ML20151F905
| ML20151F905 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 04/30/1988 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20151F897 | List: |
| References | |
| NUDOCS 8804190051 | |
| Download: ML20151F905 (94) | |
Text
{{#Wiki_filter:1 i WESTINGHOUSE NUCLEAR TRAINING REACTOR DECOMMISSIONING FINAL REPORT l l l NRC License No. R-119 Docket No. 50-87 April 1988 l
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1.0 BACKGROUND
AND MANAGEMENT l l The follaaing sections of this report sh ow t h a t the Westinghouse Nuclear Training Reactor (NTR) Facility now meets the criteria for unrestricted use as specified in the NRC Order Authorizing Dismantling of Facility and Disposition of Component Parts, Section 8.0 of the Westinghouse Nuclear Training Reactor Dismantilng Plan and Regulatory Guides and Standards. The Westinghouse Training Reactor staffe who is responsible for the conduct of the R-119 Ilcense, managed all the steps associated with the dismantling and disposition of ; c omp on e n t s . All activities associated with the di sman tl i ng l were performed by Westinghouse Electric Corporation j personnel. All procedures associated with the dismantilng j of the reactor and components, the shipments of the special nuclear material to DOE facilities and the disposition of activated components to a licensed radioactive material management site were reviewed by the NTR Management and the l Reactor Safeguards Committee to ensure regulatory compliance and ALARA practices, j l This report f ol l ows the format of the Dismantling Plan submitted by Westinghouse Electric Corporation to the Nuclear Regulatory Commission in July 1987 as supplemented , (Docket No. 50-87). I i 1.1
SUMMARY
DESCRIPTION l The Westinghouse Nuclear Training Reactor i s l ocated in the southwest corner of the Westinghouse Nuclear Training Center building (Figure 1). The Training Center is located in ! Zion, IL near the Commonweal th Edison Zion Nuclear Power Station (Figure 2). The NTR Facility consists of the reactor room, control room, heal th physi cs l ab, work shop, briefing room, rest room and office areas. Figure 3 111ustrates the layout of the room within the Facility. The NTR was a light-water moderated, graphite reflected, pool type reactor. The R-119 license limited reactor power to 10 Kw thermal. The reactor was utilized for the training l of conmercial power plant operators which generally required l power levels of less than 100 watts. Annual integrated l power between 1972 and 1987 ranged between 56.3 and 13.4 kw-brs and averaged 30.86 kw-brs during this period. The l reactor has been shut down since February of 1987. 1.2 FACILITY OPERATING HISTORY The NTR was originally constructed as the Westinghouse Critical Experimental Station (CES) in the late 1950's and l ocated at Wal ts Mill , Pennsylvania. It was issued facility license CX-11 on June 17, 1958. The CES was used to conduct low power physics tests and experimental apparatus Page 1 l 2
environmental studies at a maximum power of 100 watto. The reactor was moved to Zion, IL in 1971 and relicensed as the Westinghouse Nuclear Training Reactor, License No. R-119. There has been no detectable release of radiation to the environment during the operating history of the NTR. No radiation spills and no areas of high contamination have existed in the Facility during its operating history. During student training sessions, there were two incidents of dropped fuel elements (March 1, 1979, November 23, 1981), neither of which resulted in any damage to the fuel element or Facility contamination. 1.3 RADIOLOGICAL STATUS OF THE NTR FACILITY The NTR Facility had been operated in an extremely clean r ad i ol ogi c al environment. The consistent integrity of the fuel, the l ow integrated power, and the Ilmited amount of ac t ivated mater i al s simpl i f i ed the di sman tl i ng operat i ons. All of the radioactive portions of the Facility have been removed from the Faci 11ty. This includes the f ol l ow i n g Neutron Activated Materials: Aluminum Reactor Core Structure Stainless steel control rod supports Stainless steel and Al uminum bol ts,nu ts and var i ous componen ts l oca ted in the reactor tank Nuclear instrumentation located in the reactor Non-exempt calibration sources Contaminated Materials No contaminated material was present in the Facility. 1.4 DISMANTLING ALTERNATIVES Future activities within the Facility will not require the reactor or an NRC license. Therefore, no other al ternative is under consideration. 1.5 DI SMANTLING ORGANI ZATI ON AND RESPONSI BI LITIES The organization for the dismantling operations was essentitlly the same as that responsible for the R-119 license and Facility operation (Figure 4). All activities associated with the dismantling of the reactor and its c omp on e n t s , handling of radioactive materials and radiation surveys were done under the supervision of personnel experienced in the NTR. All procedures associated with the activities were written by staff personnel, approved by the NTR Manager and reviewed by a su bc omm i t t e e of the Reactor Safeguards Committee. Page 2
1 The NTR Manager was rocponelblo for the overall cafo conduct of the operations of the Facility and the planning and direction of the di sman ti l ng operat i ons. The Training Reac tor Coordinator was responsible f or the implementation and admi n i strat i on of the di sman tl ing pl an and procedures. He supervised the daily dismantilng activities and maintenance of the associated records. The NTR Lead Engineer assisted in the planning and assured that all aspects of the dismantling procedures were in accordance ~ with the plan and regulatory requirements. He was responsible to ensure that all equipment utilized within the Facility was in proper operating condition. He also supervised any personnel required for the completion of the project. Mr. Joseph Nardi, Manager, Licensing Administration and Mr. Andy Sabo, Director of Energy Systems Licensing, Safeguards & Safety were responsible for the adequacy of the radiation safety programs at the Facility. Besides reviewing the procedures utilized in the di sman tl i ng and disposition of radioactive components, they were available to assist the staff with any concern or problem. Mr. Nardi made frequent visits to the Facility during key phases of the dismantling to ensure compi l ance wi th regulatory requirements, ALARA practices and adequacy of established procedures. He c ompl e ted qual i ty assurance audits for each radi oac t ive mater i al s sh i pmen t . 1.6 REGULATIONS. RE_GULATORY GUIDES AND STANDARDS The dismantling operations, radioactive material shipments and surveys were conducted in accordance with the relevant federal and state regulations, regulatory guides and standards associated with nuclear research reactor d i sman t l i n g . These include the f ol l ow i n g :
-U.S. Nuclear Regulatory Commission Facility Operating License No. R-119, Docket No. 50-87, for the Westinghouse Nuclear Training Reactor, l 1
-10CFR50 Domestic Licensing of Production and Utilization l Facilities.
-10CFR20 Standards for Protection Against Radiation
-10CFR30 Rules of General Applicability to Domestic Licensing of Byproduct Maierial.
