l B-17
f 8 Reactor Building 100 Basement Area 2 9 February 1993 location Gross e Gross Grosa Beta Removable Removable Smear Code alpha Gamma Gross Alpha Gron: Beta # Units = = > (dpnV100em2 ) uR/hr [dpm/100cnfj (dpm/100cm') M D As = = > MDA = 79 MDA = 2900 12 standard deviations WOI-B17 <MDA 10 <MDA <MDA <MDA <MDA <MDA <1 <3 223 WO2 AR <MDA 9 <MDA <MDA <MDA <MDA <MDA <1 <3 224 WO2-C9 <MDA 12 <MDA <MDA <MDA <MDA <MDA <1 <3 225 WO3-A3 <MDA 13 <MDA <MDA <MDA <MDA < MDA <1 <3 228 WO3- A13 <MDA 10 <MDA <MDA <MDA 3500 < MDA <1 312 229 WO3-A17 <MDA 10 <MDA <MDA <MDA <MDA < MDA <1 <3 230 WO3-B5 <MDA 10 <MDA <MDA < MDA 3500 < MDA <1 <3 232 WO3-B18 <MDA 10 < MDA 3200 <MDA <MDA <MDA <l <3 231 l WO3-D1 120 10 <MDA <MDA 3200 <MDA <MDA <1 <3 251 WO3-D9 82 10 <MDA <MDA 3500 <MDA <MDA <2 <3 189 WO3-D15 86 10 <MDA < MDA <MDA <MDA <MDA <1 <3 188 t WO4- Al <MDA 12 <MDA <MDA <MDA <MDA <MDA <1 <3 227 WO5-BI <MDA 10 <MDA <MDA <MDA < MDA < MDA <2 <3 226 WO5-D4 <MDA 12 3500 <MDA < MDA < MDA <MDA <2 <3 369 WO6-A5 <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 192 WO6-B8 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 191 WO7- A10 <MDA 9 <MDA <MDA <MDA <MDA < MDA <1 <3 250 WO7-B3 <MDA 10 <MDA <MDA <MDA < MDA <MDA <2 <3 190 WOR- A9 <MDA 8 <MDA <MDA <MDA <MDA <MDA <2 <3 186 WO8-A13 <MDA M <MDA <MDA <MDA <MDA <MDA <2 <3 187 CO2-A2 <MDA 10 <MDA < MDA <MDA <MDA <MDA <2 <3 193 l C01- Al <MDA 10 <MDA < MDA <MDA <MDA <MDA <2 <3 197 l C03-B2 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 196 l
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- Grms Gross Beta Removable Renwvable Smear Code alpha Ganuna Gross Alpha Gross Beta #
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- Matimum in 1 square meter Background was not subtractedfrom above data.
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- Maximum in i square meter flackgre.und was not subtractedfmm above data. ,
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Reactor Building 100 Basement Area 4 10 February 1993 Location Gross
- Gross Gron Beta Removable Removable Smear Code alpha Gamma Gross Alpha Grosa tieta #
Units = = > [dpm/100cm'] uR/hr [dpm/100cnf] Idpm/100cm'] MDAs= = > MDA = 79 MDA = 2900 12 standard deviationa l l I C01- A6 <MDA 12 <MDA <MDA <MDA <MDA <MDA <2 <3 275 C01-B1 <MDA 9 <MDA 3200 <MDA <MDA <MDA <2 <3 279 WOI Al <MDA 10 3200 <MDA <MDA <MDA < MDA <2 <3 287 WOI-D3 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 280 W01 -B5 <MDA 11 < MDA <MDA <MDA <MDA <MDA <2 <3 290 l W01-A7 <MDA 9 <MDA <MDA <MDA < MDA < MDA <2 <3 291 W01-A14 <MDA 9 <MDA <MDA 3200 <MDA <MDA <2 <3 302 W01-D9 <MDA 9 <MDA <MDA <MDA < MDA < MDA <2 <3 282 W01-B12 <MDA 11 <MDA <MDA < MDA < MDA < MDA <2 <3 303 WOI-Dl6 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 281 W01-A18 <MDA 9 <MDA <MDA <MDA 3200 3500 <2 <3 304 W01-C20 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 283 W01- A22 <MDA 8 <MDA <MDA <MDA 3200 3200 <2 <3 305 WOS-A4 <MDA 11 <MDA <MDA <MDA <MDA < MDA <2 <3 293 WO5-B1 <MDA 10 <MDA <MDA < M DA < MDA 3200 <2 <3 294 WO4-A2 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 301 WO4-C4 <MDA 9 <MDA <MDA <MDA <MDA < MDA <2 <3 286 WO2-A2 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 276 WO2-B7 <MDA 11 <MDA <MDA <MDA <MDA <MDA <2 4+2 277 WO2- A10 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 27K
- Maximum in I square meter Background was not subtractedfrom above data.
