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GENERAL DYNAMI' ',
, Land Systems Division i ! !
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! : i ! - RADIOLOGICAL SURVEY REPORT : FOR SITE CLOSURE '
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i : DETROIT ARSENAL TANK PLANT (DATP) i BUILDING 4 i
28251 VAN DYKE : i ' WARREN, MICHIGAN 48090 i ; ! ; i
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, . REFERENCE: t U.S. NUCLEAR REGULATORY COMMISSION (NRC) ;
. RADIOACTIVE MATERIALS LICENSE ' i No. 21-21068-01, Amendment No.10
; Docket No. 030-19731 i 9703120167 970305 PDR ADOCK 03019731 , C PDR
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I- EXECUTIVE SUMMARY ;
, Declining tank production rates and lower defense spending caused the 1995 Base ' Realignment Closure Commission to recommend that the Detroit Arsenal Tank Plant i
, (DATP), a Government Owned Contractor Operated (GOCO) facility, be shut down. For I the years that General Dynamics Land Systems (GDLS) has produced tank systems at DATP (since 1982), tank production operations were specific to Building 4 of the plant, Bays K & L. Extensive radiological wipe testing was conducted in these areas in an I effort to quantify any removable radiological contamination that may have been present as a result of GDLS's use of sealed tritium (H-3) sources in the tank's fire control system; ! specifically the Muzzle Reference Sensor (MRS). Results by liquid scintillation analysis 4 indicate a level of removable tritium contamination much lower than (by a factor of | approximately ten (10)) the NRC's unrestricted release limit (1000 disintegrations per ' minute (dpm) per 100 cm2 ). ' Four (4) areas showed levels of removable contamination near or at the Department of the Army's release limit (100 dpm/100 cm'). These areas , were decontaminated to "no detectable activity" (NDA). No other radiological contaminants were observed. Contingent on the review and approval of this report by the Nuclear Regulatory Commission (NRC), DATP's Building 4 will be released to the
; Department of the Army (DoA) for unrestricted use.
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; TABLE OF CONTENTS
3 SECTION 3 TITLE PAGE
; 1.0 BACKGROUND 1 2.0 1 RADIOACTIVE MATERIAL 3 | 2.1 NUCLEAR REGULATORY COMMISSION (NRC) LICENSING 3 2.2 DEPARTMENT of the ARMY (DoA) PERMIT AUTHORIZATION 3 3.0 PRELIMINARY ANALYSIS 5 3.1 RADIOLOGICAL SURVEYS - GRID DEVELOPMENT 5 ; 3.2 - ESTABLISHING SITE BACKGROUND LEVELS S 1 { 3.3 TRITIUM (H-3) CONTAMINATION EVALUATION 6 i ' 3.3.1 BAYS K & L 6 |
3.3.0. OTHER POTENTIAL AREAS OF H-3 CONTAMINATION 6
: 3.4 i THORIUM / DEPLETED URANIUM CONTAMINATION EVALUATION 7
3.5 RADIOLOGICAL INSTRUMENTATION 8 ;
3.5.1 LIQUID SCINTILLATION METHOD 8
| 4.0 PRELIMINARY RESULTS 9
4.1 TRITIUM CONTAMINATION 9 : ; 4.1.1 CONFIDENCE LEVEL of the SURVEY 9
! 4.2 THORIUM / DEPLETED URANIUM CONTAMINATION 10 ' 4.3 ARMY REGULATION AR385-11 11
; 5.0 CHARACTERIZATION ANALYSIS 12
; 6.0 FINAL ANALYSIS 13
4 6.1 DECONTAMINATION EFFORTS 13 .
, 6.2 FINAL SURVEY 13
, 7.0 CONCLUSIONS 14
8.0 RECORD MAINTENANCE 15
9.0 REFERENCES 16 i
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I TAI 3LE OF FIGURES '
FIGURE TITLE PAGE
1 STANDARD SAMPLING PATTERN FOR GRID SURVEY OF FLOOR 6 2 CHARACTERIZATION SURVEY TECHNIQUE 12
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TABLE OF TABLES
TABLE TITLE PAGE
1 TRITIUM / THORIUM / DEPLETED URANIUM DECAY : p' EMISSIONS 7
TABLE OF APPENDICES
APPENDIX TITLE PAGE
I DATP BAYS K & L SAMPLING GRID 17
II PRELIMINARY SURVEY DATA 18
III H-3 CONTAMINATION DETECTED vs. " UNRESTRICTED USE" LIMIT 19
IV LIQUID SCINTILLATION GENERATED DATA 20
V H-3 CONTAMINATION DETECTED vs. DoA "AR385-11" LIMIT 21
VI CHARACTERIZATION SURVEY DATA 22
VII FINAL SURVEY DATA 23
VIII DEPARTMENT of the ARMY PERMIT AUTHORIZATION 24
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| 1.0 BACKGROUND .
: During World War II, specifically the summer of 1940, the Nazi offensive relentlessly j pushed the allies from the European continent. As a result of this, the War Department, known today as the Department of Defense (DoD), began to address large scale [ production of all types of weapons, including thousands of tanks. It became apparent that 2 the growing demand of high volume tank production would require a new plant specifically designed and equipped to build tanks.
In September -1940,'the construction of the Detroit Arsenal Tank Plant (DATP) in i Warren, Michigan began. By late summer 1941, the construction of the plant had been ' ' completed. When DATP actually opened, the United States government issued a contract ! to Chrysler Corporation to build 1,400 M3 Grant tanks. During World War II (from 1941 . through 1945), a total of 22,234 tanks were produced at DATP.
: ? From 1946 through 1951, the DATP became a tank development and modification center operated by.the government. During this period it produced prototype systems, modified and remanufactured existing tanks, and conducted an extensive M46 tank conversion program. During this five (5) year period, DATP was the United States' only active tank manufacturing facility. In 1955, new tank production was temporarily ceased at the plant.
From 1956 through 1960, DATP supported various tank production facilities (i.e. American Locomotive, GM Fisher Body, Ford Motor Company, and the Delaware Tank Plant) with machined component parts. In 1960, with the introduction of the M60 tank, | DATP again became the United States' only active main battle tank producing facility, a , position retained for the next twenty (20) years. Production of the M60 series tank was ' concluded in 1987.
In addition to the accelerated production effons at DATP in 1973, manufacturing of the XM1 prototype tank was initiated. The XM1 was a totally new, next generation tank with a 1500 hp gas turbine engine and improved armor protection, stuvivability, speed, and mobility. In order to successfully meet new contractual requirements, several commodities were integrated into the Abrams which utilized radioactive material, both exempt and licensable quantities. These commodities included the Muzzle Reference Sensor (MRS) (tritium), optical coatings in the thermal imaging system (Thorium Fluoride), the combustor liner assembly in the turbine engine (Nickel Thoria), and eventually the incorporation of depleted uranium armor. Section 2.0 (Radioactive Material) provides tne specific details surrounding the types and uses of these materials.
Prior to actual production of the M1 Abrams tank at DATP, machining of M1 Abrams component parts began here in 1979, with the first delivery to the Lima Army Tank Plant '(LATP) in the spring of that year. In October 1981, assembly of the M1 Abrams tank began at the DATP. By.1982, Chrysler Corporation's Tank Production Division was purchased by General Dynamics. Furthermore, in March of that year, the first two (2) "DATP produced" M1 Abrams tanks were delivered to the United States Army, in
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h 1.0 3 BACKGROUND (continued) '
August 1985, DATP delivered the first production M1 A1 Abrams tank. This tank system I i ! ' was an evolutionary product improvement of the original M1 Abrams tank. Significant changes included a 120 mm smooth bore cannon system, a nuclear biological chemical 4 (NBC) crew protection system, and improved armor. The last MI Al Abrams built at the I DATP was delivered to the U.S. Army in September 1991.
, Following the last M1 A1 delivered from the DATP in 1991, the plant continued M1A1 | component parts machining. Shortly thereafter, Ml A2 component parts machining was 3 added to the plant's responsibilities. From December 1993 through September 1996, ' DATP also served as a modification center for Abrams tanks sold to the Kingdom of i Saudi Arabia and Government of Kuwait. <
. Despite decades of successful operation, the combination of declining tank production rates and lower defense spending over recent years caused the 1995 Base Realignment i and Closure Commission to recommend that the DATP be shut down. In December j 1996, General Dynamics Land Systems phased out its manufacturing operations at the J DATP. By mid January 1997, all remaining General Dynamics produced Abrams Tank ' Systems located at DATP were taken possession of by the Department of the Army.
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2.0 RADIOACTIVE MATERIAL
2.1 Nuclear Regulatory Commission (NRC) Licensing | | i With the evolution of the M60 into the XM1, came the incorporation of the Muzzle I Reference Sensor (MRS) into the tank's fire control system. This unit is installed on the ! main weapon of the Abrams tank system. The purpose of the MRS is to provide the tank's gunner with a means for correcting fire control solutions to compensate for gun tube bend caused by the uneven heating and cooling effects of solar radiation, wind, rain, and main gun firing. The MRS system permits bore sight correction whenever the gunner | suspects gun tube movement and he aligns the primary sight reticle with the muzzle l mounted MRS reticle. The gunner enters necessary changes semi-automatically into the vehicle's fire control ballistic computer. Originally, each MRS contained a sealed source , filled with seven (7) Curies (Ci) of a high purity tritium gas encapsulated under 40 psi | pressure. As optical improvements became necessary over the years, a 10 Ci tritium source was required. The interaction of the F emissions from the tritium gas and the phosphor coated glass capsule which contains it, provides illumination of the MRS l collimator reticle with the Gunner's Primary Sight (GPS) reticle (aiming reticle) during periods of no or low light conditions.
When tank production operations were sold in 1982 by Chrysler Corporation (NRC Radioactive Materials License No. 21-00644-03) to General Dynamics, radioactive ]. material related activities were continued by General Dynamics under Nuclear ^ Regulatory Commission (NRC) Radioactive Materials License No. 21-21068-01. These activities included the receipt, use, storage, installation, and transfer of MRS systems at the DATP. The actual addresr, of the DATP, as authorized by the GDLS NRC license, is:
Land Systems Division Detroit Arsenal Tank Plant 28251 Van Dyke Warren, Michigan 48090
Although General Dynamics' license (21-21068-01) also authorizes the use of Nickel-63, Krypton-85, and Americium-241, these radioactive materials were not used or stored at DATP.
2.2 Department of the Army (DoA) Permit Authorization
Since the Detroit Arsenal Tank Plant (DATP) is a Government Owned Contractor Operated (GOCO) facility, in order for General Dynamics to conduct activities involving radioactive material at this plant, a Department of the Army (DoA) Permit Authorization for Possession and Use of Radioactive Afaterials was required. The contents of the permit application are very similar to the application requirements for a NRC license. This includes information regarding the type and quantity of radioactive material to be
3 2.2 - Department of the Army (DoA) Permit Authorization (continued)
possessed and used, its intended use, individuals responsible for its safe handling and use, their training, radiation detection instruments to be utilized and the applicable calibration frequencies / procedures, personnel monitoring requirements, and a detailed description of the Radiation Safety Program to be implemented at the plant. Currently, General Dynamics operates at the Detroit Arsenal Tank Plant under DoA Permit No. P21-21- 21068-01, Amendment 01; expiration 31 January 2000 (Reference Appendix VIII). GDLS's tank production operations have been specific to DATP's Building 4, Bays K & # L.
The DoA permit not only authorizes the possession and use of "NRC licensable quantities" of radioactive material (specifically H-3), but also " exempt quantities" of radioactive material as well. Exempt quantities include 56.34 nCi per unit of Thorium ~32 as an anti-rellective optical coating on thermal imaging lenses, and 0.002 pCi per gram of Thorium 232 as a thorium dioxide in magnesium / nickel alloy for the Abrams turbine engine combustor liner (this quantity constitutes not more than 4 percent by weight of each unit). Additiona ly,l this permit also authorizes GDLS to possess, use, and transfer M1A2 Abrams tank systems which contain Depleted Uranium (DU) armor shielding. A separate NRC license for the DU armor is also held by General Dynamics (Reference NRC License No. SUB-1564).
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, 3.0 PRELIMINARY ANALYSIS
3.1 Radiciogical Surveys - Grid Development
On October 03,1996, General Dynamics was issued Amendment No.10 to NRC License No. 21-21068-01, This amendment authorized General Dynamics to " release to
, unrestricted use" the Warren Logistic Center (WLC) facility located at 6700 East 14 Mile Road, Warren, Michigan. This was based on close-out surveys and sealed source wipe test data that had been submitted to the NRC in support of the amendment request.
J During decommissioning of the WLC facility, sixteen (16) wipe samples were taken from the Validation / Verification floor area (14,060 ft2 ). This equated to one (1) wipe sample per 878 ft2 of floor area, or I wipe sample per (29.6 ft. x 29.6 ft. area). Based on the NRC's review and approval of this method of sampling in the WLC Decommissioning Report, a similar approach was taken for Bays K & L of DATP. These bays, which represented the most probable areas (throughout the plant) to exhibit any removable contamination, were sectioned offinto grid areas each measuring 29 ft. x 29 ft. of floor space. Bays K & L were sectioned into 381 " sample areas" (Reference Appendix I).
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; Furthermore, the approach that was taken in " sectioning" Bays K & L seemed most ; appropriate since General Dynamics' operations at DATP (as with WLC) only involved '
sealed sources in pre-manufactured tank components, and the amounts and levels of i radioactive material used at DATP declined considerably since production halted in 1991. i Hence, the potential for radiological contamination at the DATP was estimated to be minimal.
* A statisticaljustification of the quantity of measurements taken and the nonessential need
for additional sampling can be found in Section 4.1.1. j
3.2 Establishing Site Background Levels i
NRC guideline values for residual activity are levels above the naturally occurring background levels. Therefore, it was necessary to determine the site background levels of direct radiation to enable a comparison of DATP radiological conditions with the acceptable guideline values, both NRC and DoA.
- Ten (10) measurements were randomly taken throughout the entire plant. These measurements were taken in areas in which licensed activities had not been authorized, nor conducted (Reference Appendix II, samples 391 - 400). Samples were collected and analyzed by liquid scintillation technique. It was determined that the " unaffected area" ' surface radiation level (H-3) ranged from 0 - 32 dpm/100 cm2 ; or 4.7 dpm/100 cm2 , average. This value can be compared with the contamination detected throughout the plant in order to quantify the " net residual surface contamination" at DATP due to NRC licensed operations. 4
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3.3 Tritium (H-3) Contamination Evaluation
3.3.1 Bays K & L
, With the use of a measuring wheel (Measure Master, Model MM30, Rolatape Corp.), Bays K & L were subdivided into 381 sections of floor area, each approximately 29 ft. x 29 ft.. Applying moderate finger pressure, dry wipe samples were taken over a 200 cm2 area at the center of each grid square (Figure 1). Sampling was accomplished using i Whatman Filter Paper, Qualitative Circles,42.5 mm O.
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: Figure 1. Standard Sampling Pattern for Grid Survey of Floor
; 3.3.2 Other Potential Areas ofH-3 Contamination |
In addition to the sampling done in Bays K & L, samples were also taken in areas where ) 1 tritium-contained Muzzle Reference Sensors were temporarily located during plant ) operations, or in areas where there existed a potential for contamination, regardless of ' { how minimal. These areas were primarily Receiving, the General Dynamics Quality and ' ' Logistics Offices, the General Dynamics Safety Office, and the "old" Safety Crib storage area. Samples were taken at well defined locations and are identified on the data sheets provided in Appendix II (samples 382 - 390). Specific details of these sampling locations are described below.
; Samples 382 - 384. Samples were taken from the "old" Safety Crib - MRS storage area located near upright 13E. From the upright closest to the area's fence (unmarked), measurements were taken , inline and at 6 ft.,12 ft., and 18 ft. north of the upright. s Samnie 385. Safety Office, North-Central area of the plant, second floor, third door in. Sample taken from the center of the floor area.
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3.3.2 Other Potential Areas ofH-3 Contamination (continued)
Sample 386. Safety Office North-Central area of the plant, second floor, second door in, rear room. i- Sample taken from the center of the floor area.
Samnie 387. Receiving area, Upright "29 D - E". Sample taken adjacent to the east side of the upright. l Sample 388 - 389. 4 Quality Offices, Bay L-9, second floor. Samples taken at the center of the floor (width), 15 ft. and 29 ft. east of the entrance wall.
; Sample 390. Logistics Office, Bay L-10, second floor. Sample taken from the center of the floor area.
! 3.4 Thorium / Depleted Uranium Contamination Evaluation
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; Because the Abrams Tank System also incorporates depleted uranium armor (completely enclosed) and commodities containing exempt quantities of thorium (Reference paragraph 2.1), a verification of the lack of residual contamination of these isotopes was ' I also addressed. Table 1 illustrates the primary p emissions resulting from the decay of ; ; each isotope and the channel of the liquid scintillation counter in which contamination, if ! present, would be displayed, l l PARENT p~ EMITTING MAXIMUM % p- LSC | NUCLIDE RADIONUCLIDE FENERGY. INTENSITY CHANNEL MeV | tritium (H - 3) 0.0186 100 A I
Thorium - 232 Radium - 228 0.055 100 B (Mesothorium I)
Actinium - 228 1.18 35 C (Mesothorium II) 1.75 12 C 2.09 12 C
Uranium - 238 Protactinium - 234m 2.29 98 C
Thorium - 234 0.103 21 B 0.193 79 B/C
Table 1. Tritium / Thorium / Depleted Uranium Decay : p Emissions
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3.5 RadiologicalInstrumentation
All radiological wipe samples collected at the DATP were analyzed by Wayne State i University (WSU) - Health Physics, Detroit, Michigan (NRC License No. 21-00741-08), utilizing liquid scintillation technique. The following outlines the procedures utilized in the analysis of these samples.
