ML20097J519
| ML20097J519 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 12/20/1994 |
| From: | CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC |
| To: | |
| Shared Package | |
| ML20097J517 | List: |
| References | |
| NUDOCS 9602020232 | |
| Download: ML20097J519 (52) | |
Text
{{#Wiki_filter:._ . .. _ . - _ - . .. . . CUA TIIE CATIIOLIC UNIVERSITY OF AMERICA d Radiation Sqfety Office i H'ashington, D.C. 20064 202-319-3206 a J REACTOR DECOMMISSIONING REPORT E FINAL STATUS SURVEYS i i 4 ) .i 4 1 d 9602020232 941220 PDR ADOCK 05000077 W PDR
1
. TABLE OF CONTENTS PAGE List o f Figu re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i List o f G rid M ap s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . il
1.0 BACKGROUND
INFORMATION 1.1 Facility H istory . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Fac ility Cl osu re . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.3 C UA Schedules and Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 2.0 SITE DESCRIPTION 2.1 S i te Locati o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.2 Facility Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 3.0 OPERATING HISTORY 3.1 General Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.2 Operations Performed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 4.0 DECOMMISSIONING METHODOLOGY 4.1 Objective Implementation and Decommissioning A c t i v it i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.2 Preliminary Surveys ... a 5.0 FINAL STATUS SURVEYS 5.1 S u rvey Des i gn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 i 5.2 S u rvey Read i ng s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5.3 Final Contamination Measurements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5.4 Exposure Rates at 1 Meter from Floor and Imwer Wall S u rfaces. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5.5 Instrumentation Used . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 6.0 SURVEY FINDINGS / COMPLIANCE CRITERIA 6.1 Final Status Survey Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 6.2 Compliance Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 6.3 Comparison of Final Status Survey Results to Compliance Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Appendices: Appendix A Reactor Room Iewer Surfaces Data Upper Surfaces Data Structurals Data Appendix B Reactor Pit Lower / Upper Surfaces Data Reactor Tank (Shell)
- - - - -- -- =
i List of Finures l t Figure 1 location of The Catholic University of America . Figure 2 Campus Map General Figure 3 Campus Map - Reactor Location , Figure 4 Reactor Room - B16 R Pangborn Hall [ Figure 5 Summary Sheet, Radiation Exposure Rate Analysis Figure 6 Summary Sheet, Surface Contamination Analysis 4 t t i i 5 4 d i l 1 i 1 i l
List of Grid Ma.g Grid Map A-1 Reactor Room Grid Map B-1 Reactor Pit 1 i
i
1.0 BACKGROUND
INFORMATION
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1.1 Facility History i , The Aerojet General Nucleonics (AGN) Model AGN-201 reactor, Serial Number 101, came to The Catholic University of America (CUA) in October, 1957, under an educational grant from the Atomic Energy Commission - following its around-the-world trip as a demonstration reactor under President Eisenhower's " Atoms for Peace Plan." It was primarily used as a training reactor for degree candidates within the University's Nuclear Science and Engineering Department. The original start up operation team for Baltimore Gas and Electric's Calvert Cliffs nuclear power plant was also trained on this reactor. The application to acquire and possess an AGN-201 nuclear reactor was filed by CUA on July 10,1957 and amended on August 23 and November 13, 1957. Pursuant to License No. R-31, issued November 15,1957, an AGN-201 reactor, Serial No.101, was acquired from the Aerojet-General Nucleanics Corporation. The original license was for a period of twenty years , and specified a maximum the: mal power of 0.1 watts. Initial criticality was achieved on November 20,1957. ' s The license was renewed on March 14,1979 which extended the operating authority to 1997. However, in March 1986 reactor status was changed to i i possession only. The reactor has been shut down since 1982. , i 1.2 Facility Closure : i The reactor was defueled on March 17,1990 under a NRC approved defueling ; plan. The fuel was secured in safe storage on site. i By applications dated February 6,1992, CUA requested authorization to i decommission and dismantle the reactor and to dispose of the component parts,
- in accordance with the Decommissioning Plan for the AGN-201 Research Reactor submitted as part of the application.
3 ~ On September 24,1992 the Commission issued the order that approved the [ Decommissioning Plan and authorized decommissioning of the reactor in ! accordance with the application and Decommissioning Plan. : i 1.3 CUA Schedules and Objectives CUA has worked to an end of the year deadline for the completion of the < decommissioning work necessary to meet the objectives outlined below. This , revised deadline has been influenced by several factors, the most significant of ! which was the extensive planning and preparations required before receiving : 1
- 1.3 CUA Schedules and Objectives (con't) authorization to ship the reactor fuel to an off site government facility. This shipment was completed on 9-12-94 In addition to the scheduler goals, CUA's Decommissioning Plan objectives are:
- 1. To decontaminate and decommission the reactor room facility in order to permit release for " unrestricted" use.
- 2. To accomplish the work in a safe and environmentally acceptable manner in accordance with all applicable federal and District laws and regulations
- 3. To minimize the volume of waste requiring burial. ,
- 4. To maintain exposures As IAw As Reasonably Achievable (ALARA) and,
- 5. To meet the above objectives while performing the work in the most ,
cost effective manner practicable, j 2.0 SITE DESCRIPTION , 2.1 Site Iecation The 154 acre CUA main campus is located in the NE quadrant of the District of Columbia, bounded by Michigan Avenue, Harewood Road, Taylor Street, ' and John McCormick Avenue. Figure 1 locates this quadrant. CUA was founded more than a century ago as a graduate institution and research center in the European tradition. The university enrolls ! approximately 3600 graduate students and 3000 undergraduates representing most of the states and more than 100 foreign countries. (Figure 2 shows a general layout of the main campus.) The reactor has been permanently located in the Pangborn Building (Engineering and Architecture) in the nonh wing of the basement level since 1%7. Figure 3 highlights the location of Pangborn Hall, on an older map for ease of reading. 2.2 Facility Description The licensed nuclear reactor facility area consists of one room in Pangborn Hall identified as Room B-16R. The AGN-201 reactor was designed to be a totally self-contained system. There was no auxiliary equipment associated with the reactor, nor was any ventilation system required. The reactor facility consists of a steel tank, approximately 7 feet in diameter by 13 feet high, which houses the reactor and its integral shielding. This facility was in a pit,13 ft. by 13 ft. by 6.5 ft. deep, in the north end of the room. There is no 2
2.2 Facility Description (con't) l floor drain in the reactor pit. This type of reactor was designed as a sealed ) system and, when operated, did not generate any gaseous or liquid radioactive i effluent. Figure 4 shows B-16R and the surrounding areas. ! l Access to the reactor core could only be obtained from the top access plate to the thermal column and then only with the use of considerable heavy j equipment and riggers to lift out the thermal column vessel and a second steel l vessel containing the reactor core and its lead and graphite shielding. Access j to the reactor core was never authorized in the operational tech specs. The reactor has been' stripped of all component parts such that only the steel tank remains in the pit. The reactor operating console has been disconnected and removed from the room. A catwalk around the tank perimeter and a safety railing around the pit remain in place. 3.0 - OPERATING HISTORY 3.1 General Information A review of the reactor operating logs, covering all operations at CUA (1957-1982) shows that the reactor was critical for approximately 610 hours, during which time approximately 971.9 watt-min (16.2 watt-hr) of thermal energy was generated. The reactor was licensed at CUA for a thermal power level not to exceed 100 milliwatts. It has been operated intermittently at all licensed power levels. The average power level over all operating time at CUA (16.2 watts-hrs + 610 hrs) is approximately 27 milliwatts (thermal). The reactor was last operated on December 4,1982, for a total of 71 minutes. 3.2 Operations Perfoaned The reactor was operated first by the Department of Nuclear Science and Engineering, and subsequently by the Department of Mechanical Engineering, for training nuclear engineering graduate students. The reactor usually was operated in conjunction with a Nuclear Reactor Laboratory course and used , primarily for performing basic reactor physics experiments requiring a low flux level. The inherent design features on this reactor, the low power level at which it was operated and the low accumulated mnning time precluded any significant buildup of fission products. No unusual problems have been identified during over 20 years of authorized operation. 3