Alphs background = 2 dpm/100cm' Beta background = 1600 dpm/l(Xkm' Gamma background = 9 uR/hr l l l l 4 E-31
% e Reactor Building 100 Basement Arca 4 10 February 1993 j Gross' Gross Gross Beta Removable Removable Smear Location Code alpha Gamma Gross Alpha Gross Beta # Units = = > [Jpm/10& nf) uR/hr [dpm/100caf] [dpm/100cm'l MDAs = = > MDA = 79 MDA = 2900 12 standard deviations WO3-A6 <MDA 9 <MDA <MDA < MD A <MDA <MDA <2 <3 284 WO3-B10 <MDA 9 <MDA <MDA < MDA <MDA <MDA <2 <3 285 F01- A l3 <MDA B <MDA <MDA <MDA <MDA <MDA <2 <3 288 F01-C9 <MDA 8 < MDA <MDA <MDA < MDA <MDA <2 <3 289 F01-D7 <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 292 F01-F4 <MDA 10 3200 <MDA 3200 <MDA <MDA <2 <3 309 F01-F12 <MDA 10 <MDA <MDA <MDA <MDA 3900 <2 <3 296 F01-G8 <MDA 9 3200 <MDA 3200 <MDA <MDA <2 <3 300 F01-II6 <MDA 10 < MDA <MDA 3200 3200 <MDA <2 <3 307 F01-illi <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 295 F01-12 < MDA 11 <MDA <MDA <MDA <MDA <MDA <2 <3 308 F01-J13 <MDA 9 <MDA <MDA <MDA < MDA <MDA <2 <3 297 F01-L3 <MDA 9 < MDA <MDA < MDA <MDA <MDA <2 <3 306 F01-L8 <MDA 8 <MDA 3200 <MDA <MDA < MDA <2 <3 299 F01-Ll2 <MDA 8 < M DA <MDA < MDA <MDA <MDA <2 <3 298
- Maximum in i square meter Itackground was not subtractedfrom above data.
Alpha background = 2 dpm/100cm' Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr e l B-32 i
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DATE. - 25 May 93-- l 1 Basement Area 4 DRAWN _.lSB
^"""*'"*- . U.S. ARMY ENVIRONMENTAL HYGIENE AGENCY SCALE ATS - - - -
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Reactor Building 100 Basement Stairwells 1 and 2 10 February 1993 Location Gross
- Gross Gross Beta Removable Removable Smear Code alpha Gamma Gross Alpha Gross Beta #
Units = = > [dpm/100em2 uR/hr {dpm/100cm'l Idem /100cm'l M D As = = > MDA = 79 MDA = 2900 12 standard deviations Stairwell #1 W01-Al <MDA 8 <MDA <MDA <MDA 3200 <MDA <2 <3 311 WOI D3 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 310 W01-C5 <MDA 7 <MDA <MDA <MDA <MDA <MDA <2 <3 312 WOI-E8 120 8 <MDA <MDA <MDA <MDA < MDA <2 <3 313 F01-B12 < MDA 8 <MDA <MDA 3200 3200 <MDA <2 <3 314 F01-A5 140 10 <MDA <MDA < MDA <MDA <MDA <2 <3 315 F01 B2 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 316 WO4-Al <MDA 8 < MDA <MDA < MDA <MDA <MDA <2 <3 317 WO3-D5 <MDA 10 3200 <MDA <MDA <MDA <MDA <2 <3 318 WO3-B7 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 319 WO3- A9 <MDA 10 <MDA <MDA < MDA 3200 3200 <2 <3 320 WO3-C8 <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 321 Stairwell # 2 W01-D4 <MDA 8 <MDA <MDA <MDA <MDA <MDA <2 <3 327 W01-C6 <MDA 10 < MDA <MDA < MDA <MDA <MDA <2 <3 329 W01 E8 <MDA 10 <MDA <MDA 3200 <MDA <MDA <2 <3 332 W01 A9 <MDA 9 <MDA <MDA <MDA <MDA <MDA <2 312 323 WO4-Di <MDA 10 <MDA <MDA < MDA <MDA <MDA <2 <3 331 F01- A2 <MDA 11 3200 <MDA <MDA <MDA <MDA <2 <3 324 F01-88 82 9 <MDA <MDA 3200 <MDA <MDA <2 <3 325 F01 A13 <MDA 9 3200 <MDA <MDA <MDA < MDA <2 <3 326 WO3-E2 <MDA 11 <MDA <MDA <MDA <MDA < MDA <2 <3 330 WO3-Al <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 333 WO3-C5 <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 334 W0l E7 < MDA 9 <MDA <MDA <MDA <MDA <MDA <2 <3 328