3.5.1 LiquidScintillation Method
Wipe samples collected by the General Dynamics Radiation Safety Office were individually placed in 20 ml plastic vials prior to their transfer to WSU - Health Physics for analysis.
Upon receipt at WSU, vials were filled with 10 ml of RPI 3a20 Complete Scintillation - Cocktail, capped, shaken, wiped, and then placed in a TM Analytic 5303 Mark V Liquid Scintillation Counter and dark adapted for 1.5 - 2 hours. I The Liquid Scintillation Counter has " set" window channels for sample analysis as follows:
Channel A : 1 - 19 kev (H3 channel)
' Channel B : 20 - 168 kev ChannelC : 169 - 2000 kev
Samples were counted for 10 minutes each with'a one minute low count reject setting. Results for each channel are printed in counts per minute (cpm). The following equation was then utilized to calculate net disintegrations per minute (dpm).
NET DPM = NET CPM % eff.
where NET CPM = sample CPM - background CPM, and % eff. is the percent detection efficiency for the respective isotope being analyzed for.
Aqueous Quenched and Unquenched standards have been obtained by WSU from Dupont - NEN and are used for detection efficiency determination. In addition, WSU's system is calibrated in accordance with their respective NRC license provisions.
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4 4.0 PRELIMINARY RESULTS
4.1 Tritium Contamination
! Preliminary radiological wipe test renit', indicate that the level of removable tritium contamination present throughout the Detroit Arsenal Tank Plant is below the maximum ; permissible quantity of removable p' contamination allowable for " release to unrestricted i use" (1000 dpm/100 cm-) by a factor of approximately ten (10). The maximum quantity of removable tritium contamination detected at DATP was 100.5 dpm/100 cm (Reference sunple 351). A graphic representation of the contamination detected in 1 ' 4 DATP's Bays K and L, as compared to the NRC's maximum permissible limit of removable contamination, is provided in Appendix Ill.
4.1.1 Confidence Levelof the Survey 2
(The following statistical evaluation was prepared in accordance with NUREG/CR-5849, Manualfor Conducting RadiologicalSurveys in Supporting License Termination.)
3 In accordance with Paragraph 8.5 of the aforementioned manual, the limit for removable activity is 20% of the guideline value for total surface activity. In the case of p' emitters, j the NRC guideline limit for removable contamination (for release to unrestricted use) is 1000 dpm/100 cm2 . Hence, the " remedial action limit" would correspond to 200 2 ; dpm/100 cm , . f According to the manual, the Enviromnental Protection Agency (EPA) (EPA 1989) recommends the use of the following equation for testing data, relative to a guideline value, at a desired level of confidence,
pa = X+ta.dr*{6-}i n"
where: t a.ori is the 95% confidence level obtained from NUREG/CR-5849, Appendix B, Table B-1: df(degrees of freedom) is (n-1), X is the calculated mean, 6, is the standard deviation,
n is the number ofindividual data points used to determine X and 6x .
Once calculated, the value of p is compared to our guideline value (200 dpm/100 cm2 ), If p is less than the guideline value, it is suggested that the area being tested meets the guideline at a 95% confidence level, and no further remediation/ resurvey is required.
9 4.1.1 Confidence Levelof the Survey (continued)
To demonstrate compliance at the 95% confidence level, po was based on all data points acquired in surveying Bays K & L (381 sample points). From the data provided in Appendix II, the following was determined.
Samples, n 381 Mean, X 3.761 dpm/100 cm2
Standard Deviation,6x 8.373 dpm/100 cm2
Additionally, Degrees of Freedom 380 tva, (extrapolated) 1.65
Inserting these values into the above expression results in
po = 4.47 dpm/100 cm2
In comparing this value with the guideline value, it is evident that
4.47 dpm/100 cm2 << 200 dpm/100 cm2
This indicates that the data obtained from the evaluation of Bays K & L satisfies the ! guideline at a 95% confidence level. Hence, no additional sampling is required to demonstrate overall compliance.
4.2 Thorium / Depleted Uranium Contamination
In evaluating the computer generated reports from the liquid scintillation analysis (Appendix IV), specifically the outputs from Channels B and C, it is apparent that no contamination much above background was detected. It can therefore be concluded that neither thorium or depleted uranium contamination is present in those areas in Bays K and L that were surveyed. Because these areas were the most probable areas for the presence of any radiological contamination (due to the routine, daily activities performed in and limited to these areas), it can also be reasonably concluded that the presence of these contaminants does not exist throughout DATP's Building 4. No further action is required.
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4.3 Army Regulation AR385-11
Because the Detroit Arsenal Tank Plant is a Government Owned Contractor Operated I (GOCO) facility, General Dynamics is considered to be " operating on Army Land", and therefore, various Army Regulations apply to the everyday opemticas conducted within the plant. Army Regulation AR385-1l, "lonizing 'Radicsion Protection (Licensing, Control, Transportation, Disposal, and Radiation Safety)", specifically addresses the use and handling of radioactive materials at Department of tho Army agencies, commands, and installations. Within this regulation are specif.c radioactive contamination guidelines. According to this regulation (Table 4-3), d<, contamination of uncontrolled work areas is required if Beta-gamma removable coriamination is in excess of 100 2 dpm/100 cm . Results obtained from the preliminar,, survey of Bays K and L indicate that the area identified as 351 is in excess of this limit. Additionally, three (3) other areas (samples 169,200, and 254) were identified as having removable contamination >50 2 dpm/100 cm . A graphic representation of the contamination detected in DATP's Bays K and L, as compared to the DoA's maximum permissible limit of removable contamination,is provided in Appendix V. i
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5.0 CHARACTERIZATION ANALYSIS
A characterization survey of the four (4) areas described in the Section 4.3 of this report was conducted to more precisely define the extent and magnitude of the removable tritium contamination observed in excess of the Army's release limit. As illustrated in Figure 2, twelve (12) measurements were taken in each of the four (4) applicable grid areas.
29 ft. 12 : : 9 3.. .9
9.8 , O'S a d i h' 29 ft. .30,,..:'g' .e3.. [ / '3$ 79' SS,
/ g.- .,. i1 g Areas of Sampling 10
A Figure 2. Characterization Survey Technique '
Samples 1 - 4 were taken one (1) ft. off-center (point of preliminary measurement). Samples 5 - 8 were taken ten (10) ft. diagonally off-center. Samples 9 - 12 were taken at the boundary corners of the predefined grid area. Characterization samples Al - A12 were taken at the grid area identified by preliminary measurement 169. Similarly, samples B1 - B12, C1 - Cl2, and D1 - D12 correspond to the grid areas identified by preliminary measurements 200,254, and 351, respectively. All samples were taken over a 200 cm2 area.
Samples were again analyzed by WSU utilizing liquid scintillation technique. The results obtained from the characterization survey are provided as Appendix VI. A copy of the computer-generated LSC printout has also been provided. Evaluation of the results indicates that the tritium contamination that had been detected during the preliminary survey tends to be localized around the center of each of the four (4) grid areas, and not spread out over each section's 841 2ft floor area. No significant activity (4.4 dpm/100 2 cm , maximum) was detected at any of the 12 sites surveyed. Contamination appears limited to the area immediately surrounding the point of preliminary measurement.
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6.0 FINAL A.NALYSIS
6.1 Decontamination Efforts
Decontamination efforts were accomplished at sites 169, 200, 254, and 351 utilizing RAD-CON Surface Decontaminant. Based on the results of the characterization survey, 2 decontamination was limited to 4 ft of floor area surrounding the four (4) central points of . preliminary measurement. The small amount of waste generated from decontamination activities (primarily paper toweling saturated with decontaminant) is currently being maintained as low-level radioactive waste (llrw) by Wayne State University - Health Physics. The quantity of waste that was collected as a result of these efforts has been estimated at 0.0046 Ci H-3.
6.2 Final Survey
Following the completion of decontamination activities at sites 169,200,254, and 351, radiological wipes were respectively taken over a 200 cm 2area at each of these locations. This was done to demonstrate the effectiveness of decontamination, and to ultimately verify the absence of contamination at these sites. Results from liquid scintillation analysis indicate that no detectable activity (NDA) is present. These results are provided in Appendix VII.
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t 13 , 7.0 CONCLUSIONS
' Radiological survey results obtained during the decommissioning of the Detroit Arsenal Tank Plant (DATP) show that although detectable levels of removable tritium contamination were identified in various locations throughout Bays K and L of Building 4, the levels were well below that which is allowed for unrestricted use of the facility (NRC,1000 dpm/100 cm 2) by a factor of almost ten (10). -;
Areas which exhibited low levels of tritium contamination that were in excess of the Department of the Army's requirement (100 dpm/100 cm ),2 were decontaminated appropriately and resurveyed to verify the absence ofcontamination. No further action is required.
Although samples were not specifically analyzed for thorium or depleted uranium contamination, evaluation of the liquid scintillation counter's various energy charutels' (. output indicates the absence of these isotopes in any measurable quantity.
- It should also be noted that GDLS's NRC Radioactive Materials License authorizes the possession and use of Chemical Agent Detector's containing Nickel-63 and/or Americium-241. Neither material was ever possessed or used at the DATP by General Dynamics. Therefore, it was not necessary to verify the presence / absence of these radioactive materials within the boundaries of the plant.
' Therefore, at the time of NRC review and approval of this report, the DATP will be released to unrestricted use to the Department of the Army.
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8.0 RECORD MAINTENANCE
All applicable records for this effort will be maintained by the General Dynamics Land Systems (GDLS) Radiation Safety Office and made available for review (upon request) during future NRC inspections.
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' ~ h"r-tLa . (/ y - Dennise Stallsrh a Concurrence: J. ost, Jr. GDLS Radiation Safety Officer ML ager, Systems Engineering
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d ! 9.0 REFERENCES i
' The following references were used in the preparation of this report:
1. General Dynamics Land Systems' (GDLS) Nuclear Regulatory Commission (NRC) Radioactive Materials License No. 21-21068-01, Amendment 10; expiration date 31 ; March 2005, ;