-10CFR61 Licensing Requiremen ts f or Land Di sposal of Radioactive Waste. l l
-10CFR73 Packaging and Transportation of Radioactive Waste
-49CFR Department of Transportation Regulations governing the transportation and packaging of Radioactive Materials.
-U. S. Atomic Energy Commission Regulatory Guide 1.86 Page 3
4
-NUREG/CR-26082 Monitoring for Compliance with Decommi ssi on i ng Termi nat i on Survey Criteria
-NRC Staff Position "Guidelines" "Guidance and Discussion of Requirements for an Application to Terminate a Non power Reactor Facility Operating License" The NTR Facility and its components were dismantled and disposed of such that components remaining within the ;
Facility and the Facility itself are within the l contamination ilmits specified in Regulatory Guide 1.86 ; (Figure 5) and within 5 micro-R/hr above background at one l meter from the surface. Final survey results indicate that i all areas of the NTR Fac il i ty curren tly comply with these l limits. l 1.7 TRAINING AND ODALI FI CATI ONS All work done in the Facility during the dismantling program l was compl e ted under the supervision of NTR staff personnel. j The maJ or i ty of the effort was completed by NTR staff or ; former NTR personnel trained in radi ologi cal procedures. All non-NTR staff personnel assisting in portions of the dismantilng were briefed on the applicable procedures and j ALARA prac t i ces to be f ol l owed dur i ng the opera t i on . Personnel participating in the dismantling and disposition of radioactive components were members of the NTR Staff or employees of Westinghouse Electric Corporation. 2.0 OCCUPATIONAL AND RADIATION PROTECTION PROGRAMS The radiation protection programs and standards utilized by the Facility during the dismantling program are outlined in the di sman tl i ng pl an . 3.0 DISMANTLING TASKS AND SCHEDULES The NTR Dismantling Operation included those tasks required to remove all radioactive components from the defueled NTR Facility such that any component remaining at the time of the final radiation survey is within the contamination limits of Regulatory Guide 1.86 and bel ow 5 mi cro-R/hr above background at one meter. 3.1 TASKS AND SCHEDULES Figure 6 lists the major milestones and anticipated schedule for the dismantling project. Figure 7 indicates the actual t ime s f or c anpl e t i on of the items. No special problems occurred requiring changes in the milestones, but unanticipated delays caused the project to run behind the projected schedule. Page 4
3.2 TASKS ANALYSIS This section will describe the approach taken to accomp115h each of the major tasks associated with the di sman tl i ng project. Special heal th and saf ety considerations were not required in dismantling the NTR core structure or associated components due to the low radiation levels that existed in the Facility. Normal NTR radiation safety precautions were utilized throughout the di sman ti l ng process. The di sman t l ing process was di v i ded into two phases. Phase One of the program consisted of evaluating the quantities of activated material and reactor components that would be required to be removed and shipped for burial. Procedures were then written and submitted to the Reactor Safeguards Committee for review and to the NTR Manager for approval to ship those items to a NRC licensed facility. Evaluation indicated that the shipment of the radioactive materials in the Facility would be done directly from this site and not use the Westinghouse DDR Facility. During this phase all permits, variances and approvals were obtained for shipping the radioactive materials. A computer generated analysi s of the radioactive isotopes in the activated stainless steel within the control rods, based upon total integrated power and peak neutron fluxes, was obtained. The activated control rod shafts were prepared for shipment in accordance with procedures to reduce the radiation levels within the Facility. All procedures for dismantling the reactor core and associated components and the final radiation survey of the Facility were prepared and submitted for the appropriate reviews and approval. Phase two of the program commenced with the NRC approval of the Di sman tl i ng Pl an and issuance of the "Order Authorizing Dismantling of Facility and Disposition of the Component Parts - Westinghouse Electric Corporation Nuclear Training Reactor" on January 29, 1988. This phase consisted of the dismantilng and shipment of the ac t ivated reac tor componen ts and the canpletion of the final radiation surveys of the Facility. The removal of the activated stainless steel control rod componen ts reduced the radiation levels in the reactor to Just above background levels. The core dismantilng was executed in a straightforward manner with no mechanical difficulties or unexpected exposure. All radioactive materials, except for small calibration sources, were sh i pped f rom the Fac i l i ty by March 18, 1988. No decontamination of the Facility was required. Final Radiation surveys of the Facility began on March 7. 3.3 SAFE STORAGE There is no requirement for Safe Storage since all radioactive material has been removed from the Facility. Page 5
4.0 SAFEGUARDS AND PHYSICAL SECURITY Since all Special Nuclear Material has been removed from the Facility, no Physical Security Plan is required. Areas within the Facility are being controlled in accordance with the requirements of the present Technical Specifications as outilned in the Dismantilng Plan and the NTR license No. R-119. 5.0 RADIOLOGICAL ACCIDENT ANALYSES No radiologi cal accident analysis was required since all reactor fuel had been removed from the NTR Facility. 6.0 RADIOACTIVE MATERIALS AND WASTE MANAGEMENT 6.1 FUEL DISPOSAL l All fuel had been removed from the site prior to the di sman t l i ng operat i ons. 1 l 6.2 RADIOACTIVE WASTE PROCESSING 1 No liquid or gaseous radioactive waste were present at the Facility. All solid waste were properly packaged and shipped to the Chem-Nuclear Systems, Inc. operated Barnwell
)
Waste Management Facility in Barnwell, South Carolina for burial. Figure 8 describes the contents and quantitles of these shipments. A total of 101.3 cubic feet of material , with an activity of 0.158 curies was shipped for i disposition. Irradiated nuclear instrumentation was donated to the l Univers!ty of Illinois Department of Nuclear Engineering l Laboratory. 7.0 TECHNICAL AND ENVIRONMENTAL SPECIFICATIONS The Technical Specifications for the NTR as amended for the "Possession Only" Facility License remained in effect dur i ng .the di sman tl i ng of the reactor and Facility. l The dismantling tasks were accompl i shed wi th no si gni f i can t I impact on the environment or the health and safety of the public. 8.0 TERMINATION RADIATION SURVEY The final radiation survey plan divided the NTR Facility into three sections based upon the probabilicy of contamination. Results of surveys conducted throughout the life of the Facility had indicated that no contamination has ever existed in the Facility. The final surveys used a formalized procedure based on a sampilng inspection plan to assure adequate coverage of the facility and to guarntee Page 6