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4
'4 4.0 DECOMMISSIONING METHODOLOGY ,
I 4.1 Objective Implementation and Decommissioning Activities In order to realize the objectives defined in 1.3, CUA has planned and , implemented decommissioning activities incorporating: e Removal of the thermal shield, lead shielding, graphite reflector, fuel j -and all drive mechanicsms and associated reactor mechanical parts. > e Removal of all cinder blocks used for seemity enhancement. e Removal of reactor console, furniture, and support equipment. - o Cleaning of all surfaces. 4.2 Preliminary Surveys i l Routine radiation surveys, required during reactor operations, have not i detected any contamination. These surveys were continued subsequent to
- defueling and continued to show no evidence of contamination. All
- disassembled reactor components have been surveyed and dispositioned in
. accordance with the approved decommissioning plan. No fixed or removable . contamination was identified. Preliminary surveys taken for removable contaminiation on floors, upper l surfaces and the reactor tank did not show any results above background. i , i e ! 5.0 FINAL STATUS SURVEYS 5.1 Survey Design l In preparation for the final status surveys, the reactor room has been divided l into two subunits: (1) lower surfaces, comprised of floor surfaces, wall l surfaces up to a height of 2 meters, and any other surface easily accessible to a technician standing on the floor; and (2) overhead surfaces, comprised of ceiling surfaces, wall surfaces more than 2 meters above the floor, and all other surfaces not described in (1). i l The floors and lower walls have been divided, using a rectangular grid system, j into one by one meter areas. In this report, the blocks formed in this manner ! are referred to as " survey blocks" and the corners of the blocks formed by the j j intersecting lines are referred to as " grid points." ; i 4
5.1 Survey Desij;n (con't) ; The reactor steel tank and its support structure are the only reactor components remaining in the room and remain in the pit previously described. The catwalk and pit railing remain in place for safety purposes. The surfaces have been divided into approximately 1 meter square blocks, using grid point locators, and surveyed. i 5.2 Final Status Surveys The approved decommissioning plan described the following termination radiation surveys to be taken: In the reactor facility, all surface areas larger than one square meter will be marked off in a grid of one meter square blocks. The survey will include a wipe sample of 100 cm2(nominal) taken within each block to identify removable contamination. Wipes for each grid location will be counted for alpha and beta contamination. Limits for removable contamination will be 200 dpm/100 cm 2(beta / gamma) and 20 dpm/100cm2 (alpha) (RG 1.86). A beta-gamma survey also will be performed cen'.ered on each block at a distance of one meter from the surface. Residual radioactivity will be considered acceptable if i measurements so-made are not more than 5 uR/h above background, where the reference background value is obtained as the highest of corresponding measurements of similar structural material made elsewhere in Pangborn IIall. In addition to the above described surveys, direct reading measurements for j surface alpha and beta / gamma contamination were taken on lower surfaces. Operating history, past routine surveys, preliminary scans, and the final status l surveys described above, provide demonstrable evidence that there is no reason l to suspect surface residual activity exceeding 25% of the guideline values on floor surfaces. . Therefore, a statistically significant number of grid blocks have been directly surveyed (at least 30 grid blocks) to assure reasonable coverage of these surfaces. . For upper surfaces, a minimum of 30 measurement locations were surveyed, biased to locations where radioactivity, if present, would be most likely to accumulate. t 1 5 :
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5.3 Final Contamination Measurements 5.3.1 Fixed Beta / Gamma Measurements Fixed beta-gamma readings were taken within designated grid blocks. A static count for 1 minute was converted to dpm/100 cm2 by taking the net counts and multiplying by a factor which corrects for 4 pi efficiency of the probe and the active area of the detector. Effective window area for this probe is approximately 12 cm2 . The minimum detectable level, based on typical background counts of 20-40 cpm for this detector, is approximately 980-1200 dpm/100 cm2, 5.3.2 Wipe Measurements Wipe measurements (indirect surveys) were performed using numbered filter paper disks which were then placed in labeled smear booklets with the ; item / location recorded. Each wipe was counted in a low background gas proportional counting system. The minimum detectable activity calculated for this system as set up for processing these smears is approximately 10 dpm where there is a 5% chance that a smear with this activity will be counted as less than the MDA and a 5% chance that the smear with zero activity will be counted as exceeding the MDA. 5.3.3 Fixed Alpha Measurements Measurements for fixed alpha activity were performed in designated grid blocks. Static 1 minute counts were converted to disintegration rates (dpm/100 cm2 )by multiplying the net CPM by a factor which corrected for the 4 pi efficiency of the probe and the active area of the detector. Effective window area for the alpha probe was approximately 50 cm2, i The minimum detection level for this alpha probe coupled to scaler /ratemeter ' and operated in the scaler mode is approximately 100 dpm/100 cm 2 j 5.4 Exposure Rates at 1 Meter From Floor and Lower Wall Surfaces 5.4.1 Establishment of Background Radiation Exposure: In order to insure that the final radiation survey is based upon appropriate levels of background radiation, an area of similar materials of constmetion and configuration, known to be free of any potential contamination were selected for measurement evaluation. The same instmments used for the final survey were used to constmet a series of background readings. These readings were then averaged for each selected area. 6
l I l , l . l 5.4.2 Establishment of Decommissioning Area External Radiation Exposures ' l External radiation surveys were conducted in survey units identified in this ^ report as the Reactor Room and Reactor Pit (Appendix A), and (Appendix B), respectively. As described in 5.2 a reading was taken centered over each grid block at one meter above the surface using a micro-R scaled ratemeter. For those floor survey blocks adjacent to walks, the measurement was taken at the appropriate grid point which maintained a 1 meter distance from the wall. 5.5 Instrumentation Used Direct Radiation Measurements Ludlum Instrumentation CorDoration, Santa Fe, New Mexico e Model 3 Survey Meter e Model 12 Survey Meter e Model 19 Micro R Survey Meter e Model 43-2 Alpha Scintillation Detector e Model 43-65 Alpha Scintillation Detector e Model 44-9 " Pancake" G-M Detector e Model 2221 Single Channel Analyzer, Scaler /Ratemeter Indirect Measurements Tennelec. Incorporated, Oak Ridge, Tennessee e Model LB 5100 Low Background Counting System 6.0 Final Status Survey Results Compared to Compliances Criteria 6.1 Final Status Survey Results The final status survey results for the reactor room (Pangborn B16 R) and the reactor pit / reactor steel tank, located within this room, have been grouped separately and are attached to this report within Appendix A and Appendix B respectively. 6.2 Compliance Criteria The decommissioning criteria for surface contamination has been established in
. the decommissioning plan and NRC Regulatory Guide 1.86. The decommissioning criteria for external exposure measured at I meter from surfaces has also been established in the decommissioning plan and for this facility can not exceed 5 micro-R/ hour gamma above background.