, 2. ' General ~ Dynamics Land Systems' (GDLS) Department of the Army (DoA) . Authority for Possession and Use of Radioactive Materials, No. P21-21-21068-01, i Amendment 01; expiration date 31 January 2000. ! ' - 3. Radiological Survey Report for Site Closure - General Dynamics Land Systems - (GDLS) Warren Logistics Center (WLC). June 1996. D.G. Stalismith. : '' . 4. Manual for Conducting Radiological Surveys in Support of License Termination. [ NUREG/CR-5849. June 1992. NRC. ; 5. Army. Regulation No. AR385-11, Ionizing Radiation Protection (Licensing, . . Control, Transportation, Disposal, and Radiation Safety). May 1980. I
6. Radiological Health Handbook. Revised Edition. U.S. Department of Health, Education, and Welfare; Bureau of Radiological Health.
7. Technical Basis for Beta Skin Dose Calculations at the Oak Ridge Y-12 Plant. March 1994. Y/DQ-51. Martin Marietta. J.M. Thomas, R.S. Bogard. i
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| , APPENDIX I | | DATP BAYS K & L SAMPLING GRID
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APPENDIX II
PRELIMINARY SURVEY DATA
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18
! . . - . .. ._ . - -- _-_ _ _ _ _ - . - . _. . - d
D:troit Arsinal Tank Plant (DATP) Decommissioning Activity 1 Preliminary Survey
LOCATION i COORDINATES SAMPLE DATE I AREA cm' I dpm dpm/100 cm' 'JMIT (*/100 cm')
1 14.5W,14.5N 12.12.96 200 9.0 , 4.5 i 1000
2 43.5W,14.5N 12.12.96 ! 200 0.0 i 0.0 ! 1000 3 72.5W,14.5N 12.12.96 i 200 5.0 2.5 1000 4 101.5W,14.5N 12.12.96 200 0.0 0.0 1000
130.5W,14.5N < 5 12.12.96 200 0.0 i 0.0 [ 1000 i 6 159.5W,14.5N 12 12.96 200 i 4.0 i 2.0 , 1000 ,
_ 7 188.5W,14.5N | 12.12.96 i 200 9.0 4.5 ! 1000
< 8 217.5W,14.5N 12.12.96 | ; ; ~ 200 7.0 3.5 1000
9 246.5W,14.5N 12.12.96 200 0.0 i 0.0 4 1000
10 275.5W,14.5N 12.12.96 200 t 14.0 ! 7.0 i 1000
11 304.5W,14.5N 12.12.96 | 200 ! 0.0 1 0.0 | 1000 : 12 333.5W,14.5N 12.12.96 l 200 1 0.0 0.0 i , | 1000 l 13 362.5W,14.5N 12.12.96 { 200 0.0 1 0.0 1000 | - ; l '391.SW, '14 SN , 14 12.12.96 200 2.0 1.0 , 1000
15 420.5W,14.5N 12.12.96 200 0.0 i 0.0 1000 1 16 449.5W,14.5N 12.12.96 200 4.0 2.0 1000 ! 17 478.5W,14.5N 12.12.96 ! 200 12.0 i 6.0 1000 18 507.5W,14.5N 12.12.96 7 200 4.0 2.0 , 1000 | 536.5W,14.5N 19 12.12.96 | 200 0.0 0.0 i 1000 ; | 20 565.5W,14.5N , 12.12.96 i 200 12.0 | 6.0 ! 1000 ; j 21 594.5W,14.5N 12.12.96 ! 200 i 12.0 | 6.0 1000 623.5W,14.5N 22 12.12.96 1 200 0.0 i 0.0 | 1000 " i 23 652.5W,14.5N ! 12.12.96 | 200 0.0 { 0.0 | 1000 24 681.5W,14.5N < 12.12.96 ! 200 1 7.0 l 3.5 ! 1000 ' 25 710.5W,14.5N 12.12.96 200 t 0.0 . 0.0 i 1000 " 1 26 739.5W,14.5N_ 12.12.96 j 200 , 5.0 2.5 l 1000 27 768.5W,1/ 4 12.12.96 1 200 i 0.0 0.0 | 1000 ' 28 797.5W,1% . sN 12.12.96 1 200 O.0 ! 0.0 i 1000 826.5W,14.5N i ) 29 12.12.96 200 0.0 ; 0.0 1000 30 855.5W,14.5N ! 12.12.96 l 200 23.0 11.5 i 1000 31 884.5W,14.5N 12.12.96 200 2.0 | 1.0 ; 1000 j 32 899.0W,14.5N 12.12.96 , 200 0.0 | 0.0 , 1000
; 33 , 928.0W,14.5N 12.12.96 ; 200 1 0.0 ; 0.0 i 1000 ~ ' 34 942.5W,14.5N 12.12.96 200 O.0 i 0.0 i 1000
35 971.5W,14.5N 12.12.96 , 200 { 27.0 I 13.5 1000 36 1000.5W,14.5N 12.12.96 200 ! 4.0 i 2.0 1000 37 1029.5W,14.5N 12.12.96 200 14.0 ! 7.0 ! 1000
' ' ' 38 1058.5W,14.5N 12.12.96 200 2.0 1 1.0 1000 ' 39 1087.5W,14.5N 12.12.96 ! 200 7.0 , 3.5 1000 ' 40 1116.5W,14.5N 12.12.96 200 ; 5.0 2.5 1000
' 41 1145.5W,14.5N 12.12.96 , 200 ! 16.0 8.0 i 1000
- 42 1174.5W,14.5N 12.12.96 200 ! 19.0 ! 9.5 1 1000 i 43 1203.5W,14.5N 12.12.96 200 0.0 i 0.0 ! 1000 ' 44 1232.5W,14.5N 12.12.96 200 9.0 i 4.5 i 1000
' < 45 1261.5W,14.5N 12.12.96 200 19.0 9.5 ! 1000 46 1290.5W,14.5N 12.12.96 200 0.0 0.0 | 1000
Appendix il - 1 (
Dstroit Arstnal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
LOCATION + COORDINATES SAMPLE DATE AREA cm' dpm , dpm/100 cra' LIMIT (*/100 cm') 47 1319.5W,14.5N 12.12.96 200 5.0 i 2.5 1000 48 1348.5W,14.5N 12.12.96 200 4.0 2.0 1000 49 1377.5W,14.5N 12.12.96 200 27.0 | 13.5 i 1000 50 1406.5W,14.5N 12.12.96 200 0.0 0.0 ! 1000
51 1435.5W,14.5N ! 12.12.96 200 0.0 0.0 1000 | 52 1464.5W,14.5N 12.12.96 200 0.0 i 0.0 1000 53 1493.5W,14.5N 12.12.96 200 0.0 | 0.0 1000 l 54 1522.5W,14.5N ' 12.12.96 200 0.0 i 0.0 1000 55 1551.5W,14.5N 12.12.96 200 0.0 s 0.0 1000 56 1580.5W,14.5N 12.12.96 200 0.0 i 0.0 ! 1000 57 1609.5W,14.5N 12.12.96 200 0.0 | 0.0 j 1000 58 1638.5W,14.5N 12.12.96 200 0.0 0.0 , 1000 59 1667.5W,14.5N 12.12.96 200 0.0 ! 0.0 , 1000 60 1696.5W,14.5N 12.12.96 200 5.0 i 2.5 1000 1725.5W,14.5N _ 61 12.12.96 200 14.0 i 7.0 1000 62 1754.5W.14.5N 12.12.96 200 4.0 2.0 i 1000 63 1783.5W,14.5N 12.12.96 200 + 9.0 4.5 1000 | i 64 1812.5W,14.5N ' 12.12.96 200 0.0 | 0.0 1000 ; 65 14.5W, 43.5N 12.12.96 200 0.0 ! 0.0 i 1000 66 43.5W, 43.5N 12.12.96 200 2.0 ; 1.0 1 1000 67 72.5W, 43.5N 12.12.96 200 21.0 | 10.5 i 1000 ; 68 101.5W, 43.5N 12.12.96 200 11.0 | 5.5 ! 1000 1 69 , 130.5W,43.5N ! 12.12.96 200 18.0 9.0 ! 1000 i 159.5W, 43.5N ! 70 12.12.96 200 0.0 | 0.0 i 1000 71 188.5W, 43.5N ; 12.12.96 200 9.0 ! 4.5 ! 1000 72 217.5W,43.5N i 12.12.96 200 0.0 | 0.0 l 1000 l 73 246.5W, 43.5N : 12.12.96 200 11.0 5.5 1000 e 74 i 275.5W, 43.5N i 12.12.96 200 4.0 2.0 1000 75 304.5W, 43.5N 12.12.96 200 16.0 1 8.0 | 1000 76 333.5W,43.5N 12.12.96 200 0.0 ! 0.0 ! 1000 . 77 362.5W, 43.5N I 12.12.96 200 0.0 0.0 t 1000 ! 78 391.5W, 43.5N 12.12.96 200 0.0 ! 0.0 i 1000 ; 79 420.5W,43.5N 12.12.96 200 4.0 | 2.0 : 1000
80 449.5W, 43.5N 12.12.96 200 0.0 ! 0.0 : 1000 81 478.5W, 43.5N i 12.12.96 200 0.0 | 0.0 i 1000 ' 82 507.5W,43.5N 12.12.96 200 14.0 i 7.0 1000
83 536.5W, 43.5N i 12.12.96 200 0.0 i 0.0 i 1000
565.5W, 43.5N > ' 84 12.12.96 200 7.0 | 3.5 1000 ! 85 594.5W, 43.5N < 12.12.96 200 7.0 3.5 1000 ; 86 | 623.5W, 43.5N l 12.12.96 200 2.0 1.0 1000 87 i 652.5W, 43.5N 12.12.96 200 0.0 i 0.0 1000
88 681.5W,43.5N i 12.12.96 200 0.0 0.0 t 1000
; 89 i 710.5W, 43.5N i 12.12.96 200 2.0 1.0 1000 90 739.5W,43.5N i 12.12.96 200 0.0 0.0 1 1000 91 768.5W,43.5N 12.12.96 200 5.0 2.5 < 1000
( 92 797.5W, 43.5N 12.12.96 200 14.0 ! 7.0 i 1000
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Appendix II- 2
._. Detroit Ars:nal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
LOCATION 1 COORDINATES SAMPLE DATE * AREA cm' ' dpm dpm/100 cm' ' UMIT (*/100 cm') 93 826.5W, 43.5N 12.12.96 200 9.0 4.5 1000 94 , 855.5W 43.5N 12.12.96 200 7.0 3.5 ! 1000 95 884.5W, 43.5N 12.12.96 200 0.0 0.0 * 1000 i 96 899.0W, 43.5N 12.12.96 200 0.0 0.0 | 1000 97 942.5W, 43.5N 12.12.96 200 0.0 0.0 i 1000 ' 98 971.5W, 43.5N ~f2.12.96 200 2.0 1.0 I 1000 99 t 1000.5W,43.5N I2.12.96 200 0.0 ! 0.0 i 1000 100 1029.5W, 43.5N f2.12.96 200 0.0 0.0 l 1000 101 1058.5W, 43.5N 12.13.96 200 0.0 0.0 | 1000 102 - 1087.5W,43.5N 12.13.96 200 0.0 4 0.0 i 1000 - 1116.5W, 43.5N ; ' 103 12.13.96 200 11.0 5.5 ! 1000 104 1145.5W, 43.5N 200 0.0 0.0 [12.13.96_ i 1000
6 105 1174.5W, 43.5N 12.13.96 200 0.0 0.0 : _ 1000 106 1203.5W, 43.5N 12.13.96 200 0.0 0.0 ' 1000 107 4 1232.5W, 43.5N 12.13.96 200 0.0 0.0 1000 108 1261.5W, 43.5N "12.13.96 200 0.0 0.0 1000 109 1290.5W, 43.5N ~ 12.13.96 200 0.0 0.0 1000 110 1319.5W, 43.5N 12.13.96 200 5.0 2.5 : 1000 111 1348.5W, 43.5N i2.13.96 200 7.0 i 3.5 i 1000 112 1377.5W, 43.5N 12.13.96 200 , 0.0 0.0 ! 1000 113 1406.5W, 43.5N 12.13.96 200 2.0 i 1.0 1000 114 i 1435.5W, 43.5N 12.13.96 200 11.0 i 5.5 ! 1000 115 i 1464.5W, 43.5N 12.13.96 200 0.0 0.0 | 1000 116 i 1493.5W,43.5N 12.13.96 200 0.0 ! 0.0 i 1000 i 117 1522.5W,43.5N 12.13.96 200 0.0 0.0 | 1000 118 i i 1551.5W,43.5N 12.13.96 200 0.0 0.0 i 1000 119 i 1580.5W, 43.5N 12.13.96 200 2.0 1.0 i 1000 ' 120 i 1609.5W, 43.5N 12.13.96 200 0.0 ' O.0 1000 121 1638.5W, 43.5N 12.13.96 200 0.0 0.0 ! 1000 122 , 1667.5W,43.5N 12.13.96 200 0.0 0.0 i 1000 123 , 1696.5W, 43.5N 12.13.96 200 0.0 , 0.0 i 1000 124 I 1725.5W. 43.5N 12.13.96 200 11.0 , 5.5 ! 1000
125 1 1754.5W, 43.5N i 12.13.96 200 0.0 0.0 | 1000 126 ! 1783.5W, 43.5N 12.13.96 200 0.0 , 0.0 i 1000
' 127 i 1812.5W, 43.5N ' 12.13.96 200 0.0 O.0 t 1000 128 ' 14.5W, 72.5N 12.13.96 200 0.0 0.0 i 1000 129 ' 43.5W, 72.5N 12.13.96 200 0.0 0.0 ! 1000 130 i 72.5W, 72.5N 12.13.96 200 0.0 0.0 ' 1000 131 101.5W, 72.5N 12.13.96 200 0.0 ' O.0 1000 132 i 130.5W, 72.5N 12.13.96 200 0.0 0.0 1000 133 159.5W, 72.5N 12.13.96 200 4.0 2.0 1000 134 ! 188.5W, 72.5N i 12.13.96 200 0.0 0.0 | 1000 135 i 217.5W, 72.5N 12.13.96 200 7.0 3.5 ! 1000 136 | 246.5W, 72.5N 12.13.96 200 0.0 : 0.0 | 1000 137 , 275.5W, 72.5N 12.13.96 200 0.0 0.0 | 1000 138 i 304.5W. 72.5N 12.13.96 200 0.0 0.0 1000
Appendix 11 - 3
| D:troit Ars nal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
LOCATION t COORDINATES SAMPLE DATE I AREA cm' i dpm dpm/100 cm' ' UMIT r/100 cm') 139 333.5W, 72.5N 12.13.96 200 0.0 0.0 i 1000 140 362.5W, 72.5N 12.13.96 ! 200 ' 0.0 0.0 | 1000 141 391.5W, 72.5N 12.13.96 j 200 0.0 0.0 j 1000 i 142 420.5W, 72.5N 12.13.96 200 0.0 0.0 i 1000 143 449.5W, 72.5N 12.13.96 ' 200 0.0 0.0 1000 144 478.5W, 72.5N 12.13.96 ! 200 0.0 0.0 1 1000 145 507.5W, 72.5N 12.13.96 i 200 0.0 0.0 | 1000 146 536.5W, 72.5N 12.13.96 200 0.0 0.0 | 1000 147 565.5W 72.5N 12.13.96 , 200 0.0 0.0 t 1000 148 594.5W, 72.5N j 12.13.96 200 0.0 0.0 | 1000 149 623.5W, 72.5N 12.13.96 200 0.0 ' O.0 1000 150 652.5W, 72.5N 12.13.96 200 0.0 0.0 i 1000 151 681.5W, 72.5N 12.13.96 i 200 16.0 8.0 i 1000 152 710.5W, 72.5N + 12.13.96 200 0.0 0.0 ! 1000 153 739.5W, 72.5N 12.13.96 200 0.0 0.0 1000 154 768.5W, 72.5N 12.13.96 200 0.0 0.0 1000 155 797.5W, 72.5N 12.13.96 ! 200 0.0 0.0 > 1000 156 826.5W, 72.5N ! 12.13.96 200 0.0 0.0 , 1000 157 855.5W, 72.5N 12.13.96 200 0.0 0.0 - 1000
158 884.5W, 72.5N 12.13.96 t | 200 60.0 30.0 1000 . 159 913.5W, 72.5N 12.13.96 | 200 0.0 0.0 i 1000 , 160 942.5W, 72,5N 12.13.96 ! 200 7.0 3.5 i 1000 161 971.5W, 72.5N 12.13.96 200 65.0 32.5 j 1000 162 1000.5W, 72.5N | 12.13.96 | 200 0.0 0.0 | 1000 i 163 1029.5W, 72.5N 12.13.96 ! 200 0.0 0.0 ! 1000 164 1058.5W, 72.5N 12.13.96 , 200 0.0 0.0 l 1000 165 1087.5W, 72.5N 12.13.96 r 200 0.0 i 0.0 i 1000 > > 166 1116.5W, 72.5N ' 12.13.96 200 30.0 15.0 1 1000 167 1145.5W, 72.5N ' 12.13.96 200 4.0 2.0 i 1000 168 1174.5W, 72.5N ( 12.13.96 200 19.0 9.5 i 1000 ' 169 1203.5W, 72.5N 12.13.96 200 122.0 61.0 i 1000 170 1232.5W, 72.5N 12.13.96 200 0.0 0.0 , 1000 ^ 171 1261.5W, 72.5N 12.13.96 ; 200 35.0 17.5 1000 172 1290.5W,72.5N 12.13.96 ; 200 0.0 0.0 4 1000 173 1319.5W, 72.5N 12.13.96 j 200 0.0 0.0 ' 1000 174 1348.5W, 72.5N ' 12.13.96 200 , 0.0 0.0 ! 1000 175 1377.5W, 72.5N 12.13.96 200 0.0 0.0 ! 1000 176 1406.5W, 72.5N i 12.13.96 200 12.0 6.0 i 1000 177 1435.5W, 72.5N 12.13.96 200 0.0 0.0 | 1000 178 1464.5W, 72.5N 12.13.96 i 200 0.0 0.0 1000 i 1493.5W, 72.5N 179 12.13.96 ! 200 0.0 0.0 , 1000 1522.5W, 72.5N 180 12.13.96 200 0.0 0.0 i 1000 181 1551.5W, 72.5N 12.13.96 ! 200 4.0 2.0 1000 182 1580.5W, 72.5N 12.13.96 200 0.0 0.0 1000 183 1609.5W, 72.5N 12.13.96 ' 200 78.0 39.0 1000 184 1638.5W. 72.5N 12.13.96 ! 200 0.0 0.0 > 1000
Appendix 11 - 4 D troit Arstnal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
LOCATION t COORDINATES SAMPLE DATE AREA cm' ' dpm , dpm/100 cm' LIMIT (*/100 cm') 185 1667.5W, 72.5N 12.13.96 200 41.0 i 20.5 1000 186 1696.5W, 72.5N ' ' 12.13.96 |dOO O.0 . 0.0 1000 187 1725.5W, 72.5N 12.13.96 200 2.0 1.0 l 1000 188 1754.5W, 72.5N 12.13.96 200 0.0 0.0 1000 189 1783.5W, 72.5N 12.13.96 200 0.0 0.0 1000 190 1812.5W, 72.5N 12.13.96 200 2.0 , 1.0 1000
191 14.5W,101.5N ! 12.13.96 200 ! 0.0 0.0 | 1000 192 43.5W,101.5N 12.13.96 200 : 0.0 0.0 i 1000 193 ' 72.5W,101.5N 12.13.96 200 9.0 , 4.5 1000 194 101.5W,101.5N ' 12.13.96 200 ! 0.0 O.0 i 1000 195 130.5W,101.5N 12.13.96 200 0.0 ! 0.0 e 1000