that unrectricted uco of the Facility will not causo a ; radiation hazard to the public. l 8.1 FACILITY GRID PLAN Figure 9 indicates the divisions of the Facility for the survey as f ol l ows' 1 Section I included the briefing room, console room, reactor ! of f i ce and wash romn/ shower f ac il i ty. Areas with!n this section had the l owe s t probability of contamination. Approximately 30% of the area of the walls and floort in each room were chosen to be surveyed f or f i xed and renovabl e Beta-gamma and Alpha contamination. Figures 10 A, B. C&D indicate the 3 meter X 3 meter grids that were surve:'td in each room in section I. Each of the 3 X 3 meter grics surveyed were divided into 9 square meter grids as shown in Figure 11. Five survey points were chosen in five of the nine regions in the grid and surveyed for fixed contamination. A 100 square cm smear was taken at the point of highest beta-gamma reading in each of the regions. The gamma radiation level at one meter above the center of the grid was then recorded. Section 11 contained areas that had a higher probability of contamination since work done in these areas occassionally involved the handling of radioactive materials. This section included the Hallway, HP Lab, Workshop and the Janitor closet. In this section the rooms were divided into 2 X 2 meter grids and approximately 30% of the area of the ficor and walls surveyed. Figures 12 A, B&C Indicate the 2 X 2 meter grids that were surveyed in each area of section II. Each grid was divided into four 1 X 1 meter regions with two of these regions surveyed for both fixed and removeable contamination as in section I Figure 13. A gamma reading at one meter above the surface at the center of the grid was also recorded. Section !!! contained those areas where radioactive materi al s were normall y ut il i zed and stored. This section consists of the reactor room, including the reactor and dump I tanks. The floor and the walls (two meters up f r om the I floor) of the reactor room were divided into 1 X 1 meter regions and each surveyed in the same manner as the regions in section I. Figure 14 illustrates how the floor was divided into grids. Figures 15 A,B,C & D illustrate the regions on each wall of the reactor room. Three 1 meter x 1 me ter regions were also surveyed on each wall and the ceiling above the 2 meter height. The regions surveyec are shown on Figures 15 A,B,C,D and Figure 16. Twelve additional smear surveys were taken on the upper beams as indicated in Figure 14, The bottom of the reactor and dump tanks were divided into sectors of appioximately 1 square meter (Figures 17-A and 18). Each sector was surveyed as in section I only using 3 survey points as shown. Additional surveys were completed Page 7
on the reactor lower coro plate cholf end walle of the reactor and dump tanks as illustrated in Figures 17-A,B & 18. Special surveys were done in supporting systems throughout the Facility. These surveys consisted of smears, fixed beta gamma and alpha as well as area surveys as appropriate. 8.2 SURVEYS PERFORMED-GENERAL Each region within the grids were surveyed in the fo11aning manner
- A one minute integrated Beta-gamma on contact reading was taken at five points within each region of the grids (5 regions for a 3 X 3 grid and 2 regions in a 2 X 2 grid).
Each integrated count was recorded on a data sheet and the maximum gross counts and average counts for the region were i recorded on the survey summary sheets. The contamination levels in DPM/100 sq cm were calculated for the maximum and j average values in sections by subtracting background from a clean Aluminum plate and adjusting the results for detector efficiency and geometry.
- A one or two minute integrated scaler Alpha on contact l reading was taken at five points within each region of the grids as described above. Each integrated count was recorded on a data sheet and the maximum gross count and the average gross count were recorded in the sunmar y sheets for each region. DPM/100 sq cm was calcul ated by subtracting background and adjusting the results for detector efficiency and geometry.
-A 100 sq cm smear for removabl e Be ta-ganma and Al pha were taken at the point with the maximum on contact Beta gamma reading in each region. The results recorded as smear surveys in the summary sheets.
1
- A ganma (mis : o-R/hr ) point reading was taken at 1 meter f r om the surf ace of the center of each grid. Readings were i not recorded for those grids with centers less than 1 meter '
from an adjoining surface (corners, wall s of reac tor room, reactor tank). The results were recorded on the survey sunmar y sheets. Background was determined by averaging the results of more than 30 surveys throughout the remainder of the training center (outside the NTR Facility). Figures 19 A,B indicate where the baseline surveys were taken and the results from the survey. Average background for the training center construc tion material is 14.6 micro-R/hr. The Survey Summary Sheets section I, II and II: are given in Appendices A, B & C respectively. Page 8
l 8c3 SPECIAL SURUEYS Special additional surveys were conducted in other areas of l the facility to assure that no radiation or contamination
?xists in the facility. These surveys include pumps, pipes, ;
valves, and drain lines for auxiliary reactor systems as ! well as facility ventilation systems, ceiling tiles and raceways for pipes and wiring. A description and summary of the special surveys is given in Appendix 0. l 8.4 FINAL SURVEY INSTRUMENTATI ON All instrumentation was calibrated in accordance with facility procedure or sent t o c omme r c i al facility for , calibration. Efficiency cal i brat i on of Be ta gamma and Alpha probes and associated scalers were done utilizing standardized facility sources. Figure 20 lists the i instruments utilized to complete the final surveys in the NTR Facility. l Page 9
-~ __ _ _ __.
1 l LIST OF FIGURES Fioure Description 1 Westinghouse Nuclear Training Center 2 Location WNTC in Zion, IL 3 NTR Facility Layout 4 NTR Staff Organization 5 Regulatory Guide 1.86, Table 5-1 6 Major Milestones and Schedule 7 Maj or Mi l e stone Compl e t i on Schedul e 8 Radioactive Wastes Shipment Summary 9 Facility Division for Radiological Surveys ; 10A,B,C,D, Grids surveyed in Section I 11 3 X 3 meter Grid Survey Pattern 12A,B,C Grids surveyed in Section II 13 2 X 2 meter Grid Survey Pattern 14 Grid Pattern for Reactor Room Floor 15A,B,C,D Grid Pattern for Reactor Room Walls 16 Grid Pattern for Reactor Room Ceiling 17A,8 Grid Pattern for Reactor Tank 18 Grid Pattern for Reactor Dump Tank 19A,B Facility Ganma Background Data 20 Radiation Detection Instrument Summary
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Amerie:n National Standard ANSI'ANS 15.101981 Table 51 Acceptable Surface Centamination Levels Nuclide* Averageb e Maximumb d Removableb e U nat, U 235, 5,000 dpm ol100 cm2 15,000 dpm o/100 cm2 1,000 dpm al100 cm2 U 238, and associated decay products Transuranics, 100 dpm'100 cm2 300 dpm'100 cm2 20 dpm'100 cm2 Ra 226, Ra 228, Th 230. Th 228, Pa 231, Ac 227, 1125,1129 Th nat. Th 232, 1,000 dpm'100 cm2 3,000 dpm/100 cm2 200 dpm'100 cm2 Sr 90, Ra 223. Ra 224, U 232, 1126,1131, 1133 Beta gamma 5,000 dpm 0 - 7/100 cm2 15,000 dpm # - 7/100 cm2 1,000 dpm 0 7/200 cm2 emitters (nuclides with decay modes other than alpha emission or upontaneous fission) except St 90 and others noted above.