7
6.3 Comparison of Final Status Survey Results to Compliance Criteria The survey data in Appendix A and Appendix B verify that final residual surface contamination and external radiation levels measured at I meter from surfaces meet the acceptable compliance criteria as specified in the approved decommissioning plan and NRC Regulatory Guide 1,86 titled " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted ; Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material. The general surface activity and exposure rate guideline values are average i values, above background, established for areas of survey unit surfaces and indoor exposure rates. In order to compare survey data with the guideline limits, the mean of each type of measurement taken on lower surfaces,(reactor room and pit floors; reactor room walls up to two meters and all pit walls) has been calculated using all measurements taken on those lower surfaces. Figures 5 and 6 illustrate this comparison.
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SUMMARY
SHEET RADIATION EXPOSURE RATE ANALYSIS (uR/hr at 1 Metor) SURVEY UNIT EXPOSURE RATE ABOVE COMPLIANCE ^
' BACKGROUND AT 1 METER LIMIT uR/hr uR/hr i
J REACTOR ROOM 0.3 5 REACTOR PIT 0.0 5 j. I i i
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SHEET' SURFACE CONTAMINATION ANALYSIS . DPM/100 CM2 SURVEY UNIT REMOVABLE REMOVABLE FIXED FIXED BETA' ALPHA BETA / GAMMA ALPHA + LIMIT 200 20 5000 5000 ; t lREACTORRM 2 1 62 8 l ; b b
P I APPENDIX A REACTOR ROOM FINAL' STATUS SURVEYS
. I
Reference:
Grid Map A-1 PAGE
- Lower Surfaces-Indirect Measurements Al--A8
*.- Upper Surfaces-Indirect Measurements A9--A11
- Lower Surfaces-Direct Measurements A12--A13
- Lower Surfaces-External Radiation at 1 Meter A14--A17 I
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- 1. ...r,.... . . . - . a cwE m m.s c00xts c0usts crn een c0ntcica etwieru
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, H.EALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE BA M ROUN0= A CUA'G COUNTER NWBER EFF. FACTOR
- 8 i
TEU 50V 17, '9H Object or hea Sw veyed l GkogP A F]NA1. STATUS $UiVLY REACT 0k ROOM: R0W C I du b WCf.S SAKPLE TIEi. A;.FRA BETA ALUA (CA- AlisA EUA l SN CODE (MIN.) COUMS COUMS Cr.1 015 C0kkEC'D CGILC's.. i l
- 0 1.00 1 1 0.60 0.40 . 6666667 1.1 M 706 l CN M M i 1.00 0 0 0.40 -0.60 '.. ulun ; .7647eM l C 2 ;.00 0 0 -0.40 -0.60 . . n!'. 11 ..M16 '
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IEI h0V 18, 19% Gi(0UP A FINAL STATUS SURVEY REACTOR ROOM: R0W E SURV!Y l'LOCf.S SAMPI.E TIri ALMA cdLVmW SN CODE (MIN.) COUN*S BETA ALP!:A EE!A ALEA LETA COUNTS CPM Cit /EC"R N EEC7D [ ~ ~ ' - CPM I
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- e
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-4 ,
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5 1.00 0 1 0.40 0.40 -1.1111111. 1.1h470e
= 6 ;.00 0 4 -0.40. J.40 -1,.111111; 10 1
fn: h0V 18,1H4 GLOUP A FINAL L Al!!S SilkVEY LEl.0".0R ROOM: kOW G St'KVl! liOCf.2 l 1 si:A SAMFLE ::ME ti.f.E A BETA ALPi:A ECA A:.LiA C d). d M N "M " '" " 'b # # C #C'* U ***' b 'O . 00 0 1 -U . 4'. 0.40 ;.;.;11.. 4.;7:47%
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- kOW 11 St'RVLY BLOCKS C O A.v M A/ ' EAMPLE f!ME ALPHA BETA ALPHA BETA ALPHA EEIA g ; EN CODE (MIN.) C0!NTS C0l'NTS GM Cils 00KELCliD C0ketCID 0 1.00 1 0 0.60 -0.60 1.6(66t67 -1.764705 !
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. HEALTH PHYSICS COUNTED BY _ DATE
,. SMEAR SURVEY RECORD SURVEYED BY DATE-
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- s
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o HEALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE COUNTER NUMBER BACKGROUND *- .A CUA . EFF. FACTOR * # RE$C.TCB A00M WALL 3 _. VCU LEC 07, ;ys4 Object or Area Surveyed GROLfP A hekhi bAi.1.: L0kk SUkrAOLS, L0bER 150. METEk PLOCES ktACT0k EXT M@dTN ; AMPLE Iitt ALFhA EEIA ALffiA PETA AlhA ECA 0NW '" C0'I 2" > c S$25 c"t'* S (F" "'" "'kIch ' x F* -
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._ t .. 1.00 0 0 -0.40 -0.tv -1.1:1 11 ;1.764059 i
. 7 1.90 0 3 -0.40 2.40 -1.111:1"1 . 7.05HD5 i L. 1,00 0 0.4e 0.tv -1.1;;;.:. -1.7K!So '
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COUNTER HUMBER BACKGROUND
- f h'
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- A l
CUA. ' EFF. FACTOR * ,8 06Jector Area Sur veyed M0 LEC 07. hs4 g p payg Gioi? 1. 50U1:1 #LL: 1/.%.R 5'AFi.O.:.. [As?Li. II!E A!.r . A h.IA l.J dA : :.IA A!..-i l> illi-0 40W :s cc.E is!k.; c0;tt 00'.rr cis CfM CWdiCID t%dEC~.D