196 159.5W,101.5N , 12.13.96 200 4.0 ! 2.0 i 1000 197 188.5W,101.5N 12.13.96 200 0.0 , 0.0 1000 198 217.5W,101.5N 12.13.96 200 0.0 0.0 1000 199 246.5W,101.5N _ 12.13.96 200 0.0 0.0 1000 200 275.5W,101.5N 12.13.96 200 122.0 61.0 1000 201 304.5W,101.5N 12.16.96 200 27.0 13.5 1000 202 333.5W,101.5N 12.16.96 200 35.0 i 17.5 ' 1000 203 362.5W,101.5N 12.16.96 200 7.0 | 3.5 t 1000 204 391.5W,101.5N 12.16.96 200 11.0 | 5.5 i 1000 205 420.5W,101.5N 12.16.96 200 0.0 : 0.0 | 1000
206 1 449.5W,101.5N 12.16.96 200 11.0 t 5.5 ! 1000 207 478.5W,101.5N 12.16.96 200 0.0 1 0.0 1000 208 ' 507.5W,101.5N 12.16.96 200 2.0 : 1.0 : 1000 209 536.5W,101.5N 12.16.96 200 11.0 ' 5.5 ' 1000 210 565.5W,101.5N 12.16.96 200 7.0 3.5 i 1000
211 , 594.5W,101.5N 12.16.06 200 9.0 , 4.5 1 1000
212 623.5W,101.5N > 12.16.96 200 4.0 2.0 ! 1000 213 652.5W,101.5N 12.16.96 200 0.0 1 0.0 i 1000 214 681.5W,101.5N 12.16.96 200 0.0 0.0 ! 1000 215 710.5W,101.5N 12.16.96 200 7.0 ! 3.5 ; 1000 216 739.5W,101.5N ' 12.16.96 200 5.0 2.5 ! 1000 217 ' 768.5W,101.5N 12.16.96 200 2.0 | 1.0 , 1000 218 797.5W.101.5N 12.16.96 200 19.0 t 9.5 1000 ~ ' 219 826.5W,101.5N 12.16.96 200 9.0 4.5 1000 220 855.5W,101.5N 12.16.96 200 0.0 0.0 1000 221 884.5W,101.5N 12.16.96 200 7.0 3.5 i 1000 > 222 913.5W,101.5N 12.16.96 200 7.0 ! 3.5 1000 223 942.5W,101.5N 12.16.96 200 11.0 t 5.5 i 1C-00
i ' 224 971.5W,101.5N 12.16.96 200 7.0 i 3.5 1000 ' 225 , 1000.5W,101.5N 12.16.96 200 19.0 9.5 i 1000 - 226 1029.5W,101.5N 12.16.96 200 7.0 ! 3.5 ; 1000
227 , 1058.5W,101.5N 12.16.96 200 16.0 I 8.0 i 1000 ' 228 i 1087.5W 101.5N 12.16.96 200 2.0 1.0 ! 1000 229 1116.5W,101.5N i _ 12.16.96 200 5.0 2.5 1000 230 ! 1145.5W.101.5N 12.16.96 200 9.0 4.5 1000
Appendix II - 5
_ _ _ - _ _ _ - __
Detroit Ars:nal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
LOCATION i COORDINATES SAMPLE DATE AREA cm' ' dpm dpm/100 cm' i LIMIT (*/100 cm') 231 1174.5W,101.5N 12.16.96 200 5.0 2.5 1 1000 _ 232 1203.5W 101.5N 12.16.96 i 200 0.0 0.0 i 1000 233 1232.5W,101.5N ' 12.16.96 200 30.0 15.0 1 1000 234 1261.5W,101.5N 12.16.96 200 4.0 2.0 i 1000 235 1290.5W,101.5N 12.16.96 200 5.0 i 2.5 ! 1000 236 1319.5W,101.5N 12.16.96 200 , 9.0 4.5 i 1000 1348.5W,101.5N 237 12.16.96 200 0.0 0.0 ! 1000 1377.5W,101.5N 238 12.16.96 200 0.0 0.0 i 1000 239 1406.5W,101.5N 12.16.96 200 0.0 - 0.0 1000 240 1435.5W,101.5N 12.16.96 200 i 11.0 5.5 i 1000 241 1464.5W,101.5N 12.16.96 200 7 5.0 I 2.5 i 1000 242 1493.5W,101.5N 12.16.96 200 21.0 10.5 | 1000 243 1522.5W,101.5N 12.16.96 200 0.0 0.0 ! 1000 244 1551.5W,101.5N 12.16.96 200 7.0 3.5 ' 1000 245 1580.5W,101.5N 12.16.96 200 2.0 1.0 1000 246 1609.5W,101.5N 12.16.96 200 0.0 0.0 1000 , 247 1638.5W,101.5N 12.16.96 200 14.0 7.0 1000 248 1667.5W,101.5N 12.16.96 200 7.0 3.5 i 1000 249 1696.5W,101.5N 12.16.96 200 5.0 2.5 l 1000
' 250 1725.5W,101.5N 12.16.96 200 2.0 1.0 l 1000
251 ! 1754.5W,101.5N ! ' 12.16.96 200 i 0.0 O.0 | 1000 252 , 1783.5W,101.5N 12.16.96 200 i 0.0 0.0 | 1000 253 1812.5W,101.5N ' 12.16.96 200 i 0.0 j 0.0 | 1000 > 254 , 14.5W,130.5N 1 12.16.96 200 i 102.0 | 51.0 1 1000 ' 255 43.5W,130.5N ' 12.16.96 200 O.0 ! 0.0 | 1000
, ' i 256 72.5W,130.eN ! 12.16.96 200 0.0 0.0 i 1000
< i 101.5W,130.5N 1 _257 12.16.96 i 200 0.0 0.0 l 1000 258 ! 130.5W,130.5N ' 12.16.96 ! 200 O.0 0.0 | 1000 259 159.5W,130.5N 12.16.96 200 0.0 0.0 i 1000 260 188.5W,130.5N 12.16.96 200 f 7.0 ' 3.5 i 1000 261 217.5W,130.5N 12.16.96 200 ' 4.0 2.0 1000
262 246.5W,130.5N , 12.16.96 200 14.0 i 7.0 i 1000 ' 263 275.5W,130.5N 12.16.96 200 7.0 3.5 1000 ' 264 304.5W,130.5N | 12.16.96 ! 200 i 0.0 i 0.0 i 1000 j ' 265 333.5W,130.5N 12.16.96 i 200 23.0 i 11.5 ! 1000 266 - 362.5W,130.5N ' 12.16.96 200 0.0 0.0 ! 1000
1 , 267 391.5W 130.5N , 12.16.96 | 200 0.0 i 0.0 1000 268 420.5W,130.5N ! 12.16.96 200 ; 2.0 ! 1.0 i 1000 269 ; 449.5W,130.5N 12.16.96 i 200 i 5.0 ' 2.5 | 1000
270 478.5W,130.5N , 12.16.96 200 i 19.0 9.5 ! 1000 ' 271 507.5W.130.5N 12.16.96 200 i 0.0 , 0.0 : 1000 ' 272 536.5W,130.5N 12.16.96 200 ! 0.0 0.0 1000
273 565.5W,130.5N - 12.16.96 200 1 0.0 0.0 1000 274 i 594.5W,130.5N 12.16.96 > 200 i 4.0 2.0 ' 1000
i 623.5W,130.5N ) i 275 12.16.96 200 0.0 i 0.0 1000 652.5W,130.5N ' 276 12.16.96 200 16.0 8.0 : 1000
Appendix || - 6 __- . . - -
Detroit Ars nalTank Plant (DATP) Decommissioning Activity Preliminary Survey i LOCATlON + COORDINATES SAMPLE DATE > AREA cm' ' dpm dpm/100 cm' r LIMIT r/100 cm')
' 277 681.5W,130.5N 12.16.96 200 2.0 1.0 : 1000
278 710.5W,130.5N 12.16.96 200 5.0 2.5 | 1000 279 739.5W,130.5N 12.16.96 200 9.0 4.5 i 1000 l i 280 768.5W,130.5N | 12.16.96 200 9.0 4.5 . 1000 ' ~ 281 797.5W,130.5N 12.16.96 200 0.0 0.0 1000 282 826.5W,130.5N 12.16.96 200 11.0 5.5 1000
283 855.5W,130.5N 12.16.96 200 2.0 1.0 f 1000 : 284 884.5W,130.5N 12.16.96 200 2.0 1.0 i 1000 285 913.5W,130.5N 12.16.96 200 4.0 2.0 1000 i 286 942.5W,130.5N 12.16.96 200 0.0 0.0 i 1000 1 287 971.5W,130.5N 12.16.96 200 0.0 0.0 i 1000 1000.5W,130.5N ; 288 12.16.96 200 9.0 4.5 , 1000 289 1029.5W,130.5N 12.16.96 200 9.0 4.5 1000 290 1058.5W,130.5N 12.16.96 200 2.0 1.0 1000 ~ 291 1087.5W,130.5N 12.16.96 200 0.0 0.0 1000 < 292 1116.5W,130.5N 12.16.96 200 11.0 5.5 1000 293 1145.5W,130.5N 12.16.96 200 0.0 0.0 1000 294 1174.5W,130.5N 12.16.96 200 0.0 0.0 ' 1000 1203.5W,130.5N , 295 12.16.96 200 9.0 4.5 1000
; 296 1232.5W,130.5N 12.16.96 200 9.0 4.5 1000 ' 297 1261.5W,130.5N 12.16.96 . 200 0.0 0.0 i 1000 4 298 1290.5W,130.5N 12.16.96 200 0.0 0.0 ! 1000 j 299 1319.5W,130.5N . 12.16.96 200 0.0 0.0 i 1000 * ~ 300 1348.5W,130.5N 12.16.96 200 0.0 0.0 1000 ' 301 1377.5W,130.5N 12.17.96 200 4.0 2.0 i 1000
302 1406.5W,130.5N 12.17.96 200 5.0 2.5 i 1000
303 1435.5W,130.5N 12.17.96 200 14.0 7.0 1 1000 304 1464.5W,130.5N 12.17.96 200 12.0 6.0 i 1000 305 1493.5W,130.5N 12.17.96 200 14.0 7.0 1000
1 306 1522.5W,130.5N 12.17.96 200 2.0 1.0 ! 1000 1551.5W,130.5N 307 12.17.96 200 2.0 1.0 . 1000 308 1580.5W,130.5N 12.17.96 200 7.0 3.5 7 1000 309 1609.5W,130.5N 12.17.96 200 19.0 9.5 ' 1000 310 1638.5W,130.5N 12.17.96 200 23.0 11.5 ' 1000 a 311 1667.5W,130.5N 12.17.96 < 200 18.0 9.0 1000
312 1696.5W,130.5N I 12.17.96 200 5.0 2.5 i 1000
. 313 1725.5W,130.5N 12.17.96 200 4.0 2.0 4 1000 4 314 1754.5W,130.5N 12.17.96 200 7.0 3.5 ' 1000 j 315 1783.5W,130.5N 12.17.96 200 9.0 4.5 i 1000 316 1812.5W,130.5N 12.17.96 200 0.0 0.0 1000 i 317 14.5W,159.5N 12.17.96 200 0.0 0.0 1000 1 318 43.5W,159.5N 12.17.96 200 0.0 0.0 1000 4 319 72.5W,159.5N 12.17.96 200 42.0 21.0 ' 1000 101.5W,159.5N ! _ 320 12.17.96 200 2.0 1.0 1 1000 321 130.5W,159.5N 12.17.96 200 16.0 8.0 1000
322 159.5W.159.5N , 12.17.96 200 18.0 9.0 1000
.
4 Appendix 11 - 7
2
1 1 |
Detroit Ars nal Tank Plant (DATP) Decommissioning Activity Preliminary Survey
SAMPLE DATE I AREA cm' ; LOCATION COORDINATES dpm dpm/100 cm' > LIMIT (*/100 cm')
323 188.5W,159.5N 12.17.96 200 30.0 15.0 ! 1000 324 217.5W,159.5N : 12.17.96 200 5.0 2.5 1000 | 325 246.5W,159.5N 12.17.96 200 4.0 2.0 1 1000 326 275.5W,159.5N 12.17.96 + 200 18.0 9.0 1000 327 304.5W,159.5N 12.17.96 200 9.0 4.5 1000 328 333.5W,159.5N 12.17.96 200 9.0 4.5 - 1000 {3_29 362.5W,159.5N 12.17.96 200 16.0 8.0 1000 330 391.5W,159.5N 12.17.96 200 9.0 4.5 ! 1000 I 331 420.5W,159.5N 12.17.96 200 7.0 3.5 ! 1000 332 449.5W,159.5N 12.17.96 200 2.0 1.0 i 1000
333 478.5W,159.5N 12.17.96 200 11.0 5.5 1 1000 334 507.5W,159.5N 12.17.96 200 19.0 9.5 | 1000 335 536.5W,159.5N 12.17.96 200 0.0 0.0 1000
336 565.5W,159.5N 12.17.96 , 200 19.0 9.5 1000
594.5W,159.5N 4 337 12.17.96 200 9.0 4.5 < 1000 338 623.5W,159.5N 12.17.96 200 19.0 9.5 1000 339 652.5W,159.5N 12.17.96 200 0.0 0.0 1000 340 681.5W,159.5N 12.17.96 200 18.0 9.0 1000
341 710.5W,159.5N 12.17.96 200 21.0 10.5 , 1000
_342 739.5W,159.5N 12.17.96 200 0.0 0.0 , 1000 343 768.5W,159.5N 12.17.96 200 7.0 3.5 1 1000 344 797.5W,159.5N 12.17.96 200 16.0 8.0 | 1000 345 826.5W,159.5N 12.17.96 200 0.0 - 0.0 1 1000
346 855.5W,159.5N 12.17.96 200 0.0 , 0.0 ! 1000
347 884.5W,159.5N 12.17.96 200 18.0 t 9.0 ! 1000
348 913.5W,159.5N 12.17.96 200 4.0 1 2.0 | 1000 349 942.5W,159.5N 12.17.96 200 18.0 9.0 ; 1000 350 971.5W,159.5N 12.17.96 200 2.0 1.0 i 1000
351 1000.5W,159.5N 12.17.96 200 201.0 100.5 1 1000 352 1029.5W,159.5N 12.17.96 200 7.0 3.5 i 1000 353 1058.5W,159.5N 12.17.96 200 14.0 7.0 1000
354 1087.5W,159.5N 12.17.96 200 21.0 10.5 i 1000
355 1116.5W,159.5N 12.17.96 200 19.0 9.5 t 1000
356 1145.5W,159.5N 12.17.96 200 2.0 1.0 ! 1000 ' 357 1174.5W,159.5N 12.17.96 , 200 7.0 3.5 1000 1203.5W,159.5N 358 12.17.96 200 5.0 2.5 , 1000 359 1232.5W,159.5N 12.17.96 200 19.0 9.5 ' 1000 360 1261.5W,159.5N 12.17.96 200 9.0 4.5 ! 1000 361 1290.5W,159.5N 12.17.96 200 7.0 3.5 i 1000 362 1319.5W,159.5N 12.17.96 200 11.0 5.5 1000
363 1348.5W,159.5N 12.17.96 200 4.0 2.0 l 1000 364 1377.5W,159.5N 12.17.96 200 11.0 5.5 ' 1000
. 365 1406.5W,159.5N 12.17.96 200 , 11.0 5.5 1000
366 1435.5W,159.5N 12.17.96 , 200 4.0 2.0 i 1000 1464.5W,159.5N _367 12.17.96 200 27.0 13.5 l 1000 368 1493.5W,159.5N 12.17.96 200 2.0 1.0 1 1000
Appendix || - 8 ______. _ - - - _
i Ditroit Ars:nal Tank Plant (DATP) I Decommissioning Activity
, Preliminary Survey I
LOCATION * COORDINATES SAMPLE DATE i AREA cm' I dpm dpm/100 cm' LIMIT (*/100 cm')
369 1522.5W,159.5N . 12.17.96 200 4.0 2.0 1 1000 370 1551.5W,159.5N 12.17.96 200 12.0 6.0 1000 ' 371 1580.5W,159.5N 12.17.96 200 2.0 1 ' ' 1.0 1000 | 372 1609.5W,159.5N 12.17.96 200 7.0 3.5 > 1000 $ I 373 1638.5W,159.5N i ' 12.17.96 200 11.0 . 5.5 1000 l 374 1667.5W,159.5N 12.17.96 200 0.0 1 0.0 , 1000
. 375 1696.5W,159.5N 12.17.96 200 ! 16.0 8.0 ! 1000 ! 376 1725.5W,159.5N 12.17.96 200 7.0 3.5 | 1000 377 1754.5W,159.5N 12.17.96 200 11.0 5.5 ' 1000 378 1783.5W,159.5N 12.17.96 200 7.0 1 3.5 i 1000 ; 379 1812.5W,159.5N 12.17.96 200 28.0 14.0 1 1000 380 1841.5W, 29.ON 12.17.96 200 5.0 2.5 i 1000 l i ' 381 1856.0W,29.0N 12.17.96 200 5.0 i 2.5 1000 382 safety cnb (f 3 E). 6' N 12.18.96 200 0.0 i 0.0 1000 ; 383 safety crib (13 E),12' N 12.18.96 200 20 1.0 1000 | 384 safety crib (f 3 E) 18' N 12.18.96 200 9.0 4.5 1000 safety Office (dr 3. fir etr) 385 12.18.96 200 0.0 0.0 J 1000 386 safety Office (dr 2. rr fir ctr) , 12.18.96 200 11.0 5.5 1000
' , 387 Receiving (29 0 E) * 12.18.96 200 ! 5.0 2.5 i 1000 ' 388 Quality Office (15' E, flr ctr) 12.18.96 200 14.0 i 7.0 > 1000
t 389 Quality Office (29' E. fir ctr) 12.18.96 200 7.0 ! 3.5 i 1000 390 Logistics Office (fir ctr) 12.18.96 i ! f 200 11.0 t 5.5 1000 BKG 391 ' GDLS NE Entrance - 12.17.96 200 2.0 , 1.0 : 1000 ; BKG 392 t Blind Vend * 12.17.96 200 | 5.0 ! 2.5 : 1000
' BKG 393 Canteen Area * 12.17.96 , 200 , 0.0 0.0 1000
BKG 394 GDLS Exec Offices * 12.17.96 200 f 4.0 ! 2.0 , 1000
' BKG 395 Plant Facilities * 12.17.96 200 7.0 3.5 ! 1000
BKG 396 i Govt Safety Office - 12.17.96 200 1 0.0 0.0 l 1000
BKG 397 North-West Lobby " 12.17.96 200 12.0 6.0 ! 1000
, BKG 398 2f F . E Upright * 12.17.96 > 200 64.0 32.0 1000
' BKG 399 ' 21 B Upright * 12.17.96 200 , 0.0 0.0 1000 ' BKG 400 17 C D Up.'ight * 12.17.96 t 200 i 0.0 0.0 ! 1000 Avg BKG 3 DATP Unaffected Areas 12.17.96 200 9.4 4.7 i na
* Measurements taken adjacent to specified area upright. t ** Measurement taken inside double doors to the left of first office entrance.
t ,
.
4
.
. Appendix il - 9
: {
{
{ l
I f
APPENDIX III
H-3 CONTAMINATION DETECTED vs. " UNRESTRICTED USE" LIMIT
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19
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' APPENDIX IV |
, LIQUID SCINTILLATION GENERATED DATA
i
! .