*Where surface contamination by both alpha and beta gamma emitting nuclides exists, the limits established for alpha and beta gamma emitting nuclides should apply independently.
bas used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation. eMeasurements of average contaminant should not be averaged over more than 1 square meter. For ob-jects of less surface area, the average should be derived for each such object. dThe maximum contamination level applies to an area of not more than 100 cm'.
'The amount of removable radioactive material per 100 cm2 of surface area should be determined by
- wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removabie contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
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1 DISMANTLING DATA .- l i M:LEST07:ES JAN FEB NRR APR IIRY JUN JJL PUG SEP OCT NOU DEC DECISICN TO DISMANTLE AMilOUNCEO 12-3-E6 FINAL CRITICALITV 2-9-87 FUEL SHIPT 1ENT 5-26-87 SOUP.CE SHIPMENT 5-29-87 PREPRP.E & SUBnlT DISMANTLING PLfri TO ffRC 0 c
'RSC PLAN FEUIEu O t:EET ulTH NRC 0
- DEVELOP DETAILED SCHEDULE FOR DISMANTLNG 0 DEFINE SCOPE & PERSONNEL REOUIRED : 0
, IRITE DISMANTLBG IMPLEMENTATION PROCEDURES 0 0 2 IST RA010 ACTIVE uRSTE E SHIPMENT 0
, DISMANTLE N ACTOR CORE t 0 0 REMOVE EXCESS EQUIPt1ENT FROM FACILITV. 0 0 DECONTArilNATE fEERS IF I REQUIRED 0 0 2MO RA010 ACTIVE uRSTE . SHIPMENT 0 FINRL P.ADIRTION SURVEY 0 0 URITE & SU8rilT FINAL DISMANTLING REPORT & l REQUEST FOR TERtilNATION .l OF LICENSE O O lEC FINAL INSPECTfDN O FACILITY FREE RELERSED ------ 0 I
- $: NRC APPROVAL OF, DISMANTLING PLAM, ALL SUBSEQUENT DATES DEPENDAffT ON RECEIPT OF NRC APPPOVAL 1
COMPLET!CN DATES MI LEST ONE COMPLETION DATE Decision to Dismantle 12-3-86 Final Cr i t i c al i ty 2-9-87 Fuel Shipment from site 5-26-87 Source Shipment from site 5-29-87 Submit Di sman tl i ng Pl an to NRC 7-8-87 Addi t i onal information 8-31-87 RSC Plan Review 7-10-87 Meet with NRC 6-2-87 Defined Detailed Schedule for Dismantling 2-1-88 Defined Scope and Personnel required 10-88 Completed Dismantling implementation Procedures 1-15-88 First Radioactive Shipment 2-22-88 NRC !ssues Order to Dismantle 1-29-88 Dismantle Reactor Core 2-16-88 Ramoved excess equitment from Facility 3-15-88 Decontaminate areas required none required ! Second Radioactive Shipment 3-24-88 Final Radiation Surveys 4-7-88 Final Di sman tl ing Repor t 4-12-88 l Figure 7
WESTINGCUSE NUCLEAR TPAINING REA;TO MDIM;TIVE ESTE SHIFtiDC Sat %RY t%R H 1985 I SHIFtiDC I DATE I NJtBER OF I ACITIVITY l WEIGHT I VOLLNE I I N2iBER I SHIFFED I FACKAGES I (CURIES) I (P0tNOS) 1(CUBIC FT) I DESCRIFTION I
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.i 1 IFEB 22.831 2 1 0.15B I 1350 1 11.6 IONE 55 GALLON STEEL DRJi CDMAINING 1 1 I I I I IIRRADIATED STAINLESS STEEL, IRRADIATED I I I I I I IGRAPHITE #iD 9%LL CHECK SOURCES. I I I I I I IPACKAGES CLASSIFIED: RAD!M;TIVE !%TERI ALS,1 I I I i l IN.O.S., TYPE A, CLASS A LNSTABLE I I I l l l
' I I I I I I IONE 30 GALLW STEEL DRW. CONTAINING l i I I I I ISEALED SOUR:ES OF CS-137 IN LEAD P!G, SR-90 1 1 I I I I l#iD #i-241 STABIL12ED IN CEMDiT. I I I I I I IPACKASE CLASSIFIED: RADIM"TIVE !%TERI ALS, I I i ! I I IN.O.S., TYPE A, CLASS C. I I I l l l l 1 1 1 1 I i ! I 2 It%RCH 101 1 1 1.04E-5 1 2l00 1 90.3 IIRRADIATED REACTOR C09 METS, LAB TRASH. 1 I I I I I IPACKASE CLASSIFIED: LIMITED QUNTTITY i l I I I I IRADIMOTIVE t%TERIAL, N.O.S., TYPE A, CLASS I I I i i l i A LNSTABLE. I
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........................................................ ___................,___................................. i TOTALS 3 0.159 3450 101.9 NOTES: All thigents were by 'ccm:n carrier' All shipuents were accepted and buried by 04$1 l
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WESTINGHOUSE NUCLEAR TMIN1HG REACTOR FI R CURVEY DATA {MINgCENTER 0#t% inCKGROLND g background CfN 04E METER FR21 R LS & FLOOR COWT TIME I MINUTES READING DATE 1 SMPLE NLMBER I ! C0tNTS I MICRO-R/HR 1%R!#4CE I
.........l..........................l......... I...........l............l...........I March 28 !!. WS RLEY l 1 17061 15.51 .91 I I l 16451 15.01 .21
- 2. WS 1%LLEY I 15441 14.01 .3 1 15731 14.31 .1
- 13. WS 1%LLEY l 1632 14.81 .11 1 I I 1648 : 15.01 .21
- 14. WS RLEY I 1593' 14.51 .01 1 I 1599 '
14.51 .01
- 15. WJPPS CLASSROOM i 11531 10.51 16.61 I i 12371 11.21 10.9!