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~1g 0 1.00 0 0 -0.40 -e.ou :.:21:211 - .n4:09 4 1.00 0 2 0.40 1.40 -1.1111111 4.117:471 5
1.00 0 2 -0.40 1.40 -1.1111111 4.11764?1 1 6 1.00 0 1 -0.40 0.4C 1.111'. ;U ..r/e47e6
^=
7 1.00 0 0 0. 4 '.) - 0. e t' 1.1111111 -1. /64 /0h 6 1.00 1 2 0.60 1.40 1.et6Hol 4.;17:471 y 1.00 . 2 0.60 1.49 1.66fofei 4.117:57 ; nu it?.' O. 394 sovTH set 9 b smi aLL: .m v.wA1:. .m . r.'. mi.k rLusEacn < kw . l A 0 y/ SAMP' E ?!EE A* Fi A ka'A ALFHA 6 ETA A;.PliA itu Sil COM (MIN.) COURS COUNTS CPM C1'M CORKECID C(tE!CfD 4 O0i 8 10 1.00 .! 0 1.60 -0.60 4.4444444 -1.7647059
-{g 11 1.00 1.00 0 0 0.40
-0.40
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- ' ;.00 t 2 -0.40 .90 ...;1:111 s... r4E M 1.00 0 2 -0.40 1.40 -1.1111111 4.11h4/; ;
ri 1.00 . e i.bv 1.4u 4.4944444 4.11764'/; 3 1.0J 0 2 -U.40 1.40 -1.1111111 4.1176471 x T""~ i)' 3' lz'4 41
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EFF. FACTOR * # Object or Area Surveyed ' iED i>EC (7. ;i94 , WEU ' GRU 'L 't-: nd!2; /'It N %1i:'*:> - E A?.si.t '.'l P.t a rhA ih4 A;.rrih :d:A n.n.r. t r. . i. O SN CO. r. tMih.i COU576 CMS!S CM C f.". Ahici:..- d r. ;:.;;
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, 25 . 0) 1 ; 3.t0 0.40 ..etett/ 1.1/t470t 25 1.00 3 e 2.t ' . 4e . . . - . _ . . 4. . . *4 4' 27 1.00 0 ; i.0 0.4; ......;.. 1.;/cs/0e 26 1.00 0 1 0.40 0.40 -1.111n1; 1.1764700 29 :.00 $
t . t '. . 40 .tttet 5.;17es7; Jc. 1.0? O ; 3.t . 47 ... .. . 4.1144*i; i ' i. I EE; DEC 07, ;% 4 NN Gh0'JF A 'ed!? iCL: LFiEk dhfA:i!. EFrik . .L .%u :;.S h-dA . - i' l ~ 8O M
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I Upper Surfaces-Indirect Measurements SN Reference to Grid Area-Item Survey 1 A0 Top steam line 2 A0 Air line pipes 3 AO Light fixture 4 Al Air line valve 5 A2 Steam pipe 6 A4 Top of door ledge 7 A5 Faucet 8 A5 Alarm bell 9 AS Coiled wires 10 A8 Fire extinguisher 11 A8 ADT box 12 A8 Steam line support hanger 13 A9 Top of door ledae 14 A9 Exit sign 15 A10 Top of pipe hanger 16 C10 Power box 17 D2 Light fixture 18 DS Light bulb fixture 19 I3 Power line 20 I4 Radiator 21 IS Air conditioner 22 I7 Gas lines 23 Il0 valves 24 F10 Ceiling 25 B4 Ceiling i 26 B9 Ceiling 27 G5 Ceiling 28 H7 Ceiling 29 I2 Window sill l l A9 i
9 30 I6 Window sill 31 18 Window frame 32 Il0 Window frame 33 EO South wall above 2 meters 34 IO South wall above 2 meters O V A10
. HEALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE-gg' COUNTER NUMBER EFF. FACTOR
- g BACT,GROUN0= d ;_; ,
+
R E AC T C A' U fPK R A00m S V R F ACCS
)
Object or Area Sur'veyed .- fiil DEC 09, 1994 Gi:OilP A Upper Surf aces: Incacci bu:veys-Celling /Wala/structurais LAEPLE iiME ALFEA EETA ALPEA 6 ETA AI.FEA 6 ETA SN CODE (Mih.s COUNTS COUN75 CFM CPM Ct%ECTED C0hEch11 i 1.00 1 0 6 0.40 5.40 -J.1111111 15.68235.5 1 2 1.00 0 2 -0.4u 1.40 -1.11:1:11 4.11766'/;
! 3 1.00 1 0 0.60 -0.60 1.6e6ct67 -1.764W59 4 4 1.00 0 ~2 -0.40 1.40 -1.11:1111 4.1176471 1 5 ' ** . 0L 0 0 -0.40 -0.00 -1.1111111 -1.7647059
* . 00 -0.40 g.4U . 1;11111 6 0 3 '/.Uman i
*l * (9, 6 ] . <j , . 9 p. 4 <. ,, .1;1:j ; . ' %.%
o ..UU U J ' U . 'ib U 4V J .1J 11d i J .1/t1/ v t, 9 ..v0 1 2 0.00 1.4v 1.ottete7 4.117t4/1 10 ;.00 3 2 2.60 1.40 7.;2242; 4.11764*/1 11 ; . '.'0 0 0.40 0.40 d.;;.1111 l 1 1.176479t i O.d 12 1.00 0 .' 1.w 1.lillia 9.1176 0 1, s
; 13 .t 0 : ; e.(U 0.40 ..de6,tt7 . 1/h /0e l ;4 . . 4 0. w 1. 6.i . . I .' Ii n . 1. W7i.h
- 15 ...V 0 . 0.40 0.40 .. '1111;
. 1.lin/0e
'e
. . 00 0 1 -0.40 v.% 1.'111111
. 1.17647v6 l 17 1.00 1 3 0.00 2.40 1.teb66e7 7.05h235 I Id 1.(0 1 2 0.60 1.40 1.6666f 6'/ 4.117t 4'/1
; 1.00 19 0 1 -0.40 0.40 1.11:1111 1.1764706 ,
20 1.00 0 3 0.40 2.(0 -1.1111111 7.05euj5 a 21 1.00 0 2 -0.40 1.40 -1.1111111 4.117e471 2: ..X 0 ; 0. 4t: 1.90 d.n;11H 4.11760; i s .4 1.00 0 3 0.40 4.40 1.;1"11 . 1 / C56035 i i 24 1.00 0 1 -0.40 0.40 -1.11:11n 1.176470e
. 25 1.0u 0 1 -0.40 0.40 -1.1111111 1.176470t i 28 1.00 2 0 1.60 0.60 4.4444444 -1.7647059 27 1.00 0 3 0.40 2.40 -1.1111111 7.056u35 i 26 1.00 0 2 0.40 1.40 -1.1111111 4.1176471 29 1.00 0 1 -0.40 0.40 -1.1111111 1.1764706 30 1.00 0 2 -0.40 1.40 -1.1111111 4.1176471 31 1.00 0 0 -0.40 -0.60 -1.1111111 -1.7647059 32 1.00 1 1 0.60 0.40 1.6660f4'/ 1.1764706 i j 33 1.00 0 2 -0.40 1.40 -1.1111111 4.1176471 !
34 1.00 0 3 -0.40 2.40 -1.1111111 7.0$h .:? t i i l 1 f w l g
- n .
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- A"%A s 1'* ** ' ' * *** '
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. k % op y "ka?v:.t'A ':, ~ N f ' X' .