- Manimum in I uluare meter Background was not subtractedfrom above data-Alpha background = 2 dpm!!00cnf Beta backgmund = 1600 dem/100cnf Gamma background = 9 uR/hr B-37
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SCALE- __ET -l i UNITED STATES ARMY MEDICAL DEPARTMENT PLATE _ __._ ___.._ ._ 1 B-39
4 * , Reactor Building 100 Basement l Trenches, Equipment llatch, and Airlock i 10 February 1993 Location Gross
- Gross Gross Beta Removable Removable Smear Code alpha Gamma Gross Alpha Gross Beta #
Unita = = > [dpm/100cm2) uR/hr [dpm/100cm2 ) (dpm/100cm'l MDAs = = > MDA = 79 MDA = 2900 f. 2 standard deviation Trenches in Basement floor AR < MDA 8 <MDA <MDA <MDA <MDA <MDA <2 <3 336 A21 <MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 335 H9 < MDA 10 < MDA <MDA <MDA <MDA <MDA <2 <3 337 B3 <MDA 10 <MDA <MDA <MDA <MDA < MDA <2 <3 338 HIS < MDA 11 <MDA < MDA <MDA <MDA <MDA <2 <3 339 ; F3 < MDA 10 <MDA <MDA <MDA <MDA <MDA <2 -<3 340 + Equipment Hatch I W01- Al <MDA 7 <MDA <MDA <MDA <MDA <MDA <2 <3 354 F01-B3 < MDA 11 <MDA 3500 <MDA <MDA <MDA <2 <3 353 ; _F01-Cl <MDA 10 <MDA <MDA <MDA <MDA <MDA <2 < 3' 352 WO3 A3 < MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 355
. WO4-B1 <MDA 7 < MDA < MDA <MDA <MDA <MDA <2 <3 356 l i
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- Maximum in I square meter Background was not subtractedfrom above data.
. Alpha background = 2 dpm/100em' ileta background = 1600 dpm/100cm3 j
Gamma background = 9 uRMr i 1 l 1 l B-40
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U.S. ARMY ENVIRONMENTAL HYGIENE AGENCY i SCALE 9lS UNITED STATES ARMY MEDICAL DEPARTMENT PLATE B-41 l
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U.S. ARMY ENV[RONMENTAL HYGIENE AGENCY
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i s *, ! Reactor Building 100 Basement Airlock 2, Gamma Well, and Basement Sump I1 February 1993 location Gross Gross Gross Beta Removable Rennvable Smear alpha Gamma Gross Alpha Gross Beta # Code Units = = > lopm/100cnfj uR/hr [dpm/100em'] [dpm/100cm'] MD As = = > MDA = 79 MDA = 2900 12 standard deviations Airlock # 2 C01-B2 <MDA 6 <MDA <MDA <MDA <MDA <MDA <2 <3 345 WO4-Al <MDA 5 <MDA < MDA < MDA <MDA <MDA <2 <3 346 F01-El <MDA 5 <MDA <MDA <MDA < MDA < MDA <2 <3 347 WOS-B8 <MDA 5 <MDA <MDA <MDA <1 )A < MDA <2 <3 351 WOS-A5 <MDA 6 <MDA < MDA <MDA < MDA <MDA <2 <3 350 F01-G2 <MDA 5 <MDA < MDA < MDA <MDA <MDA <2 <3 348 F01- Al <MDA 5 <MDA <MDA <MDA <MDA < MDA <2 <3 344 WO3-Al < MDA 5 <MDA <MDA <MDA <MDA <MDA <2 <3 342 WO3-B7 < MDA 6 <MDA <MDA <MDA <MDA <MDA <2 <3 343 WO3-B4 < MDA 6 <MDA < MDA < MDA < MDA <MDA <2 <3 349 Basement Gamma Well W01-A5 <MDA 10 <MDA < MDA < MDA 4200 <MDA <2 <3 372 WO2-D1 <MDA 10 <MDA < MDA <MDA < MDA < MDA <2 <3 373 WO2-A5 <MDA 9 <MDA <MDA <MDA <MDA < MDA <2 <3 376 WO2-E7 <MDA LO <MDA < MDA <MDA < MDA 3200 <2 <3 371 WO2-B3 <MDA i1 <MDA < MDA 3200 3200 < MDA <2 <3 377 WO2-E4 < MDA 10 <MDA <MDA <MDA <MDA <MDA <2 <3 370 Basement Sump Top Rim <MDA 12 < MDA <2 <3 378 1 Meter down <MDA 12 <MDA <2 <3 379 15 feet down <MDA 13 < MDA <2 <3 380
' Maximum in i square meter BacLground was not subtractedfrom above data.
Alpha background = 2 dpm/100cn/ Beta background = 1600 dpm/100cm' Gamma background = 9 uR/hr B-44 :
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