1
4
3
20 a tF89: SU9"EYS l'0DE: CPR CD SN8L - FEFEA75: 0 FEFLICATES: 0 FA: OFF TIGE TERQ: 5.00 (= 1.00 |-] fCf (,, DM;ENT: Fregras Cossei.t Field
ARADETERS CHANNEL A CHANNEL B 2HANNEL C ...... n ~ . =...... ()^.% 1A w SCRIPTION: L0ii NEJ d!8H ANSE: 1 - 19 20 - 168 169 - 2000 ACL8ND SUB: 5 0. O FESETCNT: 0 0 0 CWCNTFEJ: 100 0 0 FILL-0VEA CORR: !)A C)A 2)3 0FF 0FF CFF LC: PALF-LIFE OFF 0FF 0FF LC: ;3SAY DATE: 06-21-88 06-21-88 06-21-88
ffCH4 'FR8M: SURVEYS START TRAY: o PUNS REllAININB: Cent ' FORT FILE: None 3PECTRUM FILE: None YENT: Batch C:ssent field 7E 12-03-96 TIME: 12:09:02
Y 10 TIRE CFMA/K CFMB/K CFMC/K 2sIA 2 stb :s1C A/B ESP FLA83 6 1 5.00 113047.8 25.0 15.6 0.27 17.83 22.65 88.*II NA 2 1.00 22.0 14.0 10.0 42.64 53.45 e3.25 !.571 LCR1 6o 'a Sassle I- 4 1.00 -29.0 6.0 6.0 37.14 81.65 81.65 4.833 LCR1 --- I $' 1.00 22.0 6.0 6.0 42.64 91.65 81.65 3.667 LCR1 6 1.00 27.0 - 9.0 2.0 38.49 66.67 8. 3.000 LCR1 7 1.00 19.0 7.0 6.0 45.88 75.59 81.n$ 2.714 LCR1 8 1.00 24.0 16.0 7.0 40.82 50.00 75.59 1.500 LCR1 6 1 1.00 26.0 11.0 5.0 39.22 60.30 89.44 2.364 LCR1 2 1.00 29.0 7.0 4.0 37.14 75.59 18.88 4.143 LCR1 3 1.00- 28.0 9.0 8.0 37.80 66.67 70.71 2.111 LCR1 4 1.00 11.0 9.0 9.0 60.30 66.67 66.67 1.222 LCR1 5 1.00 32.0 12.0 4.0 35.36 57.74 88.*I 2.667 LCR1 --- |6 -6 1.00 22.0 0.0 3.0 42.64 70.71 88.18 2.750 LCR1 7 1.00 23.0 8.0 6.0 41.70 70.71 81.65 2.875 LCR1 3 1.00 19.0 12.0 12.0 45.88 57.74 57.74 1.583 LCRI 2 1 1.00 25.0 16.0 12.0 40.00 50.00 57.74 1.563 LCRI 2 1.00 21.0 9.0 4.0 43.64 66.67 8.88 2.333 LCR1 3 - 1.00 26.0 21.0 8.0 39.22 43.64 70.71 1.238 LCR1 4' !.00 31.0 13.0 6.0 35.92 55.47 81.65 2.385 LCRI. 5 1.00 26.0 9.0 6.0 39.22 66.67 81.65 2.889 LCR1 6 1.00 19.0 8.0 9.0 45.88 70.71 66.67 2.375 LCR1 7 1.00 ~ 31.0- 13.0 14.0 35.92 55.47 53.45 2.385 LCRi~ A 0 0 1.00 31.0 12.0 10.0 35.92 57.74 63.25 2.583 LCR1 L .1 1.00 16.0 0.0 4.0 50.00 70.71 88.II 2.000 LCR1 2 1.00 15.0 11.0 6.0 51.64 60.30 81.65 1.364 LCR1 3 1.00- 28.0 15.0. 5.0 37.80 51.64 89.44 1.067 LCR1 4 1.00 21.0 6.0 7.0 43.64 81.65 75.59 3.500 LCR1 5 1.00 27.0 7.0 10.0 38.49 75.59 63.25 3.857 LCR1 6 1.00 21.0 8.0 10.0 43.64 70.71 63.25 2.625 LCR1 7 1.00 24.0 12.0 5.0 40.82 57.74 89.44 2.000 LCR1 8 1.00 20.0 4.0 4.0 44.72 88.88 88.88 5.000 LCR1 -.1 1.00 37.0 8.0 5.0 32.88 70.71 89.44 4.625 LCRP-N 2 1.00 25.0 7.0 8.0 40.00 75.59 70.71 3.571 LCR1 3 1.00 21.0 14.0 3.0 43.64 53,45 88.*I 1.500 LCRI 4 1.00 19.0 12.0. 2.0 45.88 57.74 88.I8 1.583 LCRI $ 1.00 24.0- -14.0 4.0 40.82 53.45 88.18 1.714 LCR1 f - 6, 1.00 39.0 7.0 5.0 32.03 75.59 89.44 5.571 LCR1
1
_ . _ _ . ______. - - - _ - - - _ _ ___-_. --
CH 4 M SA: SURVEYS 3 TART TRAY: 6 EUNS RERAINING: Cent DRTFILE: None 3FECTRUM FILE: None MENT: fatch Cossent Field E:12-03-96 TIME: 12:58:40
V ID' TIRE CFMA/L CPM 8/K CFMC/t Is1A :518 :s1C A/B ESP FLA8 !.00 :6.0 16.0 13.0 39.22 50.00 55.47 1.625 LCR1 3 1.00 32.0 6.0 7.0 35.36 31.65 75.59 5.333 LCR1 1 1.00 :5.0 . 12.0 : 0 40.00 57.74 66.67 :.S83 LCR1 : 1.00 :8.0 10.0 4.0 37.80 63.25 8.Ii 2.800 LCR1 3 1.00 27.0 17.0 10.0 38.49 48.51 63.25 1.588 LCR1- 4 0 4 !.00 33.0 13.0 8.9 b.02 !!.47 18.88 2.538 LCRI 5 1.00 35.0 3.0 7.0 33.81 11.I8 75.59 11.667 LCRI 3 1.00 :4.0 7.0 ' 5.0 40.82 75.59 99.44 3.429 LCR1 !.00 :9.0 e.0 4.0 37.14 81.65 66.67 4.833 LCR1 i !.00 !5.0 16.0 10.0 33.81 50.00 63.25 2.188 LCRI 1 1.00 16.0 3.0 1.0 50.00 18.18 ft.st 9.333 LCRI : 1.00 7.0 9.0 * 4.0 38.40 66.67 18.!! 3.000 LCR1 1.00 26.0 10.0 4.0 39.2: 63.25 18.8I 2.600 LCRI 4 1.00 39.0 0.0 12.0 32.03 '0.71 57.74 4.875 LCR1 ? 1.00 20.0 '.0 1.0 44.72 t!.It 18.18 e.e67 LCR1- EO : :.00 i'.0 4.0 ' '.0 43.51 : .e7 75.59 1.589 LCR1 !.~0 :4.0 13.0 8.0 4).82 55.47 70.71 1.846 LCR1 3 1.00 24.0 8.0 2.0 40.82 70.7! 88.88 3.000 LCR1 : 1.00 17.0 14.0 !.0 48.51 53.45 89.44 1.214 LCR1 2 1.00 22.0 12.0 2.0 42.64 57.74 ft.it 1.833 LCR1 3 1.00 22.0 20.0 10.0 42.64 44.72 63.25 1.100 LCR1 4 1.00 18.0 18.0 12.0 47.14 47.14 57.74 1.000 LCR1- 5 1.00 24.0 8.0 6.0 40.82 70.71 81.65 3.000 LCR1 6 1.00 24.0 10.0 11.0 40.82 63.25 60.30 2.400 LCFr! , 7 1.00 27.0 18.0 8.0 38.40 47.14 70.71 .500 LCRI - 4 0 5 1.00 22.0 10.0 8.0 35.36 63.:5 70.71 3.a 1 LCR1 1 !.00 26.0 13.0 10.0 39.22 55.47 63.25 2.000 LCR1 2 !.00 29.0 11.0 5.0 37.14 60.30 8?.44 2.636 LCR1 3 1.00 16.0 15.0 5.0 50.00 51.64 89.44 1.067 LCR1 4 1.00 23.0 8.0 6.0 41.70 70.71 81.65 2.875 LCR1 5 1.00 25.0 10.0 6.0 40.00 63.25 81.65 2.500 LCR1 6 1.00 36.0 14.0 8.0 33.33 53.45 70.71 2.571 LCRI 7 1.00 30.0 17.0 5.0 36.51 48.51 G?.44 1.765 LCR1 3 1.00 34.0 5.0 11.0 34.30 99.44 60.30 6.800 LCR1 1 1.00 21.0 10.0 12.0 43.64 63.25 57.74 2.100 LCR1- 7C 2 1.00 29.0 16.0 7.0 37.14 50.00 75.59 1.813 LCR1 3 1.00 21.0 14.0 6.0 43.64 53.45 70.71 1.500 LCR1 4 1.00 30.0 0.0 ?.0 36.51 70.71 66.67 3.750 LCR1 5 1.00 26.0 11.0 12.0 39.22 60.30 57.74 2.364 LCR1 6 1.00 33.0 10.0 3.0 34.82 63.25 tt.II 3.300 LCR1 7 1.00 23.0 18.0 7.0 41.70 47.14 75.59 1.278 LCR1 8 1.00 23.0 11.0 11.0 41.70 60.30 60.30 2.091 LCR1 1 1.00 18.0 17.0 7.0 47.14 48.51 75.59 1.059 LCR1 2 1.00 26.0 11.0 6.0 39.22 60.30 81.65 2.364 LCR1 3 1.00 21.0 12.0 0.0 43.64 57.74 70.71 1.750 LCRT"' D 4 1.00 24.0 16.0 11.0 40.82 50.00 60.30 1.500 LCR1 5 1.00 32.0 14.0 10.0 35.36 53.45 63.25 2.286 LCRI 6 1.00 20.0 15.0 10.0 44.72 51.64 63.25 1.333 LCR1 7 1.00 28.0 7.0 6.0 37.80 75.59 81.65 4.000 LCR1 0 1.00 28.0 18.0 8.0 37.80 47.14 70.71 1.556 LCR1 ,1 1.00 25.0 15.0 14.0 40.00 51.64 53.45 1.667 LCR1 2 1.00 24.0 8.0 11.0 40.82 70.71 60.30 3.000 LCR1 22.0 18.0 !3 1.00 11.0 42.64 47.14 60.30 1.222 LCR1 1.00 25.0 6.0 i4 10.0 40.00 81.65 63.25 4.167 LCR1 l
_
__ _ _ - ______- _ _ .. . _
C4 4 F#GM: SURVEYS 57 ART TEAY: 6 :UNS FEMAINING: Cent ORT FILE: None SPECTRUM FILE: None MENT: !aten Consent Field En 12-03-i6 TIME: 14:11:23
i !D TIME CFNA/r C5!'!/K CFNC/r 2sIA 2sta 251C A/B ggp rtAg 5 1.00 24.0 0.0 6.0 40.82 66.67 31.65 2.b67 LCR1 - 9 6 : 1.00 27.0 14.0 !0.0 ;8.49 53.45 63.25 1.929 ~ LCR1 1.00 74.0 5.0 5.0 34.30 80.44 97.44 6.300 LCR1 3 !.00 29.0 9.0 4.0 37.14 66.67 26.67 3.222 LCR1 1 1.00 :9.0 2.0 15.0 37.80 70.71 51.64 !.!00 LCR1 : 1.00 l'.0 21.0 ' 4.0 45.99 43.64 18.II 0.?05 LCRI !.00 :2.0 12.0 ; 13.0 42.64 55.47 !*.47 1.:92 LCR1 N li.0 17.0 9.0 45.E3 49.51 f:.67 1.!!9 LCR! ! :.'0s ;5.0 11.0 11.0 40.00 60.30 60.30 2.273 LCR1 1.00 :!.0 11.0 ~ 12.0 41.70 60.30 57.74 2.091 LCR1 1.00 21.0 14.0 7.0 43.64 $!.45 75.!9 .500 LCR1 - tC@ *?. SitDlt
. 1.0) .'I.0 16.0 7.0 40.00 50.00 7$.$9 1.$63 ;,CR) - D $480le
':' :inDat D 384019 N3 $4ADie %3 33PD}e N3 3390le N0 3&&Dle
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' 00 !!!;73.3 . . 2.0 i!,o o.:? !!.22 ~4 : :. :: N#' %M : 1.M 01.0 !s.0 4.0 :!.1: !0.00 : . 1.?:2 LCA1 t iisole 4 . 00 :3.0 5.0 3.0 " .30 !0.30 7: 71 1.750 LOR 1- | C \ 5 1.00 3.0 ;0.0 !.07.30 ::.25 39.44 2.500 L R: : 1. M !6.0 :.0 l''.0 ::.;; 31.55 3:.25 :.000 LCR1 7 1.00 :3.0 15.0 11.0 37.30 51.e4 60.00 1.367 LCR1 i 1.00 2!.0 !!.0 7.0 41.70 51.64'75.5? 1.!!3 LCRI ! !.00 :5.0 s.0 s.0 40.00 50.00 31.o5 1.563 LCR1 2 1.00 17.0 !!.0 ;0.0 43.51 w.') 3 .:5 1.545 (CR: : 1.00 21.0 15.0 2.0 43.64 51.:4 : . 1.400 '. :R1 2 1.00 19.0 17.0 5.0 45.E3 42.5130.44 1.118 LCR1 5 1.00 :3.0 15.) !!.0 ;4.92 '1.9 20. 0 2.:00 LCR1- 1I O 6 1.00 ;4.0 15.0 7.04.30 5!.e4 to.o7 2 :57 tcci
,
P
- - _ _ _ _ . 4 PR6M: SURVEY 5 START TRAY: 6 RUN3 REMAININ8: Cent f FILE: None SPECTRUM FILE: None "NT: Batch Coseent Field 12-02-96 TIME:13:44:07
ID TIME.-CPMA/K CPMB/K CFMC/K :sIA 2s1B 2 SIC A/B E3P FLAG 7 1.00 17.0 13.0 5.0 48.5155.4T 99.44 1.308' LCR1 0 1.00 31.0 13.0 6.0 35.92 55.47 81.65 2.385 LCR1 1 1.00 36.0 11.0 6.0 33.33 60.30 81.65 3.273 LCR1 2 1.00 23.0 5.0 7.0 41.70 39.44 75.59 4.600 LCR1 3 . 1.00 20.0 8.0 7.0 37.00 70.71 75.59 3.500 LCR1 4 1.00 26.0 6.0 2.0 39.22 81.65 ft.it 4.333 LCR1 5 1.00 19.0 13.0 7.0 45.88 55.47 75.59 1.462 LCR1 6 1.00 31.0 12.0 3.0 35.92 57.74 ti.it 2.583 LCR1 7 1.00- 15.0 8.0 10.0 51.64 70.71 63.25 1.875 LCR1 - | 1 0 8 1.00 22.0 16.0 15.0 42.64 50.00 51.64 1.375 LCR1 1- 00- 20.0 9.0 4.0 37.80 66.67 II.It 3.111 LCR1 .00 30.0 10.0 8.0 36.51 63.25 70.71 3.000 LCR1
. . 00 36.0 13.0 8.0 33.33 55.47 70.7! 2.769 LCR1 4 1.00, 30.0 5.0 7.0 34.51 81.65 75.59 5.000 LCR1 5 1.00 26.0 9.0 10.0 39.22 66 e7 63.25 2.989 LCR! 6 1.00 22.0 6.0 5.0 42.64 81.65 89.44 3.667 LCR1 7 !.00 22.0 17.0 6.0 42.64 48.51 81.6! 1.2?4 LCR! ~ 8 1.00 17.0 12.0 0.0 48.51 57.74 70.71 1.417 LCR1 1-'1.00 26.0 2.0 5.0 39.22 t.I 89.44 13.000 LCR!- G O 2 1.00 25.0 6.0 4.0 40.00 81.65 *t.88 4.167 LCR1 3 1.00 21.0 10.0 3.0 43.64 63.25 .II 2.100 LCR1 4 1.00 32.0 14.0 5.0 35.36 53.45 89.44 2.286 LCR1 5 1.00 25.0 4.0 5.0 40.00 ft.tt 89.44 6.250 LCR1 6 1.00 34.0 9.0 4.0 34.30 66.67 84.18 3.778 LCR1 7 1.00 27.0 9.0 3.0 38.49 66.67 88.88 3.000 LCR1 0 1.00 30.0 7.0 4.0 36.51 75.59 88.88 4.286 LCR1 1 1.00 18.0 13.0 5.0 47.14 55.47 89.44 1.385 LCR1 2 1.00 19.0 9.0 5.0 45.88 66.67 89.44 2.111 LCR1 3 1.00 19.0 8.0 4.0 45.88 70.71 88.88 2.375 LCR)--- |NO 4 1.00 26.0 17.0 4.0 39.22 48.51 18.88 1.529 LCR1 5 1.00 24.0 4.0 7.0 40.82 18.88 75.59 6.000 LCR1 6 1.00 21.0 11.0 4.0 43.64 60.30 tt.Ii 1.909 LCR1 7 1.00 24.0 14.0 9.0 40.82 53.45 66.67 1.714 LCR1 8 1.00 24.0 6.0 6.0 40.02 81.65 81.65 4.000 LCR1 1 1.00 28.0 6.0 3.0 37.00 81.65 18.81 4.667 LCR1 2 1.00 26.0 6.0 5.0 39.22 81.65 89.44 4.333 LCRI : 3' 1.00 25.0 4.0 1.0 40.00 t .II It.I1 6.250 LCR1 4 1.00 15.0 10.0 4.0 51.64 63.25 11.18 1.500 LCR1 ' .5 1.00 20.0 14.0 5.0 44.72 53.45 09.44 1.429 LCR M | N 6 1.00 39.0 11.0 5.0 32.03 60.30 89.44 3.545 LCR1 7 1.00 23.0 10.0 3.0 41.70 63.25 18.18 2.300 LCR1 8 ~1.00 28.0 5.0 5.0 37.00 89.44 09.44 5.600 LCR1 1 1.00 30.0 4.0 2.0 36.51 ** *I tt.It 7.500 LCR1 2 1.00 28.0 13.0 0.0 37.80 55.47 88.18 2.154 LCR1 3 1.00 25.0 5.0 3.0 40.00 89.44 tt.tt 5.000 LCR1 4 1.00 20.0 11.0 4.0 37.80 60.30 **.*I 2.545 LCR1 5 -1.00 64.0 15.0 8.0 25.00 51.64 70.71 4.267 LCR1 6 1.00 25.0 10.0 3.0 40.00 63.25 *t.II 2.500 LCRI 7 1.00 34.0 6.0 1.0 34.30 81.65 .88 5.667 LCR1- f 6 0 8 1.00 67.0 18.0 3.0 24.43 47.14 88.88 3.722 LCR1 1 1.00- 30.0 14.0 4.0 36.51 53.45 31.88 2.143 LCR1 p_L__L OO 21.0 '202 4.0 35.M ".74 st.it 2 :9 LC8!