3 .l ' ') .' - N hs'Neh.it i i
CUA DECONTAMINATION AND DECOMkilSSIONING SURVEY DATA Pangborn B-16R, Reactor Room A-1 .} BUILDING & AREA DRAWING No. SURVEY Imdlen 2221 Scaler /Ratemeter: Lud1 tun 44-4 Prnb' BLOCK D!RECTLYMEASURED DESIGNATION ColNTS/1 MIN./ PROBE DPM/100 04 2 GROSS NET BETA-GAMMA B-0 22 0 n D-0 30 0 n G-0 22 - 0 0 H-0 30 0 0 C-1 34 4 136 F-1 24 0 0 H-1 32 2 68 E-2 31 1 34 A-3 30 0 0 D-3 24 0 0 F-3 20 0 0 , H-3 28 0 0 l E-4 17 0 0 i G-4 27 0 0 4 ; C-5 26 0 0 l F-5 22 0 0 H-5 25 0 0 A-6 36 6 204 H-6 28 0 0 A-10 31 1 34 B-R 34 4 2nA H-8 26 0 0 B-9 38 8 272 t D-10 31 1 34 yQ g K6 g44 .i SHEET of l I
It . i -s CUA DECONTAMINATION AND DECOMMISSIONING SURVEY DATA t Pannborn B16R. Reactor Room Ae1 BUILDING & AREA DRAWING No. SURVEY m calerMmer; Mm G-M hok BLOCK DIRECTI.Y MEASURED DESIGNATION Counts /1 Min./ Probe DPM/100 cm2 GROSS NET ALPHA B-0 3 0 O D-0 6 2 13 G-0 5 1 7 H-0 9 5 34 C-1 4 0 0 i F-1 6 2 13 H-1 1 0 0 E-2 5 1 7 A-3 3 0 0 D-3 10 6 40 F-3 1 0 0 H-3 6 2 13 E-4 7 3 20 G-4 5 1 7 C-5 3 0 0 F-5 9 5 33 ! H-5 0 0 0 A-6 6 2 13 H-6 4 0 0 A-10 7 3 20 B-8 4 0 0 H-8 4 0 0
- B-9 5 1 7 D-10 1 0 0 F-10 1 0 0
" 10 5 1 7 i
SHEET of I
RADIATION EXPOSURE RATE ANALYSIS Micro R/hr at 1 Meter AREA Reactor Room, Pangborn Hall B16-R INSTRUMENT Ludlum Model 19 S/N 82787 BACKGROUND-SIMILAR CONSTRUCTION: Pangborn B-16, 5.5 micro-R/hr-GRID POINT / BLOCK MICRO-R/Hr B 1* 6.0 B 2* 6.2 B 3* 6.0 B4* 5.2 B 5* 6.0 B 6* 6.2 B 7* 6.8 B 8* 6.0 B 9* 7.0 B 10* 7.2 B1 5.0 B2 5.0 B3 5.2 B4 5.0 B5 6.0 B6 6.0 B7 6.3 B8 6.0 l B9 7.0 l Note: * = Measurement taken over gridpoint; remainder of readings taken over gridblock center as located by l
- lower left gridpoint.
/7 /f
O RADIATION EXPOSURE RATE ANALYSIS Micro R/hr at 1 Meter AREA Reactor Room, Pangborn Hall B16-R INSTRUMENT Ludlum Model 19 S/N 82787 BACKGROUND-SIMILAR CONSTRUCTION: Pangborn B-16, 5.5 micro-R/hr GRID POINT / BLOCK MICRO-R/Hr C 1* 5.7 B1 5.0 B2 5.0 B3 5.2 B4 5.0 B5 6.0 B6 6.0 B7 6.3 B8 6.0 B9 7.0 C1 5.0 C2 5.2 C3 5.5 C4 5.5 C5 5.2 C 10* 7.8 D 1* 5.0 D1 5.0 D2 5.0 D3 4.7 l l 1 Note: = Measurement taken ove. grid point; remainder of readings taken over grid block center as located by lower left grid point A If
l 1 RADIATION EXPOSURE RATE ANALYSIS Micro R/hr at 1 Meter AREA Reactor Room, Pangborn Hall B 16-R INSTRUMENT Ludlum Model 19 S/N 82787 BACKGROUND-SIMILAR CONSTRUCTION: Pangborn B-16, 5.5 micro-R/hr GRID POINT / BLOCK MICRO-R/Hr D4 4.5 l D5 5.0 D 10* 8.0 l l E 1* 5.0 E1 5.0 , l E2 5.5 E3 5.5 E4 5.5 -l l E5 5.0 l l E 10* 7.2 F 1* 5.0 F1 5.7 F2 5.7 F3 5.5 F4 5.0 F5 5.2 F 10* 8.0 ( G 1* 5.2 G1 5.5 l G2 5.2 , 1 l Note: * = Measurement taken over grid point; remainder of readings taken over grid ! I block center as located by lower left grid point. Alb
f w RADIATION EXPOSURE RATE ANALYSIS ' Micro R/hr at 1 Meter AREA Reactor Room, Pangborn Hall B16-R INSTRUMENT Ludlum Model 19 S/N 82787 BACKGROUND-SIMILAR CONSTRUCTION: 5.5 micro R/hr , GRID POINT / BLOCK MICRO-R/Hr G3 - 5.2 G4 5.7 G5 5.7 G 10 7.5 H 1* 5.5 H1 6.0 H2 5.2 H3 5.7 H4 5.7 H5 6.0 H6 7.0 H7 7.0 H8 7.0 H9 7.2 I 10* 7.5 Note: * = Measurement taken over grid point; remainder of readings taken over grid block center as located by lower left grid point. lAVERAGEDROOMMEASUREMENTS: 5.8 uR/hrl l l l l l AM l
r. 4 '
~W
?
3 I 9 APPENDIX B REACTOR PIT ; FINAL STATUS SURVEYS :
Reference:
Grid Map B-1 t I PAGE
- Floor Surfaces-Indirect & Direct Measurements B1--B3
- Wall Surfaces-Indirect Measurements B4--B5
- Structure Surfaces B6--B16 l
- External Radiation Survey at 1 Meter B17 )
i i i
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2
. x 6
+
J ! T 2. 4 . E; . l
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Y , Y I
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4
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4 Ag. r h
HEALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE COUNTER HUMBER B ACT,GROUNO a .8 . CUA EFF. FACTOR * -8
==
._REnc r o R pa' 1> cog ,
& RI O 0).QCg$ jngp gaf }l Object or Area Surveyed TUE DEC 06, 1994 _ ,
C200P A Flocr of the Reactor ht W.RF 11E ALPEA blTA' ALPE/. EM t. f.I,PhA ' FETA l Sh CVDi (Mih.s cow 8 wnu rw COUNIS Crn Cert (0ngyl.:, ) i A0
- 1.00 0 0 0.40 0.60 -1.1111111 -1.764'/059 I A / 1.00 1 3 0.60 2.40 1.6666661 7.056845 Ai 1 .0(> 1 0 0.60 -0.60 1.66ct6e7 -1.7647059 Ag 1.00 ,
1 3 0.60 2.40 1.6666e67 7.050eb5 A /) ' 1.00 0 1 -0.40 0.40 -1.1111111 1.1764706 gj 1.00 0 1 -0.40 0.40 -1.1111111 1.1764706 g2 -
- 1. g.; C U 0.4s 0.60 -1. 1111;. 1.)c47059 A ,g 1.00 1 U.b0 0. 4 f> 1.tttoeci ' .17c4 /Ut -
q
- f. [) 1.v0 2 0 1.tv -c.c0 4.hw 1.764/0n ;
c1 1 0' 1 1 ' 60 0 40 ""/ i 1/'47V' gy 1.y; O 2 .40 1.43 . 1....;. 4.i;16i/1
- p, 7 1.LJ C 0 0.40 -0.tQ ......... 1./047eh
) y ;.O g . ,,s c. 9.' . .... . . . . . ts. u -
qj . . f.f L i i.si 0. 4t- ......... . 1/ci/Oc jy ..t. U . e.40 .3) ......... s.;iit.i/.