- 16. W S R LWAY I 14381 13.11 2.21 1 I 15071 13.71 .7h
- 17. WS 1%LLay 1 I 18171 16.51 3.91 1 17031 15.51 .91
- 18. WS1%LLEY l l 15471 14.11 .21 1 15531 14.11 .21
- 19. CLASSR0013 i 13891 12.61 3.71 I i 14031 12.81 3.21
- 10. CLASSR0013 1476l 3 .41 1.31 1468 13.31 1.5' I 11. CLASSR0013 1511' 13.7) . 71 15571 14.21 .21 l 12. E/W W LW Y l 16231 14.81 .01 1 16821 15.JI .51
- 13. CLASSROGi1 14961 13.61 .91 ll l i 1544, 14.01 .31 114. CLASSROGi ! ll 1799: 16.41 3.21 1 I I 1791 1 16.31 3.01 115. CLASSRO@t 1 1 I 1823' 16.61 4.11 1 I l 18601 16.91 5.61 116. CLASSRO@l 1 1 I 16841 15.31 .61 I i l 16911 15.41 .71 4
117. EAl RLWAY I i 16581 15.11 .31 I I i 17281 15.71 1.31
- 18. STAFF LOWGE I i 15791 14.41 .01 I i 15381 14.01 .31 I19. E/W 1%LLEY I i 17491 15.91 1.8l i I i 16341 14.91 .11 120. C0FERD4CE R001 1 I 16251 14.81 .01 I i i 1604l 14.61 .01 l 21. C04UiDiCE RO&l ,
i 16631 15.ll .3: l 17611 16.0 i 2.! ! I I I I 1...... ....]............l .........] l l .... ..... .......1 ........ . AVEPAGE 1535 14.6 - READING 1 l l
% RIM 4CE I.11 ST m MRO DEVIAT!D1 1.1 C0iFLETED BY: yz' wh[#/
A CALIPPATIO4 = 110 CFtt411CRO-R/HR CAL 18 RAT!D4DATE: !!/3/87 i J//r/fr8 6 1 Figure 19-B i i
e RADIATION DETECTICN INSTRUMENTS TYPE OF RADIATION . SENSITIVITY l INSTRUMENT DETECTED RANGE M1E { Eberline E-530 Beta, Gamma 0-2K mR/hr Survey Victoreen , Radector !!! Beta, Gamma .1-1 KR/hr Survey
- Eberline PAC-1SA Alpha 0-2K cpm Survey ;
Eberline RM-15 Beta, Gamma 0-500K cpm Survey Eberline PRS-1 N/A N/A Scaler Final Survey . $ Technical Associates Scaler / PRS-3 Beta, Gamma 0-4K Micro-R/hr Final Survey l Staplex Beta, Ganma N/A High Volume Alpha Air Sampler Nuclear-Chicago N/A N/A Scaler I Model 8775 i i Eberline Beta, Ganma N/A Probe for < HP-210 Probe Scalers Eberline Alpha N/A Probe for AC3-8 Probe Scalers ] ' Eberline Alpha N/A Smear Counter , Sac-4 i i ! ] t41C Proportional Ccunter Smear Counter i i Model PCC 11T Beta, Gamma i c i j I ) I 1 ; 1 1 i i ! 4 1 i } I Figure 20 3
LIST OF APPENDICEQ T Aeoendix Qescription A Survey Data Sheets - Section I B Survey Data Sheets - Section !! C Survey Data Sheets - Section !!! D Survey Data Sheets - Special Surveys l ll e
5 l % l l APPENDIX A FINAL RADIATION SURVEY DATA SHEETS SECTION 1 BRIEFING ROOM CONTROL ROOM REST ROOtVSHOWER FACILITY OFFIC6 I l i
t SECT!W ! SURVEY SlM%RY M BER OF GRIDS SURVEYED: P GRID O! MENS! M$t 3 X 3 METERS ! RE6l WS PER GR!D SURVEYED 5 MXIM FIXED ALPM CMM!mT!W (DPW 100 50 m) 99.5 t MRAGE FlxED ALPm CMM!* Tim (DPW 100 S0 m) 11.3 l MXIM FIXED BETA-Gm CNM!milm (DPW 100 SQ m) 7883 MMGE FIXE 0 BETA-0#t% CHM!mTim (DPW 100 S0 m) 1985 FACILITY 6#t% InCKGR0lND (MICRO-R/m) 14.6 l
! MXIM G#t% RADIATim LEVEL (MICRO-R/m) 16.7 AVEMGE (#t% RADIAT!W LEVEL (MICRO-R/HR) 14.4 mXlM RDOABLE BETA-C#t% CNMlmilm (DPW100 SQ m) 145.4 MX1M REN#BLE ALPm CNMIST!W (DPW100 SQ m) MCKGRO M l
A , I 1 1 1 ) i i, 3 Page A-1
._ - .- -, .c..-. . . . _ . - - . , . - - . . , . - _ - _ _ _ .