- _ _ _ _ - _ < ;.vv 34.J 2,.s o.v so.sv : .o si.c3 :.ais Lwn2 4 1.00 24.0 7.0 2.0 40.32 66.o7 88.88 :.co7 LCR1
4 F2SM: SUR'/Ef 3 3 TART TRAft 6 40NS FEMalN!N6 Cont T FILE: None 3FECTRUM FILE: None N7: Batta C:ssent Field 12-02-76 i:ME: 14:57:59
!D T!ME CF?A/( CMB/K CFMC/K :sIA :llB : SIC A/B ESP FLAG 5 1.00 47.0 10.0 5.0 :9.17 63.:5 39.44 4.700 LCR1 e 1.00 32.0 5.0 5.0 35.36 39.44 89.44 6.400 LCR1 7 1.00 41.0 5.0 3.0 31.23 57.44 st.it 9.000 LCR1 3 1.00 :3.0 1.0 7.0 20.10 6o.o7 75.5? 11.000 LCR1 1 1.00 :6.0 7.0 3.0 37.:: 75.54 70.71 3.714 LCR1- |TO : 1.00 50.0 12.0 e.0 :9.23 57.74 81.65 4.167 LCR1 3 1.00 30.0 3.0 7.0 36.51 70.71 75.57 3.750 LCR1 4 1.00 !?.) 7.0 5.0 49.51 7'.!: 32.44 :.424 LCR1 5 1.00 :7.. ?.0 13.0 33.49 is.o7 55.47 3.000 LCR1 i 1.00 :1.0 3.0 e.0 43.64 70.71 21.65 2.625 LCR1 7 1.00 '0. 3.0 3.0 32.33 66.67 62.67 4.111 LCR1 3 1.00 :3.0 I?.0 3.0 37.80 45.33 70.71 1.474 LCR1 1 1.00 :!.0 3.0 5.0 43.e4 70.71 59.44 2.625 LCRI : 1.00 :1.0 ?.0 2.0 43.64 75.59 88.81 3.000 1.CR1 3 1.00 22.0 9.0 6.0 42.64 66.67 31.65 2.444 LCR1- |%O 4 1.00 32.0 4.0 6.0 35.36 81.88 51.65 8.000 LCR1 5 1.00 :0.0 4.0 0.0 44.72 II.!! !!.88 5.000 LCR1 6 1.00 74.0 7.0 4.0 23. 5 75.59 8.Ii 10.571 LCR! 7 1.00 :4.0 7.0 4.0 40.92 75.59 st.it 3.429 LCR1 3 1.00 !!.0 12.0 3.0 27.47 57.74 11.88 4.417 LCR1 1 1.00 29.0 6.0 3.0 37.14 61.65 II.st 4.833 LCR1 : 1.00 !!.0 4.0 6.0 35.92 11.18 81.o$ 7.750 LCR1 3 1.00 :9.0 8.0 2.0 37.30 66.67 81.II 3.111 LCR1 4 1.00 7.0 7.0 6.0 30.47 66.67 91.65 :.000 LCR1 5 1.00 31.0 11.0 6.0 35.92 60.30 81.65 2.918 LCR1 - R D t 1.00 ::.0 16.0 11.0 42.64 50.00 60.30 1.375 LCR1 7 1.00 !.0 9.0 5.0 40.00 6e.67 87.44 2.778 LCR1 ',I 3 1.00 35.0 14.0 11.0 33.81 53.45 60.30 2.500 LCR1 d 1 1.00 23.0 8.0 6.0 37.90 66.67 01.65 3.111 LCR1 2 1.00 ::.0 10.0 4.0 42.64 63.:5 I.8I 2.200 LCR1 ! 1.00 32.0 9.0 8.0 35.36 66.67 70.71 3.556 LCR1 4 1.00 26.0 10.0 e.0 39.22 63.25 81.65 2.600 LCR1 5 1.00 :5.0 10.0 6.0 40.00 63.25 31.65 2.500 LCR1 6 1.00 :4.0 6.0 4.0 40.92 31.65 88.18 4.000 LCR1 ' 5.00 99.0 7.3 2.2 3.99 32.93 53.45 12.6?3 - ig ko 5asole i 1.00 :3.0 15.0 7.0 37.30 $1.64 75.59 1.867 LCR1 \ No Sanole No Sainte -' No Sanole No Satole No Satole t No Sanole i No $asole
- - _ - ______--__- ll |T h Mr SURVEYS MDEE: CP9 CD ENGL GEFEAVS: 0 9EPLICATES: 0 F9: OFF 1 'IME TERM: 5.00 r= 1.00 g ' QQ-- 3cc iMENT: Fregras Ceseent Field ' . :g :AMETERS CHANNEL A CHANNEL B CHANNEL C M.*5
...... - -- ...... ------_ - _= =
IC21FTICN: LOW MED HIGH 16E 1 - 19 20 - 168 169 - 2000 EGN3 Suit 0 0 0 SET CET: 0 0 0 CNT GEh 100 0 0 LL-0VEQ CMR i>A C; A C)B CFF 0FF 0FF
: FALF-LIFE: CFF 0FF QFF : iSSM DATE: 06-21-58 06-21-S8 06-21-88
CH 4 FRGM SURVEV5 37 ART TEAY: 6 FUNS EEMAININS: Cont ORf FILE: None SPECTRUN FILE: None MENT: !atch C:seent Field E: 12-04-96 IIME: 13:!$ 53
VD TIGE :FMAll CFMB/A CFMC/K :s1A 2s19 2 SIC A/B ESP FLA8 3, . 1 * .00 112:89.0 25.0 - .d 12.6 0.27 17.89 25.20 t8.11 . : 1.00 :4.0 14.0 10.0 40.82 53.45 63.:5 !.714 LCRI - sa iassie 4 1.00 37.0 5.0 2.0 32.88 70.71 ts.*: 4.625 LCR1- - 1 01 ! 1.00 42.0 11.0 3.0 30.86 60.30 18.18 3.818 LCRI 6 1.00 :6.0 5.0 6.0 39.22 69.44 81.65 5.200 LCR1 7 1.00 28.0 7.0 11.0 37.80 75.59 60.30 4.000 LCR1 8 1.00 22.0 11.0 9.0 42.64 60.30 66.67 2.000 LCRI 1 1.00 28.0 6.0 8.0 37.80 81.65 70.71 4.667 LCR1 2 1.00 13.0 6.0 5.0 55.47 81.65 89.44 2.167 LCR1 3 1.00 23.0 3.0 4.0 41.70 70.71 88.tI 2.875 LCR1 4 . 00 28.0 4.0 10.0 37.50 ft.tt 63.:5 7.000 LCR! 5 1.00 26.0 6.0 1.0 39.22 81.65 18.18 4.333 LCR1 ')d O 6 1.00 27.0 8.0 3.0 38.49 70.71 18.18 3.375 LCR1 7 1.00 24.0 6.0 4.0 40.82 81.65 11.18 4.000 LCR1 3 1.00 20.0 9.0 5.1 44.72 66.67 89.44 2.222 LCR1 : 1.00 20.0 10.0 1.0 42.6i 63.25 81.ti 2.200 LCRI 1.00 : 26.0 11.0 2.0 39.22 60.30 88.88 2.364 LCRI ' !.00 | 25.0 17.0 4.0 40.00 48.51 tt.II 1.471 LCR1 4 1.00 23.0 18.0 3.0 41.70 47.14 It.Ii 1. 78 LCR1 5 1.00 33.0 13.0 6.0 34.82 55.47 81.65 2.538 LCR1 : 1.00 27.0 6.0 3.0 38.49 81.65 st.it 4.500 LCR1 7 1.00 21.0 7.0 4.0 43.64 75.59 88.!! 3.000 LCRI- 4~10 8 1.00 26.0 11.0 1.0 39.22 60,30 !!.88 2.364 LCR1 1 1.00 26.0 12.0 3.0 39.22 57.74 i*.II 2.167 LCR1 : 1.00 28.0 10.0 6.0 37.80 63.25 81.65 2.800 LCR1 26.0 ! 1.00 13.0 3.0 39.22 55.47 88.88 2.000 LCR1 33.0 4 1.00 9.0 7.0 34.82 66.67 75.59 3.667 LCR1 5 1.00 26.0 10.0 7.0 39.22 63.25 75.59 2.600 LCR1 6 1.00 31.0 15.0 2.0 35.92 51.64 18.88 2.067 LCR1 7 1.00 23.0 10.0 6.0 41.70 63.25 81.65 2.300 LCR1 3 1.00 5.0 7.0 3.0 40.00 75.59 18.18 3.571 LCR1 1 1.00 27.0 12.0 3.0 38.49 57.74 88.II 2.250 LCRI - '13 0 2 1.00 25.0 8.0 3.0 40.00 70.71 18.It 3.125 LCR1 3 1.00 22.0 14.0 8.0 42.64 53.45 70.71 1.571 LCR1 4 5.00 39.0 8.4 8.4 14.32 30.86 30.86 4.643 5 1.00 24.0 10.0 6.0 40.82 63.25 81.65 2.400 LCR1 3 1.00 25.0 10.0 5.0 40.00 63.25 89.44 2.500 LCR1 .
CH o FPSM SURVEYS START TRAY: 6' N NS REZIN!NG: Coat DRTFILE: None iPECTRUM FILE: None MENT: l'atch Consent Field En 12-04-4 TIME: 14:11:13
Y 10 TipE CPMAIK CPMB/K CFMC/K Os1A 2stS :s1C A/B ESP FLAG 7 1.00 27.0 0.0 7.0 38.49 70.71 75.59 3.375 LCR1 8 1.00 20.0 7.0 7.0 44.72 75.59 75.59 2.857 LCR1 < 1 1.00 21.0 8.0 7.0 43.64 70.71 75.59 ~ 2.625 LCR1 2 1.00 17.0 3.0 4.0 48.51 88.II It.It 5.667 LCA1 3 1.00 28.0 12.0 7.0 37.50 57.74 75.59 2.333 LCR1 ' M O o 1.00 25.0 8.0 11.0 40.00 70.71 60.30 3.125 LCA1 5 1.00 34.0 7.0 4.0 34.30 75.59 88.!! 4.857 LCR1 e 1.00 20.0 10.0 5.0 44.72 63.25 89.44 2.000 LCRI 7 1.00 26.0 8.0 6.0 39.22 70.71 81.65 3.250 LCR1 8 1.00 23.0 10.0 7.0 41.70 63.25 75.59 2.300 LCR1 20.0 7.0 1.. ~ 1.00 2 4.0 44.72 75.57 88.II 2.857 LCR1 2 1.00 30.0 6.0 7.0 36.51 81.65 75.59 5.000 LCR1 3 1.00 26.0 0.0 3.0 39.22 70.71 18.Ii 3.250 LCR1 4 1.00 25.0 10.0- 5.0 40.00 63.25 89.44 2.500 LCR1 5- 1.00 23.0 12.0 3.0 41.70 57.74 It.Ii 1.917 LCRI 3 f C 6' 1.00 22.0 11.0 7.0 42.64 60.30 75.59 2.000 LCR1 7 1.00 22.0 16.0 9.0 42.64 $0.00 66.67 1.375 LCR1 3 1.00 17.0 13.0 9.0 48.51 55.47 66.67 1.308 LCR1 ,1 5.00 80.2 8.6 8.4 9.99 30.50 30.26 9.326 2 1.00 17.0 7.0 6.0 48.51 75.59 81.65 2.429 LCR1 3 1.00 21.0 11.0 6.0 43.64 60.30 81.65 1.909 LCRI ~4 1.00 21.0 8.0 7.0 43.64 70.71 75.59 2.625 LCR1 5 1.00 21.0 5.0 4.0 43.64 29.44 11.88 4.200 LCRI 6 1.00 18.0 10.0 5.0 47.14 63.25 89.44 1.800 7. LCR1 1.00 26.0- 13.0 4.0 39.22 55.47 11.88 2.000 LCR1- M O 8 1.00 24.0 10.0 '4.040.8263.2511.88 2.400 LCR1 1 1.00 30.0 11.0 5.0 36.51 60.30 89.44 2.727 'CRI. 2 1.00 26.0 11.0 4.0 39.22 60.30 88.88 2.364 LCR1 3 1.00 17.0 13.0 4.0 48.51 55.47 It.Ii 1.308 LCR1 -o 1.00 35.0 11.0 7.0 33.81 60.30 75.59 3.182 LCR1 5 1.00 21.0 9.0 4.0 43.64 66.67 18.18 2.333 LCR1 6 1.00 21.0 6.0 6.0 43.64 81.65 81.65 3.500 LCA1 7 1.00 23.0 15.0 6.0 41.70 51.64 81.65 1.533 LCR1 8 1.00 25.0 0.0 4.0 40.00 70.71 81.Ii 3.125 LCRI l' 1.00 33.0 8.0 6.0 34.82 70.71 81.65 4.125 LCRI-~ MO -. 2 1.00 20.0 9.0 4.0 44.72 66.67 18.88 2.222 LCRI 3 1.00. 17.0- 12.0 8.0 48.51 57.74 70.71 1.417 LCR1 4 1.00 19.0 11.0 8.0 45.88 60.30 70.71 1.727 LCR1 '5 1.00 24.0 8.0 3.0 40.82 70.71 88.88 3.000 LCR1 6 21.00 13.0 15.0 9.0 55.47 51.64 66.67 0.867 LCR1 7 . 1.00 .-31.0 13.0 .12.0 35.92 55.47 57.74 2.385 LCR1 8 .1.00 23.0 15.0 5.0 41.70 51.64 89.44 1.533 LCR1 .I 1.00 25.0- 9.0 8.0 40.00 66.67 70.71 2.778. LCR1 2 1.00 27.0 .7.0 3.0 38.49.75.59 8t,t8 3.857 LCRI 3 1.00 27.0 13.0 12.0 38.49 55.47 57.74 2.077 LCR1 - D C .4 1.00 19.0 9.0 6.0 45.88 66.67 81.65 2.111 LCR1 5 1.00 28.0 15.0 6.0 37.80 51.64 81.65 1.867 LCR1 6 1.00 23.0 18.0 15.0 41.70 47.14 51.64 1.278 LCR1 72 1.00 23.0 13.0 11.0 41.70 55.47 60.30 1,769 LCR1 0 1.00 24.0 14.0 4.0 40.82 53.45 t8.I8 1.714 LCR1 1 1.00 22.0 12.0 8.0 42.64 57.74 70.71 1.833 LCRI 2 1.00 20.0 8.0 7.0 44.72 70.71 75.59 2.500 LCR1 3 1.00 27.0 15.0 5.0 38.49 51.64 89.44 1.800 LCR1 4 1.00 .27.0 13.0 4.0 38.49 55.47 88.88 2.077 LCR1
...... ,. _ _ . - _ _ - _ . -_------
.CH 4 : IGM: SURVEYS 37 ART TRAY: 3 ;UNS FEMAINING: C:nt ,CRT FILE: None 3:ECTRUM FILE: Nene MENT: Patch Cessent Field En 1244-06 TIME: !$:29:20
Y 19 TiPE CPMA/K CPMBn CFMC/K :stA 2s19 2s1C UB ESP FLAG 5 1.00 23.0 !.0 7.0 41.70 70.71 75.59 2.375 LCR1- MO e . 00 19.0 17.0 ' .0 47.14 49.51 81.Ii 1.059 LCRI 00 28.0 ::.0 :1.0 !7.30 55.47 60.30 2.154 LCR1 5 1.00 19.0 13.0 6.0 45.58 55.47 91.65 1.462 LCR1 ! !.00 17.0 25.0 12.0 43.51 40.00 57.74 0.680 LCR1 : 1.00 27.0 12.0 5.0 33.49 57.74 70.71 2.250 LCR1 3 1.00 27.0 6.0 6.0 30.49 81.65 81.65 4.500 LCR1 4 !.00 19.0 0.0 ' i.0 45.38 66.67 66.67 2.111 LCR1 1.00 13.0 13.0 3.0 47.14 55.47 66.67 1.;85 LCR1 6 1.00 19.0 12.0 ' 7.0 47.14 57.74 75.59 1.500 LCR1 !.00 16.0 12.0 0.0 50.00 57.74 66.67 !.333 LCRI~ 3CO