- y q ..O O c .40 -0.tv ......... . . /t4 /vh I i
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t I , CUA DECONTAMINATION AND DECOMMISSIONING SURVEY DATA i l Pangborn B-16R. Reactor Pit B-1 BUILDtNG & AREA DRAWING No. Ludlum 2221 Scaler /Ratemeter; Ludlum 44-9 Probe ' - SURVEY BLOCK DIRECTLY MEASURED i DESIGNATION COLNTS/1 MIN./ PROBE DPM/100 CM2 3 ETA-GAMiA
; A-0 33 3 102
, C-O' 21 0 0 4 A-2 34 4 136 D-3 23 0 0 I l l j l i t
, .3 4 I i
d n (; SHEET . of
.I i 6-k
I 1 si , .i n . CUA _ DECONTAMINATION AND DECOMMISSIONING SURVEY DATA $j! i !! Pannborn B16R. Reactor Pit B-1 l BUK. DING & AREA DRAWNG No. l l SURVEY m er/Ratmeter; Mm 43-6 hok , l BLOCK DIRECRY MEASURED DESIGNATION Counts /1 Min./ Probe DPM/100 cm? GROSS NET ATPHA , I,
.l A-1 4 0 0 A-3 2 -
0 0 C-1 2 0 0 I D-4 4 0 0 l l l l ) l l j "e 1 I i
\
l 8 SHEET - of
\ ! 83 1
H.EALTH PHYSICS _ COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE 1 COUNTER NWBER BA M ROUND* .A CUA EFF. FACTOR *t -- g _L_ REACT 0R PIT WAM_S _ G RID rnB P 8-l Object or Area Surveyed TUE Dtc 06, 19y4 GROUP A Nerth b]1 c! the Peactor ht ! yQ$7y iAGl.2 ..a n r:n sin s:n :..n n r u. =. r.
. SN CODE iMIE.1 COVETS COUNTS CFM CPM CMRB:hD CushCYD
_p 4 ,
. 1.K 1 3 0.60 2.40 1.t666667 7.056 tis 5 l)
R '4 ' . 2 1.00 0 0 -0.40 -0.60 -1.1111111 -1.7647059 [' GI ' ) 3 1.00 2 1 1.60 0.40 4.4444444 1.176470e ;
,s . If 4 1.00 0 3 -0.40 2.40 .1111111 7.056fu5 A'4 'D 5 1.00 0 0 -0.40 -0.60 -1.1111111 -1.764769 ,
f4 () 6 1.00 0 0 -0.40 -0.60 -1.1111111 -1.7647059 t M _ T) 7 1.00 0 2 -0.40 1.40 -1.1111111 4.1176471 l J)' id)' [] 8 1.00 0 1 0.40 0.40 -1.1111111 1.1764706 IVE DE'; tt. .sM EAST 8/S!.E ";'.ME T' ALPEA EhA ALh:t. EETA ALPHA BETA SN CODE t 5:14. ) CuyNTS COUNTE CFM CPM CORRECTED COERC1ED i f, .4 , j 1 1.00 0 2 -0.40 1.40 1.1111111 4.117b471 f ', j ,' ) 2 1.00 0 1 -0.40 0.40 1.1111111 1.1/64/0t p ' 3 '. j 3 1.00 1 1 0.tv U . 4t' ..etttett 1.1'/t,470c f ' ~f ' j 4 1.00 0 1 -0.40 0.40 . . n1'. In 1.17647vt f j ,' /) 5 1.00 . 4 0.t? J.40 1.;tttbbi IV I'W D e [ ' j ' [] 7 ..W U i -D. W U.W ... 11'. . ; . . ib4 / Ut 6 . 00 0 2 -U 40 1.40 1.1111111 4.117e4/1 F '. ) ' /) - 3, e d 7 .
-N *
' .i.','.. .
H. eat.TH PHYSICS COUNTED DY DATE SMEAR SURVEY RECORD - SURVEYED BY DATE C UNTER HUMBER BACKGROUND
- A
- CUA EFF. FACTOR * ,8
. l (2fect or hea Surveyed ~TUE DEC 06; 1994 ,
GROUP A South bil ef the kcactor gfffy - UKM ME AL M WA Mh' WA A'A MA l 5!i CODE (!!h.) COUhTS CuUNIS CiE CPM .CORRECID CCEECliD l 77p, j 13 1.00 1 4 0.60 3.40 1.6666667 10 r_ ' n ', j 14 1.00 0 1 -0.40 0.40 -1.1111111 1.1764/06 l l ['bf~) 15 1.00 0 1 -0.4v 0.40 1.1111111 . 1764706
; ) ' B ,' j 'e
. 1.00 1 1 0.60 0.40 1.6666e67 1,1164706 l ' f)' () 17 ,
1.00 4 2 3.6u 1.40 10 4.11764'/1 ( ', j) * [] 12 1.00 0 0 -0.40 -0.60 ~ -1.1111111 -1.7t4/0$y gs j)! f)
- 19 1.00 1 2 0.6) 1.40 1.666666'l 4.1176471 j
. v"AW 'bi D 20 1.00 1 1 0.60 0.40 1.6666667 1.1764706 >
E I'
- WEST '
i 10E DEC Ot. 1 W. l Gk00P A West kall ci the Reactor ht ! SAMPLE TIME ALPHA BETA ALPHA r' LTA ALFHA BETA th 003 (Mih.) COUb!S COUkfs CPM CFR CORRECTED CORRECTED 1 H. O. ' 1 ;u 0 1 -0.g0 0.40 1.1111111 1.1764706
; i f}'; 1 . 00 ( 0 -.. 4'; -0.0 . 11'.1.. . . . ?t 4 !0H l 'b'
. IJL 0 1 0. 9 .' O.s0 -1.1111111 ;.;764?06
'A 'W J s 1.00 .5 1 .:.60 0. 4t- /.2d.'d2 1.;7%70t 1 .' d .' O : 1.M 0 J v. u .: .4U -1.1114111 ' 'emah F i' D 6 1.00 0 3 -0.40 2.40 -1.1111111 /.0566235 1 .' ; ' ? - -
7 1.lio 0 1 0.40 J.40 -1.1111111 1.1764706 1 ' t '. D_ 6 1.00 0 1 -U.40 0.40 -1.1111111 1.1764706
~
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A 7, j [ i-4
._ _. ,+ -
i l Reactor Structure Surveys
. Pit Rail, Reactor Room (13' side : circumference of pipe : 4.5" 8
equivalent 1 m =28 f t] SN Area-Item Survey 1 Sotith Side Top Rt.il 2 South Side Mid Rail 3 North Side Top 4 North Side Mid 5 East Side Top 6 East Side Mid 7 West Side Top and Mid
. Catwalk Railing (facing west)
SN Area-Item Survey 8 Left Half Top 9 Left Half Mid .- 10 Number Not Used 11 Right Half Mid P 66
, HEALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE :
COUNTER HUMBER BACT, GROUND
- A
,CUA EFF. FACTOR
- f R2 ACT0R S T R t/ C TJ /trS _
i t W w hea Meyed FRi DEC'02, 1 H 4 GEOUP A PIT RAluhG- EEACTOR kOOM EAMPLE 7:ME ALMA iETA ALPsA LLIA ALFtA :UA I 08I SN CO?E #M!h,J COURS COUCS CPM CPM 00kRECTED GdccD
. R RI Alp s.