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WESTINC4100SE fiUCIEAR TMINING REACTOR PAEE
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FIPML IMDIATIW4 SUPJEY MTA SEET - j t%RCH 1988 l l 1 LOCAT 34 i REGIGi SUPJEY IGM 9% SUINEY 1 PETER i 9fAR SUPJEY 11 I IGROSS 7%XIMtM CPM IGROSS #>Em 0E CPM i FR91 SURFACE I (DptV198 SOUARE CM) II MTE I IWM i SECTItN l GRID I REGI@i IBETA GM9% i M.Ple IBETA-GN9% i ALP m i MICRO-R/ HOUR iBETA-649% i ALPtM 11 1 I i i i I I I I I I II l 3/7/09 i BRIEFING POW 1 1 I I I i 1 1 811 2.51 73.41 1.51 i e I e il SETA/Gmtm i I I 2 1 798 3.01 65.61 1.71 I e i e 11 I I I I 3 1 773 2.01 67.21 1.31 15.91 e I e il 3/14 1 1 I i 4 i Bel 2.51 73.61 1.01 i e i e il l ALPm i I I I i 941 2.51 74.61 .91 i e I e Il l i I I I ilFCKGP0tND = 8.8 CPM i I I I ll l l l l 1 l- 1 I I I I I 11 ' T I BRIEFING RO@l I I I I! ! ! I 831 5.01 76.41 3.11 I e i e 11 B: 2A I I I 2 I B6l 5.01 77.21 2.71 I e i e 11 y I I I I 3 i B21 7.01 74.01 4.41 11.91 41.31 e II I ,.,, i I I I 4 I 851 4.51 78.01 2.98 I e I e ll 0, I I I I 5 1 811 4.51 72.01 3.21 i e i e II 1 I I I I IIMCKGP0lND = 2 CPM i I i I II 1 l- 1 I I I I I I I I ll 3/7/88 1 BPIEFING RD@l I I I III i 1 1 521 0.01 44.4I 8.01 I e I e Il BETA G#9m i I I 2 1 511 1.51 44.41 .41 I e I e II I i 1 1 3 1 531 1.01 41.41 .51 13.71 e I e il 1/11/88 I I I I 4 I 551 .51 47.01 .11 i e i e il C1Pm i I I I 5 I 571 .51 46.21 .31 i e I e 11 I I I I I IBACKGROWO = .9 CPM i l i i 11 I I I I I I l-- 1 I I I ll e ItOICATES 91 EAR READINGS OF LESS TlWI LLD I
'ETO 0,YtM LLD: 28.2 DFM/lGD SDUAPE D1 i ALF% IACKGROGG FOR GRID I (CPM) .8 ALP m LLD: 0.56 [*tV100 50lMPE D1 ,
ALP % imCKGR0tND FOR GRID II (CPM) 2.8
. ALPM BACKGROL90 FOR GRID III(CPM) .8 7%XIMLM BETA GM9% FDTD CONT #ilmTI94 94.0 CPM ALPm #JEIMGE FOR GRID I (DPfV100 S0WWE 00 9.6 #>El%GE BETA GM9% FIXED CD4TMiltMTIW4 2 63.7 CPM ALPH4 tmXIMW1 FOR GRID I (DPfV199 $0lmRE 00 43.8 f%XIttM ALPm FIXED CCNTMItMTI&is 7.9 CPM ALPim AVElmEE FOR GRID II (DP?V199 SelfWE Do 25.1 E'ETeGE ALPIM FIXED C3iiMtINATIS4: ALPim !%XIttM FOR GRID II (DPtV180 SQLMRE 00 99.5 ALPim #>EIMGE FOR GRID III (DPM/ ISO SelmRE DO B .3 1%XIMW1 BETA FIXED CORM 11tMTI2 : 5908 DPM/Itil SD Di ALPHA !%XIttM FDR GRID III (DPfv100 SEKmRE 00 13.9 A'ERAGE C}TA FIXED CCNTM11tMTIG4 IN AREA: 1317 DPM/102 SU Di IIETA IACEGP0lfOr 55 CPM ,, ALPm #>ERAGE FOR BRIEFING F001 !!.5 DrTA TrrirTr*Jrym 4.4% tJ FSm pew!weg frID DDirritJr. OfwN 99.%
' CCN50LE (CCeRROL) ROOM
' section !
(3 X 0 metor grids) TOP W A LL i s.se m tt) I L > ta 3 V # I j j ';g ' GtQ(o
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3 F L 0 L' Ps _ __ f__ $2 9. _ _ . 6 ?!J9 . J b 3 h E E M V M x i , . u i _ . ~ . . . - - - Page A-4
WESTINGHOUSE NUCLEAR TPAINING REAt. PAGE _ FIEL PADIATIDJ SURVEY DATA SHEET MARCH 1988 i LOCATION I REGIR4 SURVEY 1649% SURVEY 1 METER I SMEAR SURVEY 11 1 IGROSS t%XIMLN: CPM IGROSS MEl%GE: CPM i FR91 SURFACE ! (DFWid0 SQUARE CM) ll OATE I RO@t i SECTID4 i GRID I REGION IBEfA GMt% I ALPHA IBETA-GMtm i ALPl% 1 MICRO-R/ HOUR IBETA-G#t% i ALPIM ll t 1 I I I I I l -- 1 I I il 3/7/88 i CG4 TROL R001 1 I I IV i 1 1 841 5.01 78.41 2.81 1
- 1 * !!
BETA /GMt% 1 i 1 2 1 831 6.01 70.61 4.31 1 37.31 m 11 1 I I I 3 I 971 6.01 90.01 4.51 13.91 45.21
- 11 3/15 I I I I 4 I 981 2.51 82.01 2.01 I e i
- 11 ALPl% 1 1 I I 5 1 861 4.01 76.61 2.31 1
- I
- ll l 1 1 I I I I I I I I ll l C'NTROL R0et i I I V i 1 1 931 5.51 82.81 4.21 1 > I o 11 8: 2A I I I 2 1 811 5.01 72.41 4.01 I e i
- 11
% 1 I I I 3 1 841 6.51 75.01 4.41 14.81
- l n 11
, 3 I I I I 4 I 891 4.51 86.61 2.41 1
- 1
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) di i l i 1 5 l 911 4.01 74.61 2.11 1 29.41
- 11 1 I I I I I I I I I i 11 3/7/88 i CG4 TROL RORt i I I VI i 1 1 671 2.01 60.41 .81 1
- I e 11 BETA C4tm I i i 2 1 65! 3.01 54.01 .91 i e I e il i I I I 3 1 611 1.01 54.61 .81 13.61
- 1
- ll 3/15/88 I I I I 4 1 611 1.01 53.21 .6l I e I n ll ALPm i I I i 5 I 681 1.01 57.01 .81 i e I
- 11 1 I I I I I I I I I I 11 o IM)ICATES SNEAR READINGS OF LESS TWii LLD l BETA G#t% LLD: 28.2 DPM/100 SOUARE 01 l ALTHA BACKGR0lND FOR GRID IV (CPM 2.0 ALPHA LLD: 0.56 DPM/100 SQtMRE 01 ALPl% BACKGROIND FOR CAID V (CPH) 2.0 ALPl% BACge%w TCR BRID VI (CFTt) 2.0 m
MAX 2 Mat BETA Cat'A FIXED CGiTMtINATIG4 98.0 CFM s ' A *HA WERME FOR GRio IV(DPM/100 S0tnRE 01) 23.5 WE'ME BETA Cut % FIXED CGiTMtINATIR4 : 71.2 CPM nPim MAXIHill FOR GRID IV (DfY/100 SQ Di) 79.6 1%XIMW1 ALPin FIXED CONTMtIPMTI&is 6.5 CPM AJ:% AVERAGE FOR GRID ; (bni/19" SQ D1) 28.3 WEl%GE ALPHA FIXED C0NTM11t% TION: 2.5 CPM ALPm MAXIMLM FOR GRID.V (DPM/100 S'l CM) 89.5 1%XIMW1 CETA FIXED Cti4T#ilNATIG4 IN Tliis AREA 6514 DPM/100 SQ D* ALPl% MERAGE FOR GRID VI (DPM/!C $7 On) 0.9 WLRAGE BETA FIXED CINTMtINATION IN THIS ra f: 2456 DPM/100 SQ Di ALPHA !%XIMtM FOR GRID VI (DPMe!00 53 01) 19.9 BETA BACKG20!N!> 55 CRi BETS EFFICIDC(= 4.47. ALPl% MERAGE FOR CG{ TROL R001 17.2 ALPHA t%XIMLN FOR C'NTROL liDR1 89.5 ] %
- REST ROOM / SHOWER
~
Section I (3 X 3 meter grids)
'._ TeP W A L L.