0 20.0 6.0 17.0 44.72 31.65 48.51 3.;33 LCR1 - do titole No $18o19 No filole No ia8 ole NoSaaole No iasole No fasole
______- _ _ _ . __ - -
GM: SURVEYS MODE: CPM CQ SNGL REPEATS: 0 REPLICATES: O PM: OFF TIME TERM: 5.00 K: 1.00 MMENT: Program Comment Field ~ crD LC RAMETERS N-3 barf CHANNEL A CHANNEL B CHANNEL C 3,y. du ______
NGE: 1 - 19 20 - 168 169 - 2000 CKGND SUB: 0 0 0 'g g c. ESET CNT: 0 0 0 R CNT REJ: 100 0 0 . ILL-0VER CORR: B>A C>A C>B CLdL.go - g gC{* OFF OFF OFF ^ 1) : 56. 6 /c 3: HALF-LIFE: OFF OFF OFF , (T 3: ASSAY DATE: 06-21-88 06-21-88 06-21-88 TCH 4 PRGM: SURVEYS START TRAY: 6 RUNS REMAINING: Cont PORT FILE: None SPECTRUM FILE: None 4 MENT: Batch Comment Field CE: 12-04-96 TIME: 17:04:07
4Y ID TIME CPMA/K CPMB/K CPMC/K 2e%A 2s%B 2s%C A/B 2 ESP FLAG 3 1 5.00 105064.8 18.2 13.0 0. 28 20. 97 24. 81 ** . *** H 3*d 2 1.00 20.0 19.0 No dample, 15.0 44.72 45.88 51.64 1.053 fpqg LCR1 4 1.00 20.0 12.0 9.0 44.72 57.74 66.67 1.667 .70\ LCR1 5 1.00 21.0 7.0 10.0 43.64 75.59 63.25 3.000 LCR1 6 1.00 26.0 9.0 5.0 39.22 66.67 89.44 2.889 LCR1 7 1.00 25.0 11.0 6.0 40.00 60.30 81.65 2.273 LCR1 8 1.00 26.0 11.0 7.0 39.22 60.30 75.59 2.364 LCR1 3 1 1.00 19.0 10.0 12.0 45.88 63.25 57.74 1.900 LCR1 2 1.00 19.0 7.0 10.0 45.88 75.59 63.25 2.714 LCR1 3 1.00 22.0 15.0 4.0 42.64 51.64 **.** 1.467 LCR1 4 1.00 29.0 6.0 6.0 37.14 81.65 81.65 4.833 LCR1 5 1.00 31.0 4.0 3.0 35.92 **.** **.** 1.00 7.750--3\o LCR1 6 28.0 15.0 6.0 37.80 51.64 81.65 1.867 7 1.00 21.0 LCR1 8.0 6.0 43.64 70.71 81.65 2.625 LCR1 8 1.00 20.0 3.0 5.0 44.72 **.** 89.44 6.667 LCR1 1 1.00 22.0 12.0 7.0 42.64 57.74 75.59 1.833 LCR1 2 1.00 23.0 10.0 8.0 41.70 63.25 70.71 2.300 3 1.00 LCR1 7.0 7.0 5.0 75.59 75.59 89.44 1.000 4 1.00 LCR1 18.0 10.0 5.0 47.14 63.25 89.44 1.800 5 1.00 LCR1 12.0 20.0 7.0 57.74 44.72 75.59 0.600 LCR1 6 1.00 42.0 12.0 6.0 30.86 57.74 81.65 3.500 LCR1 7 1.00 19.0 12.0 5.0 45.88 57.74 89.44 1. 583-~ 31o LCR1 8 1.00 27.0 9.0 5.0 38.49 66.67 89.44 3.000 LCR1 1 1.00 28.0 8.0 4.0 37.80 70.71 **.** 3.500 2 LCR1 1.00 35.0 10.0 3.500 3 7.0 33.81 63.25 75.59 LCR1 1.00 21.0 7.0 8.0 43.64 75.59 70.71 3.000 4 1.00 LCR1 20.0 15.0 9.0 44.72 51.64 66.67 1.333 LCR1 5 1.00 28.0 11.0 5.0 37.80 60.30 89.44 2.545 6 1.00 LCR1 23.0 16.0 5.0 41.70 50.00 89.44 1.438 LCR1 7 1.00 23.0 12.0 6.0 41.70 57.74 81.65 1.917 LCR1 8 1.00 27.0 8.0 6.0 38.49 70.71 81.65 3.375 LCR1 1 1.00 23.0 7.0 0.0 41.70 75.59 **.** 3.286 330 LCR1 2 1.00 22.0 7.0 6.0 42.64 75.59 81.65 3.143 LCR1 3 1.00 19.0 4.0 5.0 45.88 **.** 89.44 4.750 LCR1 4 1.00 24.0 10.0 7.0 40.82 63.25 75.59 2.400 LCR1 5 1.00 29.0 10.0 7.0 37.14 63.25 75.59 2.900 LCR1 6 1.00 18.0 7.0 6.0 47.14 75.59 81.65 2.571 LCR1
-__-______ATCH 4 PRGM: SURVEYS START TRAY: 6 RUNS REMAINING: Cont EPORT FILE: None SPECTRUM FILE: OMMENT: Batch Comment Field None ATE: 12-04-96 TIME: 17:53:42
RAY ID TIME CPMA/K CPMB/K CPMC/K 2e%A 2e%B 7 2e%C A/B ESP FLAG 1.00 29.0 9.0 9.0 37.14 66.67 66.67 3.222 8 1.00 23.0 13.0 LCR1 33 4.0 41.70 55.47 **.** 1.769 LCR1 1 1.00 29.0 13.0 6.0 37.14 55.47 81.65 2.231 2 1.00 16.0 7.0 LCR1 7.0 50.00 75.59 75.59 2.286 LCR1 3 1.00 28.0 10.0 7.0 37.80 63.25 75.59 4 1.00 30.0 2. 800-- J90 LCR1 13.0 10.0 36.51 55.47 63.25 2.308 LCR1 5 1.00 18.0 7.0 6 10.0 47.14 75.59 63.25 2.571 LCR1 1.00 22.0 9.0 9.0 42.64 66.67 66.67 2.444 7 1.00 27.0 16.0 LCR1 8 1.00 9.0 38.49 50.00 66.67 1.688 LCR1 15.0 12.0 14.0 51.64 57.74 53.45 1.250 18 1 1.00 15.0 15.0 LCR1 2 1.00 10.0 51.64 51.64 63.25 1.000 LCR1 28.0 10.0 9.0 37.80 63.25 66.67 2.800 3 1.00 20.0 11.0 LCR1 6.0 44.72 60.30 81.65 1.818 LCR1 4 1.00 28.0 12.0 16.0 37.80 57.74 50.00 2.333 LCR1 5 1.00 19.0 11.0 7.0 45.88 60.30 75.59 1.727-Jfo LCR1 6 5.00 132.0 11.6 9.2 7.78 26.26 29.49 11.379 7 1.00 22.0 10.0 9.0 42.64 63.25 66.67- 2.200 LCR1 8 1.00 26.0 3.0 3.0 39.22 **.** **.** 8.667 LCR1 M2 1 1.00 30.0 9.0 3.0 36.51 66.67 **.** 3.333 LCR1 2 1.00 29.0 6.0 3.0 37.14 81.65 **.** 4.833 LCR1 3 1.00 4.0 19.0 7.0 45.88 **.** 75.59 4.750 LCR1 4 1.00 22.0 9.0 6.0 42.64 66.67 81.65 2.444 LCR1 5 1.00 21.0 12.0 10.0 43.64 57.74 63.25 1.750 LCR1 6 1.00 29.0 12.0 9.0 37.14 57.74 66.67 2.417 LCR1 7 1.00 23.0 14.0 4.0 41.70 53.45 **.** 1.643--200 LCR1 8 1.00 22.0 8.0 6.0 42.64 70.71 81.65 2.750 LCR1 !4 1 1.00 24.0 4.0 5.0 40.82 **.** 89.44 6.000 LCR1 2 1.00 20.0 8.0 2.0 44.72 70.71 **.** 2.500 LCR1 3 1.00 24.0 9.0 7.0 40.82 66.67 75.59 4 1.00 24.0 2.667 LCR'i 14.0 4.0 40.82 53.45 **.** 1.714 LCR1 5 1.00 20.0 8.0 6.0 44.72 70.71 81.65 2.500 LC21 6 1.00 33.0 11.0 7 1.00 10.0 34.82 60.30 63.25 3.000 LCR1 19.0 8.0 4.0 45.88 70.71 **.** 2.375 8 1.00 20.0 8.0 LCR1 5.0 44.72 70.71 89.44 2.500 LCR1 :0 1 1.00 25.0 8.0 6.0 40.00 70.71 81.65 3.125-310 2 1.00 19.0 8.0 LCR1 10.0 45.88 70.71 63.25 2.375 LCR1 3 1.00 22.0 8.0 5.0 42.64 70.71 89.44 2.750 LCR1 4 1.00 24.0 7.0 5 1.00 8.0 40.82 75.59 70.71 3.429 LCR1 15.0 7.0 2.143 6 1.00 6.0 51.64 75.59 81.65 LCR1 27.0 13.0 5.0 38.49 55.47 89.44 2.077 7 1.00 22.0 LCR1 13.0 3.0 42.64 55.47 **.** 1.692 LCR1 8 1.00 24.0 9.0 7.0 40.82 66.67 75.59 2.F67 LCR1 1 1 1.00 22.0 8.0 7.0 42.64 70.71 75.59 2.750 LCR1 2 1.00 34.0 9.0 4.0 34.30 66.67 **.** 3.778 LCR1 3 1.00 21.0 18.0 4.0 43.64 47.14 **.** 1.167-230 LCR1 4 1.00 21.0 12.0 13.0 43.64 57.74 55.47 1.750 LCR1 5 1.00 13.0 7.0 6.0 55.47 75.59 81.65 1.857 LCR1 6 1.00 19.0 4.0 6.0 45.88 **.***81.65 4.750 LCR1 7 1.00 23.0 2.0 4.0 41.70 **.** **.** 11.500 LCR1 8 1.00 17.0 9.0 6.0 48.51 66.67 81.65 1.889 LCR1 7 1 1.00 24.0 13.0 15.0 40.82 55.47 51.64 1.846 LCR1 2 1.00 21.0 2.0 3 1.00 1.0 43.64 **.** **.** 10.500 LCR1 26.0 8.0 7.0 35.22 70.71 75.59 3.250 4 1.00 22.0 9.0 LCR1 10.0 42.64 66.67 63.25 2.444 LCR1
...... - _ _ - _ _ _ CCH 4 PRGM: SURVEYS START TRAY: 6 RUNS REMAINING: Cont ' ORT FILE: None SPECTRUM FILE: None 1 MENT: Batch Comment Field E: 12-04-96 TIME: 19:11:04 \Y ID TIME CPMA/K CPMB/K CPMC/K 2s%A 2s%B 2s%C A/B ESP FLAG S 1.00 24.0 16.0 1.0 40.82 50.00 **.** LCR1 6 1. 500~ 39o 1.00 19.0 5.0 7.0 45.88 89.44 75.59 3.800 LCR1 7 1.00 21.0 11.0 9.0 43.64 60.30 66.67 1.909 LCR1 8 1.00 13.0 12.0 9.0 55.47 57.74 66.67 1.083 LCR1 1 1 1.00 20.0 10.0 2.0 44.72 63.25 **.** 2.000 LCR1 2 1.00 22.0 7.'0 15.0 42.64 75.59 51.64 3.143 LCR1 3 1.00 18.0 10.0 9.0 47.14 63.25 66.67 1.800 LCR1 4 1.00 25.0 7.0 3.0 40.00 75.59 **.** 3.571 LCR1 5 1.00 54.0 15.0 3.0 27.22 51.64 **.** 3.600 LCR1 6 1.00 17.0 9.0 4.0 48.51 66.67 **.** 1.889 LCR1 7 1.00 15.0 7.0 5.0 51.64 75.59 89.44 2.143 No Sample 4gyo LCR1 3 1 1.00 16.0 21.0 14.0 50.00 43.64 53.45 0.762 No Sample LCR1 No Sample No Sample No Sample No Sample No Sample No Sample
! l > . . . . _ ...... - -
GM: SURVEYS MODE: CPM C0 SNGL FEFEATS: 0 REPLICATES: 0 PM: 0FF %%e 8 5F (40 TIME TER3: 5.00 r= 1.00 %:,|E MMENT: Prooras Coseent Field d RAMETERS ' CHANNEL A CHANNEL 9 CHANNEL C 6(,, G ke, ...... - - ...... - . h SCRIPTION: LOW MED HIGH jg g( NSE: 1 - 19 20 - 168 169 - 2000 i CK6ND SUB 0 0 0 ESCT CNT: 0 0 0 W CNT REh 100 0 0 ILL-DVER CORR: B)A C)A C)B 0FF 0FF 0FF
C: HALF-LIFE: OFF 0FF OFF C: ASSAY DATE: 06-21-80 06-21-88 06-21-88
TCH 4 PRGM: SURVEYS START TRAY: 6 RUNS REMAIN!NS: Cont PORT FILE: None SPECTRUM FILE: None MMENT: Batch Caseent Field TE: 01-21-97 TIME: 12:30:23
AY ID TIME CPMA/K CFMB/K CPMC/r 2sIA 2519 2 SIC A/B ESP FLASa 6 1 5.00 8486.8 14.6 15.4 0.97 23.41 22.79 88.tti dM 2 1.00 15.0 17.0 7.0 $1.64 48.51 75.!' O.882 LCR1 No Sasole 4 1.00 3.0 4.0 2.0 18.88 88.88 tt.tt 0.750 LCR1 R-\ 5 1.00 9.0 9.0 8.0 66.67 66.67 70.71 1.000 LCR1
6 1.00 14.0 3.0 5.0 53.45 88.88 89.44 4.667 LCR1 7 1.00 13.0 6.0 6.0 55.47 81.65 81.65 2.167 LCR1 8 1.00 8.0 2.0 4.0 70.71 1I.II i1.II 4.000 LCR1 6 1 1.00 9.0 7.0 6.0 66.67 75.59 81.65 1.286 LCR1 2 1.00 15.0 5.0 6.0 51.64 09.44 81.65 3.000 LCR1 3 1.00 13.0 11.0 8.0 55.47 60.30 70.71 1.182 LCR1 4 1.00 16.0 4.0 2.0 50.00 t .ti I*.It 4.000 LCR1 5 1.00 17.0 7.0 5.0 48.51 75.59 89.44 2.429 LCR1 6 1.00 12.0 12.0 3.0 57.74 57.74 88.88 1.000 LCR1 7 1.00 11.0 1.0 2.0 60.30 88.II t8.It 11.000 LCR1 No Sa:ple r 1 1.00 9.0 10.0 10.0 66.67 63.25 63.25 0.900 LCR1 6-\ 2 1.00 15.0 6.0 4.0 51.64 81.65 18.18 2.500 LCR1 3 1.00 12.0 6.0 8.0 57.74 81.65 70.71 2.000 LCR1 4 1.00 12.0 6.0 7.0 57.74 81.65 75.59 2.000 LCR1 5 1.00 10.0 5.0 3.0 63.25 89.44 88.88 2.000 LCR1 6 1.00 10.0 2.0 4.0 63.25 88.It 88.It 5.000 LCR1 7 1.00 8.0 4.0 4.0 70.71 11.t: 31.It 2.000 LCR1 9.0 0 1.00 7.0 5.0 66.67 75.59 89.44 1.286 LCR1 i . . a4 ,a .. . . o. ., ,. 4. ,...... , , , . .