1 1.00 1 9 0.60 6.40 1.76 JCi9 ;4. '!0i rc.- 2 1.00 0 0 -0.40 0.00 -1.1/e4/0e -1.1:4/05
- ;. 00 0 0 0.40 0.60 1.D64706 1.i647 b j 4 1.00 2 0 1.60 -0.00 e.70%e24 !J64/0h 5 1.00 0 4 -0.49 3.90 1.17f4700 '. 0 6 1.cv 1 1 0.e0 0.40 1.70470% 1.17t<J0t
- 7 4.00 0 0 0.40 0.60 1.D64700 -1.764bM ,
i fH DEC 02, 1 h4 Gs0UF A Fil xi,:LINJ -REACT 0k ROOM (AMPLE !!ME ALFEA Bh!A A:.HA FEIA A;Ht. E;t. Sh GDi iM.h.) COUCS 10'JCf CPM GM C0sgTEg coincrED 8EC9VMU . 1.00 0 2 -0.40 1.40 1.D64706 4.11764'/1 5 1.00 1 1 0.60 0.40 ;.76470% 1.1764'i06 FEI DEC 62, ah
- CAT WAAJC CEOG B CAieALK kA:usG-(FACIsG WEsis.mC;ck gem AAJA./#(y EAMPLE IIME ALMA BETA ALF.8.A BETA AL,'hA M;A Sh CODE (MIh.) COUCS COUCS j
CFM CFM (0hiCTED C0kRECTEDe: B 1.00 1 1 0.40 0.60 1.1111111 1.7647059l' 9 1.00 0 0 -0.60 -0.40 -1.666e667 1.1704706 ' 11 1.00 0 2 -0.60 1.60 2.6 % 66 9 4.70ne 4 i e i
~ tw.
q c .-f S - r p . - . ,29 ,y7 ,) - *
,P, _ ( e f~ g . - l b.. .li m . c. . .m e ri j .
9 a
. Catwalk Platform (facing west)
SN Area-Item Survey 12 Left Half 13 Left Half 14 Left half 15 Left Half 16 Right Half 17 Right Half 18 Right Half 19 Right half
. Steps down into Pit SN Area-Item Survey 1 Left Side Runner 2 Right Side Runner 3 Steps: Top two 4 Steps: Hid two 5 Steps: Bottom Three
. Catwalk Support Poles SN Area-Item Survey 6 North Pole Base 7 North Pole 8 East Pole base 9 East Pole 10 South Pole Base 11 South Pole 12 West Pole Base 13 West Pole b8
B
, H.EALTH PHYSICS COUNTED BY DATE SMEAR SURVEY RECORD SURVEYED BY DATE CUA COUNTER HUMBER BACKGROUND
- A EFF. FACTOR
- 8 Object or Area Surveyed IRI DEC 02, 1994 GROUP C CATWALK PLA!f0RM, (FACIM bEST), REACTOR ROOM SAMPLE IIME ALPHA BETA ALPEA EETA ALFhA iETA EN CODE (HIN.) COUNTS COUN:s CPM CPM C0kkECTE: C0kkEC'.D f4ATMRPt'~
12 1.00 0 1 -0.40 0.40 -1.1111111 1.1M4706 1:1 1.00 0 0 0.40 -0.60 -1.1111111 1.76470% 14 -1. 00 0 0 -0.40 0.60 -1.1111111 -1.7647059 15 1.00 0 2 -0.40 1.40 -1.11:1111 4.1176471 ,
;s 1.0u 0 0 0.0 -0.00 -1.1111;11 -1.7t47059 i
;/ 1.(0 1 5 0. t.0 4.50 1.66t t.it// 14.941176
- ;u 1.00 0 . -0.40 0.40 -1..;..... .. 1t4/Co
.. 1.00 2 1 1.6v .i.40 4.4W d . . . 't 4Tc.
i 1 W .2 l vs, .n4 k / r t. . .' t : . 'L , h ! .'s'.'0 t il. .
. ' '!i *.
'"~ STA l $ $ :o 'r a *:Mi
. 1.Ln.i, . . . i, b.ii i. ...A r...r u, : . . i.
4 . :. J. ! . :!:CJ . .r X.
. Gr. i.'r M .vr e...t J.:.v.p.;i0
. 1.00 u u v.sv .- ..... ... . . ies is:.8
.. i.h 5 2 -0.40 1.40 -1.1;4...; 4.11/os!;
1.00 0 0 -0.40 -U.eu ;.111;1*1 . ~;.?t 470% 6 1.00 0 1 -0.40 0.40' -;.1111;.; 1.1764/u6 I 1.00 0 1 -0.4u 0.40 -1.:1;;111 ; . ;'/o4'/0d I I ru sc 05. I w, ' GLOUP b CA hALK SUPP0kl v6 LS I M 1; AMPLE TIME ALFEA LETA ALPHA bi1A ALh.A ILIA i
~
M 0 M8 SE CODE (MIN.) C00CS COUNTS CPM CPM CORRECTD COERLCTED [ t c 1.00 0 0 0.40 -0.6u 1.1111111 -1.76470Lv 7 1.00 0 ; -0.40 0.40 -1.1111111 1.;7644e B. 1.00 0 2 20.40 1. 4's -1.111:111 4.1;/f 471 9 1.00 0 0 -0.40 -0.60 -1.1111111 ..ies /un 10 1.00 1 0 0.69 -0.6u 1.666 eft 7 1.*t.47uty 11 1.00 0 0 -0.40 -0.e0 : 1111111 ..itsiv5 12 1.00 0 1 -0.4u 0.40 -1.1111111 1.17b47ut. 13 1.00 2 1 1.60 0.40 4.44HH4 :.176470e i
, . \
l I
~
, .,.,e.
e . Q. P try .,^ p --
'd
.n. ,-
9 ,
l
. Reactor Tank (Shell), Top SN Area-Item Survey 14 Left Side First Quadrant ;
15 Left Side Second Quadrant , 16 Right Side First Quadrant 17 Right Side-Second Quadrant
. Reactor Tank (Shell), Middle SN Area-Item'* Survey 6 Left Half Block 1 5 Left Half Block 2 4 lef t Half Block 3 3 Right Half Block 4 2 Right Half Block 5 1 Right Half Block 6
. Reactor Tank (Shell), Bottom SN Area-Item Survey 7 Left Half First Quadrant 8 Left Half Second Quadrant 9 Right Half First Quadrant l 10 Right Half Second Quadrant I
J
'6 10'
i.