[ 1 Ne<+% 1 1 i o < e m x b, a J
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O NTR OFFICE Section I (3 X 3 meter grid) TOP WALL tJoATH p LODR m f
' t t , A i C f
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WESTINGHOUSE NUCLEAR TRAINING REACTOR PAGE , FINAL RADIATI(N SURVEY DATA SHEET MARCH 1988 i LOCATICN I REGION SURVEY IGMt% SURVEY 1 METER I 91 EAR SURVEY ll 1 1 GROSS MAXIMtM: CPM iGROSS M ERAGE: CPM i FROM SURFACE I (DPM/100 SQUARE 01) lI DATE I ROOM i SECTION I GRID I REGION IBETA G#t% i ALPl% 18 ETA-GMt% i ALPHA l MICRO-R/ HOUR IBETA-GMt% i ALPl% ll l 1 I I I I I I- 1 I I ll 3/9/88 i REST RO&t / SHOWER I I I VII i 1 I 991 3.01 79.81 2.11 1
- 1
- 11
, BETA /G4tM i i 1 2 1 961 1.51 84.01 .71 1
- 1
- ll 1 1 I i 3 1 921 1.51 72.41 .91 16.71
- 1
- ll 3/16/88 I I I I 4 1 1071 3.51 91.61 1.41 1
- 1
- 11 ALPtM i i i 1 5 1 851 2.01 73.21 1.11 1
- 1
- Il i I I I I I ! I I I I II m i RESTRO&l/ SHOWER I I I VIII I 1 1 891 3.01 85.21 2.01 1
- I e ll I $%
I i i 2 1 551 1.51 47.01 .81 1
- 1
- 11 I I I I 3 1 1071 3.51 88.41 1.71 16.41 52.81 ll Y I I I I 4 l 1061 3.01 93.01 1.51 1 36.81
- 11
- i 5 1.51 60.01 .91
- I
- I i 1 1 891 1 11
-1 1 I I I I I I I I i 11 APRIL 7 1 0FFICE AREA I I i 1 1 1 1 681 21 51.01 1.41 1 22.31
- 11 1 I I I 2 1 61i 11 52.01 .41 1
- 1
- 11 1 I I I 3 1 601 11 52.61 .21 1
- 1
- ll 1 1 I I 4 1 691 11 53.41 .41 13.81 6.91
- 11 I I I i 5 I 661 01 57.01 0.01 1 145.41
- 11 1 1 I I I I I I I . I 11 I I I I I I I I -l I I ll PAGE MERAGE GROSS COLNTS: 03.3 1.9 68.6 1.0 t%XIMLH VALUES: 107.0 3.5 93.0 2.0 16.7 145.4
- sit 01 CATES RESULTS OF SMEAR LESS THAN ALPl% BACKGR0tN) FOR GRIDS (CPM) .7 STATISTICAL BACKGR0lND LLD BETA /G#t% (DPM/100 SQ 01) 29.4 MAXIMLM NET ALPl% C0tNTS THIS PAGE (CPM) 2.8 LLD ALPl% (DPM/100 SQ CM) .56 @ERAGE NET ALPHA C0lNTS THIS PAGE (CPM) .3 NERAGE G4t% BACKGROLND (CPM) 55.0 NAXIMlM ALPl% CONTM11NATI(N: (DPM/100 SQ 01) 55.7 BETA EFFICIENCY = 4.4% MERAGE ALPl% C0NTM11NATI(N: (DPM/100 SQ 01) 5.1 NERAGE BETA FIXED CCNTMilNATIIN (DPM/100 SQ 01)= 2066 MAXIMLH BETA FIXED CCNTM11NATI[N (DPM/100 S0 CH) = 7883
9 l l APPENDIX B FINAL RADIATION SURVEY DATA SHEETS SECTION II HALLWAY HEALTH PHYSICS LABORATORY JANITORS CLOSET WORKSHOP l l I l
SECTION 11 SURVEY Slkt%RY NLNBER OF GRIDS SURVEYED: 13 GRID DIMD4S!0NS: 2 X 2 METERS REGIONS PER GRID SURVEYED 2 mXIMLN FIXED ALPm CORM!tMTIG4 (DPH/100 SQ D1) 65.7 NERAGE FIXED ALPm C04TMIPMTitN (DfW 100 50 DI) 9.4 MXIMlN FIXED BETA-G#t% COU#ilmT104 (DPW 100 SO Di) 5609 WERAGE FIXED BETA-04t% CDUM!tMTID4 (DfW 100 SQ CH) 1724 FACILITY G#t% BACKGROLND (MICRO-R/HR) 14.6 t%X1tfli 04t% PADIAT104 LEVEL (MICRO-R/HR) 18.6 MERAGE G#t% RADIAT!G4 LEVEL (MICRD-P/HR) 15.2 t%XIM'Ji RD10VABLE BETA-04t% COUMIPMTIG4 (DPW100 S0 D1) !!2.2 MXIM'Ji REMOA8LE ALPm CG4TMItMTID4 (DfW100 S0 Qi) 5.6 1 1 l l Page B-1
l . HALLWAY Section II I (2 X 2 meter grids) I l l x/.. g L. d 2 / ( e 1 D r k . r C i+ x , ol sJ / j 4 ' d P 4 3 I
/
I
-J l
Page B-2 l
' HEALTH PHYSICS LABORATORY' )
.Section If (2 X 2 meter grics)
TOP WALL . I 3. tJoRT9 < FLDOR rn I 4 A J +a > 7 o o a e ' ~
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'1 M W /M do.L Page B-3
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WESTINGHOUSE NUCLEAR TIMINING REACTOR PAGE - - FINAL RADIATI(N SURVEY DATA SHEET MARCH 1988 i LOCATION I REGION SURVEY 1G4t14 SURVEY 1 METER I SMEAR SURVEY ll i IGROSS MAXIMLM: CPM IGROSS AVERAGE: CPM i FROM SURFACE I (DPM/100 SOUARE D1) 11 DATE I R0(M i SECTI(N I GRID I REGI(N IBETA GMt% i ALPim IBETA-G#t1A I ALPim i MICRO-R/ HOUR IBETA-GMt% i ALPHA 11 I I I I I I I I I l--- l 11 3/9/88 i HALLWAY I II I I i 1 1 781 2.01 70.61 1.31 1 55.31 2.711 BETA /GMt% i I I 2 I 801 2.51 70.01 1.51 14.41 79.71