__ _ ...... - ______. ------. . .
1 1.VV c.V 3.V 0.V C1.0J IV il /V./l V./30 LLMA 2 1.00 3.0 4.0 2.0 70.71 1I.*I II.II 2.000 LCR1 3 1.00 0.0 8.0 4.0 70.71 70.71 1.t8 1.000 LCR1 4 1.0Q 15.0 7.0 9.0 51.64 75.59 66.67 2.143 LCR1 No Sasole (b.O C. o 8.0 en 47 20.1173,7/ 3,76 No Saeole No Sasole No Sasole ! 1.00 10.0 6.0 2.0 63.25 81.65 18.88 1.667 LCR1 C.- k 2 1.00 7.0 8.0 8.0 75.59 70.71 70.71 0.875 LCR1 3 1.00 14.0 7.0 5.0 53.45 75.59 89.44 2.000 LCR1 4 1.00 10.0 6.0 2.0 63.25 81.65 t1.1I 1.667 LCR1 5 1.00 15.0 16.0 7.0 51.64 50.00 75.59 0.938 LCR1 6 1.00 3.0 4.0 4.0 70.71 : . st,st 2.000 LCR1
4 'RGM: iURVEYS 57 ART TRAY 6 RUNS REMAIN!NS: Cent 7 FILE: None SPECTRUM FILE: None NT: fatch C:asent Field 01-21-97 IIME: 13:14:46
ID TIME CFMA/K CFMB/K CFMC/X 2sIA 251B 2s1C A/B ESP FLA6 7 1.00 15.0 8.0 9.0 51.64 70.11 66.67 1.875 LCR1 8 1.00 4.0 4.0 3.0 ft. I 88.st 18.18 1.000 LCRI 1.00 i 20.0 14.0 8.0 44.72 53.45 70.71 !.429 LCR1 2 1.00 3.0 9.0 5.0 70.71 70.71 89.44 1.000 LCR1 3 1.00 17.0 3.0 2.0 48.51 II.it 88.88 5.667 LCRI 4 1.00 15.0 6.0 8.0 $1.64 81.65 70.71 2.500 LCR1 No Sasole No Sasole No Saanle No Sasole 1 1.00 17.0 6.0 13.0 48.51 81.65 55.47 2.833 LCR1 D - { 2 1.00 7.0 7.0 5.0 75.59 75.59 69.44 1.000 LCR1 3 1.00 4.0 12.0 5.0 66.67 57.74 89.14 0.750 LCR1 4 1,00 4.0 6.0 5.0 18.88 81.65 89.44 0.667 LCR1 5 1.00 16.0 !!.0 4.0 50.00 60.30 88.88 1.455 LCR1 6 1.00 13.0 7.0 9.0 55.47 75.59 66.67 1.857 LCR1 7 1.00 9.0 10.0 8.0 66.67 63.25 70.71 0.900 LCR1 8 1.00 12.0 6.0 8.0 57.74 81.65 70.71 2.000 LCR1 1 !.00 5.0 7.0 3.0 89.44 75.59 18.18 0.714 LCR1 2 1.00 13.0 8.0 6.0 55.47 70.71 81.65 1.625 LCR1 3 1.00 12.0 7.0 6.0 57.74 75.59 81.65 1.714 LCR1 4 1.00 13.0 3.0 2.0 55.47 st.it it.it 4.333 LCR1 No Sasole No Sasole No Saaole
8 1.00 15.0 10.0 6.0 51.64 63.25 81.65 1.500 LCR1 .u,
_ _ _ - - _ _ _ 1 :nt By: WSU HEALTH PHYSICS 313 577 5579 ( 01/28/97 14:23 W JoD 426 Page 2/2
1H: ShRVW.C, MODE: CPM CO ?.NGI. REPEATS: 0 REPLICATES O PM: OFF 'IME TERM: G.uo K. !.nu IMENT: Program Comment Field ?AMRTERS CHANNEL A CHANNRI, B CllANNEL C ... . ---- ...... ------...... - - ;CRIPTION: 1.OW MED HIGH IGE: 1 - 10 20 'KGNIi Cull: 168 16.4 - 5:000 0 ti ' SET CNT: t O o O P CNT REJ: 100 (> U LL-0VER CURH: B.' A CsA C > t< OFF ' UFF OFF - HALF-LIFK; OFF - OFF 0FF ASCAY DATK: 0G-91-88 06 21-88 ut;-2t-88 CH 4 PRCM: CURVEYC START THAY: el nRT FILE: None RUNS REMAINING: Cont MENT: Batch Comment Ficid SPECTRI1M F 11.E : None E: 01 -2ti-9'I TIME- 13:06:37
Y Tb TTME i'PMA/K CPMB/K CPMC'K 2s,tA . :e.t Tt *:r%C A, U ESP Flhi 1 5.00 ;V/683. 0 17.6 11.2 Nc, :stmo ! e- U.46 21.32 20.73 ** .+4+ 1.v0 21.0 11.0 '/. % ''.N . Snmp *l ,- 43.84 t it i . :in '/ ' % l.009 LCH1 ', 1.00 10.0 6.0 10.0 b0.00 vu.7) Lt, 47 6 2.000 L.Ch1 1.9u io.o 12.u 5.0 63.20 &~T.74 0U.44 u.naa ~/ 1.00 i/O 8.o LCR1 8.0
i TL, Y1 ' 1 \ ter D L > d to, h
#s i vi . ec. t .M o ,. _ . . . . _ _ . _ _ _ _ - - .. .. . _ ...... , ...... APPENDIX V H-3 CONTAMINATION vs. DEPARTMENT of the ARMY "AR385-11" LIMIT 21 - # ~ ' *=7: 55 s"5- -7 !!!!!! < h ' * . , ' - j i t . g ,, ., ., S' @ , s u i # : '| s. i = :s- g ,. I < |g I g | L. ~ I : . LV 69 ,9 .9 S9 L9. 89 -...... 151 _ _ _ ------.. . - , APPENDIX VI CHARACTERIZATION SURVEY DATA > 22 | | .. .. _ _ _ _ Detroit Arsenal Tank Plant (DATP) Decommissioning Activity Characterization Survey LOCATION SAMPLE DATE AREA cm' dpm dpm/100 cma , UMIT (*/100 cm a, # 169 12.13.96 200 122.0 61.0 i 100 A1 01.15.97 200 0.0 0.0 i 100 A2 01.15.97 200 0.0 0.0 ; 100 A3 01.15.97 200 0.0 0.0 i 100 A4 01.15.97 200 0.0 0.0 l 100 A5 01.15.97 200 0.0 0.0 ! 100 - A6 01.15.97 200 0.0 0.0 i 100 A7 01.15.97 200 0.0 0.0 100 A8 01.15.97 200 0.0 0.0 ; 100 A9 01.15.97 200 1.8 0.9 100 A10 01.15.97 200 3.5 1.8 100 A11 01.15.97 200 0.0 0.0 i 100 A12 01.15.97 200 0.0 0.0 i 100 # 200 12.13.96 200 122.0 61.0 100 B1 01.15.97 200 0.0 0.0 100 82 01.15.97 200 0.0 0.0 100 B3 01.15.97 200 0.0 0.0 , 100 B4 01.15.97 200 0.0 0,0 ' 100 B5 01.15.97 200 0.0 0.0 i 100 B6 01.15.97 200 0.0 0.0 j 100 B7 01.15.97 200 0.0 0.0 i 1 00 88 01.15.97 200 0.0 0.0 i 100 89 01.15.97 200 0.0 0.0 i 100 B10 01.15.97 200 0.0 0.0 i 100 B11 01.15.97 200 0.0 0.0 ! 100 812 01.15.97 200 0.0 0.0 i 100 # 254 12.16.96 200 102.0 51.0 i 100 C1 01.15.97 200 0.0 0.0 100 C2 01.15.97 200 0.0 0.0 100 C3 01.15.97 200 0.0 0.0 i 100 C4 01.15.97 200 0.0 0.0 l 100 C5 01.15.97 200 0.0 0.0 i 100 C6 01.15.97 200 0.0 0.0 100 C7 01.15.97 200 0.0 0.0 100 C8 01.15.97 200 0.0 0.0 | 100 C9 01.15.97 200 8.8 4.4 ; 100 C10 01.15.97 200 0.0 0.0 1 100 C11 01.15.97 200 3.5 1.8 | 100 C12 01.15.97 200 0.0 0.0 1 100 # 351 12.17.96 200 201.0 100.5 | 100 D1 01.15.97 200 3.5 1.8 ! 100 D2 01.15.97 200 0.0 0.0 ! 100 D3 01.15.97 200 0.0 0.0 1 100 D4 01.15.97 200 0.0 0.0 i 100 D'i 01.15.97 200 1.8 0.9 ' 100 Appendix VI - 1 | ! . . . . _ . _ - ______- _ _-______- Detroit Arsenal Tank Plant (DATP) Decommissioning Activity Characterization Survey a LOCATION t SAMPLE DATE A REA cm - dpm dpm/100 cm' ! LIMIT (*l100 cm8 ) D6 01.15.97 200 0.0 0.0 100 D7 01.15.97 200 0.0 OL 100 D8 01.15.97 200 0.0 0.0 100 D9 01.15.97 200 0.0 0.0 100 _ D10 01.15.97 200 0.0 0.0 100 D11 01.15.97_ 200 0.0 0.0 100 D12 01.15.97 200 0.0 0.0 100 Appendix VI - 2 1 APPENDIX VII FINAL SURVEY DATA : 23 ...... _ - _ _ _ _ _ .. Detroit Arsenal Tank Plant (DATP) Decommissioning Activity Final Survey ORIGINAL FINAL SURVEY SAMPLE POST DECONi AR385 11 LOCATION f dpm/100 crE8 ' 8 8 8 DATE AREA cm ! dom /100 cm ! LIMIT (*/100 cm ) # 169 61.0 4 01.28.97 200 0.0 > 100 dpm ' ' # 200 61.0 01.28.97 200 O.0 i 100 dpm # 254 51.0 01.28.97 200 ' O.0 100 dpm # 351 100.5 01.28.97 200 c 0.0 | 100 dpm Appendix Vil - 1 ! ._ .- APPENDIX VIII DEPARTMENT of the ARMY PERMIT AUTHORIZATION 24 - ______- __ -- . . E2hiIs DEPARTMENT OF THE ARMY - gF//y AUTHORITY FOR POSSESSION AND USE a OF RADIOACTIVE MATERIALS *n reliance on statement anc representat;:n ace cy the apcit: ant. transfer, possess, use, ano s t:re t..e .a t e ria. ( s i authority is herecy grantec : spect!iec below. cesignatec 'n. ..em 5. receive. A rc=uce This authority is sucJect i: ::n::"L ks l. ACTIVITY GRANxw AUTHORIrr 3a. ._ General Dynamics Land Systems Division AUTHORITY / PERMIT NUMBER P21-21-21068-01 Amendment 01 3b. DOCIET NUMBER 2. Central Office complex 38500 Mound Road . Sterling Heights, MI . 48078-2268 4 EXPIRATICN DATE 31 January 2000 5. MATERI.'.L 6. CHDiIc11. AND/OR 7. PHYSICAL. FORM QUANTITY LIMITATION NOT TO EXCEED PER ITEM TOTAL a. Thorium 232 a. The:ium Fluoride a. No single source to Cptical Ceated Lens exceed 56.34 nanecuries (Hughes Aircraft, Inc., (ncil per unit (30 P/N 122821401 percent.by weight) b. Tritium (H-3) -b. Tritium. Gas in a b. 300 units, maximum sealed glass ampeule activity en-hand is 3000 (Self Powered Lighting.- Corp. or.Mb-Micretec, curies (C1). No single Inc.) scurce to exceed 10 Ci c. Thorium 232' c. Therium:Dicxide in c. No single source to Magnesium / Nickel .'.110y exceed 2.0E-03 (AVCO-Lyceming, ?/N microcuries (uCil per 12286890) gra:n (4 percent by weight) d. Uranium 238 d. Metal encased . d. As'needed 42epleted Uranium) Stainless steel 8. AUTHORIIED USE: a. primaryUssd as sight an inanti-reflective ABRAMS Tank. coating on lens of enermal imaging system of the gunner's b. Used as a light source in the Mu:cle Reference senser (Cell Assembly 12304725). c . Used for assembly only of the C :.custer Liner :f -he M1 Tank series turbine engine . d . Used f:r manufacture of MI Abrams Tank system turrets and bal_istic test targets, and f:r display, demonstratien, maintenance and noncestructive :perational testing . Page 1 of 5 __ ~ Page 2 of 5 DEPARTMENT OF THE ARMY AUTHORITY FOR POSSESSION AND USE OF RADIOACTIVE MATERIALS SUPPLMENTARY SHEET Authorization / Permit No. P21-21-21068-01 _ Docket Number: 0030 5. MATERIAL 6. CHEMICAL AND/CR 7. PHYSICAL FORM QUANTITY LDfITATICN ] e. NOT TO EXCEED PER ITEM TOTALi Uran um 239 e. Sealed Scurce e. (SN: 07) Cne source, total activity is 6 mci f. Uranium 239 f. Electreplated Nickel f. Two sources, maximum (Eberline Model CNS-4SP) total activity is 3.5E-4 uCi 7 Tecnnicium 99 g. Electreplated Stainless g. One source, total Steel IEberline Model 54) aetivity is 2.1E-3 uCi h. Strentium 90 h. Electreplated Nickel h. Two sources, maximum (Eberline Model total activity is 5.7E-4 ONS-3SP) uCi 1. Cesium 137 :. Sealed Scurce (Eberline i. Three sources, maximum Model Cs-7A, Cs-7B and total activity is 15 uCi Victureen Model 06-201) 3. Tr : um (H-3) , :. Tritiated Plastic j. One source, total i : Amersham Corp., Model | activity is .27 uCi TRR16161) 8. AUTHCRIZED USE: e. Jsec in a varian Linatren 220 Radicgraphic Linear Accelerater . f. Used as check scurces. g. Osec as a check scurce, t. Usec as check scurces. . The Iberline scur:es are usec as des: meter :alibrater for s:crage onlycheck sources, while the Victoreen is used in a . Usec as a :heer. scurce. i _ . _ _ - - - - __ ._ .. ______ Page 3 of 5 * DEPARTMENT OF T.HE ARMY AUTHORITY FOR POSSESSION AND USE OF RADIOACTIVE MATERIALS SUPPLMENTARY SHEET Authorisation/Permi+: No. p21-21-2106a.01 __ Docket Number: 0030 5. MATERIAL 6. CHEMICAL AND/OR 7. _ PHYSICAL IVRM QUANTITY LIMITATION NOT TO EXCEED PER ITEM TOTAL k. Varian Linatron 200 k. 2.2 MeV Radiographic Linear SN: -07 k. One linear accelerator Accelerator 1. Phillips MG 420 1. 420 kV, 10 mA Industrial X-ray System '.. One industrial X-ray SN: 005189 system , m. General Electr:,c ::XD i m. 150 kVp, 300 =A 350-I2 X-ray Unit with m. Cne meci:a1 X-ray system SN: 41922X General Electric MAXIRAY 75 X-ray Tube n. UX Universal EZMatic n. 125 kVp, 300 :-A Super 25 X-ray Unit n. One medical X-ray system with Linear 1 X-ray SN: F056079 Tube 8 . AUTHORI::ED USE: k and 1. Used at Lima Army Tank Plant t: Inc. (DARP F34-120062207 LATP:. perf:rm industrial raciegraphy b. MQS :nspection, jm and n. Used for stcrage only at Lima Army Tank Plant and Dete:it Army Tank Plant, respectively, pending final disp:siti:n er transfer of the equipment. . ...... .. .. . . _ _ _ _ _ Page 4 of 5 ' DEPARTMENT OF THE ARMY AUTHORITY FOR POSSESSION AND USE OF RADIOACTIVE MATERIALS SUPPLMENTARY SHEET ' Authorization /PermAt No, p21-21-21068-01 Docket Numbers oc f, CONDITIONS 9. The Radiation Safety officer for this authorization is Mr. GDLS, or DLA, ATTN: Boyd H. Rose, 419-221-8858, DCMDN-GJCG (DATP), DSN 786-8781, or DCMDN-RQT (LATP), DSN 850-6064. 10. The authorized place of use is any facility under the direct Pl ant , CH and Detroit Arsenal Tank Plant, control of Lima Army Tank MI operated by General Dynamic Land Systems Div. 11. identified in Item 9 above.Authori:edAddi: material will be ut:11:ed under the supervisionuals of the individ training and education must 1=nal users may be approvec locally. The individual's stated in Items 5, 6, and 7 above.be commensurate with the radioactive material being used as requirements.responsible for ensuring all user personnel meet minimum training and educationThe individuals identified in Item 9 above will be office. All users ' personnel credentials will be made available upon requests by thi 12. Notify CECCM, ATTN: AMSEL-SF-RER, Commarcial 908-427-3112, or Facsimile Fort Monmouth, NJ 07703, DSN 987-3112, 908-542-7161, within 60 days of a change int a. The Radiation Safety officer identified in Item 9 above. b. above.Ownership and/or the location / address of your organi:ation, as identifi d i e n Item 2 under this document will include the13. P.aquests for termination, disposal or transfer of any radioactive material auth following information as applicable: ori:ed a. A description of the material being transferred, the name of the authori:ed recipient the pending date of the transfer, number. and the recipient's authori:ation/ permit b. A description of the radioactive material authori:ed anc..r requiring disposal radiationactions, thesurvey. specific disposal procedures, and the results of the closecut contamination remains on the premises.The purpose of the closecut survey is to determine whether any 14. f If there is radiological contaminatien as a result of authori:ed operations ae:.11 ties will be dec:ntaminatec by the organization identified in Items 1 and, 9Army abov 15. e. s tate / local release criteria for unrestricted use. Army property will be restored to pre-operational conditions that meet NRC and/or 16. decontaminationThe user requirements.will be respensible for ensuring funds are available to conduct all necessary 17 . Copies of this document jldentified in Items 1 and 9. and any amend::.ents will be retained by the organi:ations 13. 385-1.All authori:ed material will only be disposed of IAW AR 385-11 and AMCCCM Pamphlet s .. . . - - - - . Page 5 of 5 DEPARTMENT OF THE ARMY AUTHORITY FOR POSSESSION AND USE OF RADIOACTIVE MATERIALS SUPPLMENTARY SHEET ' Authorization / Permit No. e21 21-21068-01 _ Docket Nt=%r: 0030 _ CONDITICNS (CONTINUED) 19 Unless specifically provided otherwise, shall be possessed and used IAW statements, the materials described in Items 5, 6, and 7 representations, DA form 3337 application cated 10 November 1995, signed by Mrand procedures centained in the Protect:.cn Officer, GDLS, LATP: . Boyd H. Rose, Radiation expiration date 31 January 1999; NRC License No. Nuclear Regulatory Cerrmission (NRC) 21-21068-01, License No. SUB-1564, Army Materiel Command Regulaticn expiration date 31 March 2000; Perm t (AMC-R) 385-25 and Army Regulatien (AR) 385-11. This P21-212106801-DATP,supersedes DAdated Perm 14 Septemoer ts P21-12-02, 1995. 03, 05, 06; P21-LATP-12-01, 03, 07, 08; and i o APPROVED -_ . P ( 'f f ( .I FATE: 3/ I'M Q $5ik E '' ~ JOHN E. RANKIN _ Chief, AMC Safety OffiC8 ______------