, H.EALTH PHYSICS COUNTED BY DATE -
SMEAR SURVEY RECORD SURVEYED BY DATE l COUNTER NWBER BA M ROUN0= A CUA - EFF. FACTOR
- 8 l
l
, l
. Object or Nea Surveyed Mvh M 05, 1994 i Gk0tlP C kEALM SHELL GACIM WEST) T##4 - 6 AMPLE T1HE ALPliA BE1A alpha d,A AL}EA EL1A Eh CODE tKIN.> . C0tKTS C0(int -:H' CckKECTED C0Eh.. . top i 14 ' 1.00 0 ; -0.4v V.M -1.111M11 3.17t 4 /(+
- . 15 1.00 0 2 0.40 - 4. rX *1.11H111 4.11N G
;b 1.W D 2 -U.W . . s t. ..; ilin 4.li E 7; l
' ;.1764/Ce 17 1.00 1 1 0.60 0.40 1.6t66667 :
- . 5
~
i MON DEC 05,1994
~
GkOUP A hACM LHELL. R;D 11.A.Lhli iA?!% 6.fi 6 d:.a , ,
~
M I O gb.( SAMPLE flhE ALPHA EE 4 D FA . :. . A Akt. A 661A l l 1 a ch . .n h . 20m? cGt t '. 3.1 .t . a n.& w.:n a.. . ! 6 1.00 0 0 c.4 ' .A G.~.;in;. -1.764 /en . , 0, '. . . . ;. 2111 4.u7t47; ' l 5 1.0 0 . ..M i ) 4 1.00 6 2 U . 4i. ..':'.' . 11.;1 U 4.llh4'/; + 1.00 0 0 -0.49 n ..nni;. 1.h4%i+ l
- i. 2 1.00 0 2 - 0. 4'; . 40 d.UMin 4.U7t,47; j
- 1 1.00 0 2 0.40 1.4. 1.n2.111 4..;7tfi; l t . l f .i I 4-i l TANN MONIisc 05. 1994
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SN Area-Item Survey . 11 Outside Corner 1 12 Outside Corner 2 4 13 Outside Corner 3 5 14 Outside Corner 4 15 Inside First Half 16 Inside Second half i . Access Ports SN Area-Item Survey 1 Outside B.P. 2B 2 Outside B.P. 1B 3 Outside B.P. 3B 4 Outside B.P. 4B 5 Inside B.P. 2B 6 Inside B.P. 1B 7 Inside B.P. 3B 8 Inside B.P. 4B i I l I l 1 1 I 1 l l 8/2 l l l I
; H.EALTH PHYSICS COUNTED BY DATE ,
SMEAR SURVEY RECORD SURVEYED BY DATE ! COUNTER NUMBER BACKGROUND = .A CUA EFF. FACTOR
- f i
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l GkOUP C kEACTOW PLATE ON }LOOH ri1A f! y ypppg i't.MPLE T1!!E ALPEt. FETA ALPHA !!TA ALPHA C0i.Rt.CTED 1 ! D C'f>E (Mik.) COUNTS COV5TS CFE CPE CORRECTED PA$7$ i 1
- EU FA#d 11
;2 1.00 0 0
3 -0.40
-0.40 2.40 0.40
-1.1111111 1.1111111 7.0bbrib 1.'.Yt4/0t l
1.09 1
-0.49 1.40 -1.1111111 4.117t47; IJ 1.00 0 2 14 1.00 0 1 -0.40 0.40 -1.1111111 1.176006 4 lb 1.ve 0 0 -0.4U 0,t U 1.1111111 -1.76470%
16 . 1.00 0 1 -U.40 0.40 -1.1111111 1.1764?06 i- !
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- ACCESS MON DEC 05,1994 .
~
GROUP A ACCEIS P0KTM4 INCiD B.P. 2B,1B,3B.41t; ;G FOUH 0UTSIDE. 2ND FOUK-pgg EAMPLE TIME ALPEA BETA A'.F"A IETA A'.. PEA EETA l 00i3ECfD CORRECO
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SN COLL MIN.) COUNTE COW.T CPM CPM 1 1.R 2 0 :.t0 -0.60 4.4M4M4 1.7t4E H 1
. 1. '.4 ; ! 1.f 7 4. 4 ') 4.4H444 ;;.M;. -
t 1. i" i' ' 0.40
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;.1764/05 t, 1.w 1 1 0.t 0 U.60 1,i666667 1.176479t, 7 1.00 1 3 0.60 2.40 1.6666667 7.0566235 ,
e 1.v0 0 0 -0.40 0.60 -1.111111; -1.76470b 4 4
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SN Area-Item Survey 9 Outside B.P.-2A : 10 Outside B.P. 1A ' 11 Outside B.P. 3A i Outside B.P. 4A 12 f 13 Inside B.P. 2A 14 Inside B.P. lA' 15 Inside B.P. 3A i i
. Glory Hole Access Port (l n")
i SN Area-Item Survey
- 16. S W Side Outside 17 S W Side Inside ;
18 N E Side Outside j 19 N E Side Inside l 1 l l a 6H
, HEALTH PHYSICS. COUNTED BY DATE i SMEAR SURVEY RECORD ~ SURVEYED BY DATE' :
COUNTER HUMBER BACV, GROUND
- A CUA EFF. FACTOR * ,8 i'
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Object or Area Surveyed G. % o IO lfS P0.Cc: .P. 2A,1A,3A,4A: 15! W..< v. PES N!ihi, J.i tc'.x Ikh t i EAMPLE f!ME ALP!'A EETA A!.FEA BETA A. PEA iCA i !
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t .te r.2a222 1.1764/.: i
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'f' 15 *- 1.00 1 3 v.e9 2.40 1.Hettt7 7.0%B;35 i I r
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SMEAR SURVEY RECORO SURVEYED BY DATE ,' COUNTER NWBER BA M ROUN0m s f CUA. EFF. FACTOR * ,8 l j l'..'h : EC vt, ivM - 7WlP A iAlb S UM: et.: .;;, GP a u l, yki n . O 1 Ot M m na M yAgtg - gg A:,pgA pMA rJnr. r- lr n.inA PL r l 1 ,
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I l l RADIATION EXPOSURE RATE ANALYSIS Micro R/hr at 1 Meter l l t AREA Reactor Pit INSTRUMENT Ludlum Model 19 S/N 82787 l 3 BACKGROUND-SIMILAR CONSTRUCTION: Poured concrete wall *, SuR/hr i
,
- Similar pit not present on site 1
GRID POINT / BLOCK MICRO-R/Hr B 1* 4.0 B 2* 4.0 B3* 4.0 l C 1* 4.0 C 3* 4.0 D 1* 4.0 D 2* 4.0 D3* 4.0 Note: * = Measurement over grid point l l Averaged Pit Measurements: 4.0 uR/hr l i l l l l 1 I 6 11}}