- 11 1 I I I I I I I I I I 11 3/16 I I I 11 1 1 1 801 2.01 72.61 1.31 1 79.71
- 11 ALPim i I I t 2 1 921 2.51 73.01 1.51 13.41
- I 2.71&
I I I I I I I I I I I il i i i i I I I I I I i 10 3 o UTILITY R0(H I 11 I IV i 1 1 711 2.51 63.01 1.61 1
- I
- 11 BE 3 n i I I 2 1 651 3.01 59.01 2.01 12.7I
- I 5.610
- I I I I I I I I I I Il i' I I V i 1 1 861 1.01 74.81 .61 1
- I 5.619
- I I I 2 1 551 1.51 49.01 .81 12.51
- I 5.611 1 I I I I I I I I i 10 I I -l i I I l l I I I ll 3/7/88 I IEALTH IHYSICS LAB I II I III i 1 1 851 2.01 75.01 1.21 1 6.51
- IB BETA G4t% 1 1 1 2 I 871 2.01 74.61 1.41 14.11 112.21
- 11 I I I I I I I I I I I ll 3/11/88 I I I VI i 1 1 631 21 49.21 1.01 1 I ll ALPim I I I 4/7/88 1 2 1 721 41 63.81 2.01 1 I ll 1 I I I I I I I I I I Il i I I I l I I I I I i 19 PAGE NEIMGE GROSS C0lNTS: 76.2 2.2 66.2 1.4 PMXIMLM t% LUES: 92.0 4.0 75.0 2.0 14.4 112.2 5.6 sINDICATES RESULTS OF SHEAR LESS THM ALPHA BACKGROLM) FOR GRIDS (CPM) .7 STATISTICAL BACKGR0tta LLD BETA /GMt% (DPM/100 SQ 01) 28.2 MAXIMlM NET ALPim COLNTS THIS PAGE 3.3 LLD ALPHA (Dft1/100 SQ 01) .56 AVEl%GE NET ALPim COLNTS THIS PAGE .65 AVERAGE G4t% BACKGR0lND (CPM) 55 MAXIMLN ALPim C(NTM11NATI(N: (DPM/100 SG D1) 65.7 BETA EFFICIENCY = 4.47. MEl%GE ALPHA CCNTMtINATI(N: (DPM/100 SG D1) 12.9
#>EPAGE BETA FIXED CONTM1! NATION (DPM/100 SQ D1)= 1700 PMXIMLM BETA FIXED C(NTM11NATI(N (DPM/100 SQ D1) = 5609
1 l WORKSHOP Section II (2 X 2 meter grids) WA LL 1 9 - I gp K r
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WESTINGHOUSE NUCLEAR TIMINING REACTOR PAGE - FINAL 1%DIATI(N SURVEY DATA SHEET t%RCH 1988 i LOCATICN I REGI(N SURVEY IGNt% SURVEY 1 METER I SMEAR SURVEY 11 1 16ROSS t%XIMlM: CPM IGROSS MEIMGE: CPM i FROM SURFACE I (DPM/100 SQUARE CN) 11 DATE I ROOM i SECTilN I GRID I REGI(N 18 ETA G49% i ALPl% IBETA-GNtm ALPHA I MICRO-R/ HOUR IBETA-G#t% i ALPl% 11 1 I I I I I I I I I I 11 tmR 17,211 WORK SHOP I II i 1 1 1 1 75.01 1.01 65.01 .41 1 25.01
- 11 1 I I I 2 I 81.01 .51 68.01 .21 15.21 48.01
- 11 I SEVEN 2 METER X l I i i I I i l l I II I 2 METER GRIDS WERE I I 2 1 1 1 72.0! 1.01 44.21 .51 i e I n 11 i MEASURED WITH 2 1 l 1 2 1 74.Cl 1.01 63.41 .41 17.01 2.3I 2.Bil i REGIONS PER GRID I I I I I I I I I I ll y i CINSISTING OF 5 I l 3 1 1 1 92.01 1.51 75.21 .71 1
- I e ll g i POINTS PER REG 10N I I I 2 1 74.01 1.51 69.81 1.21 16.91 18.01 e il
, I I I I I I I I l l l Il 4 I I I 4 1 1 1 68.01 4.01 61.41 2.11 1 25.01 a ll 1 1 I I 2 I 74.01 1.51 65.21 .91 15.01
- I
- 11 1 I I I i 1 1 I I I I ll I I I 5 1 1 1 89.01 2.01 71.61 1.21 1 I e ll l l l 1 2 1 85.01 3.01 65.01 1.41 18.61
- I 2.81I I I I I I I I I I I I ll I I I 6 1 1 1 69.01 2.51 65.61 1.31 I e I e 11 I I I I 2 1 78.01 3.01 69.21 1.81 17.9! n 1
- ll 1 I I I I I I I I I I il i I i 7 1 1 1 73.01 1.51 64.01 1.11 1 10.01 a 11 1 I I I 2 1 66.01 2.01 63.41 1.11 1 a i 2.8ll 1 I I I I I I I i 1 1 11 a INDICATES SMEAR READINGS OF LESS THM OR EQlML TO STATISTICAL BACKGR0lND BETA-GMt% LLD (DPM/100 SQ CM)= 28 MEIMGE ALPHA BACKGROLND FOR AkE/. (CIH) .7 ALPHA LLD (DPM/100 SD (N) = 0.33 PROBE / DETECTOR EFFICENCY 8.5'./
M EIMGE BETA BACKGROLHD (CPM) 55.8 t%XIMLM BETA G49% FIXED CINTM11NATI(N : 107.0 CPM PROBE EFFICIENCY 4.4% MERAGE BETA G#t% FIXED C(NTNilt% TION : 77.5 CPM 1%XIftM ALPHA FIXED C(NT#tlNATI0N: 3.5 CPM M ERAGE ALPl% FOR AREA (DPM/100 SQ CM) 6.4 AVEl%GE ALPl% FIXED CCNTAMINATl[N: 1.3 CPM PMXIMLM ALPl% FOR AREA (DPM/100 SQ 01) 65.7 MERAGE BETA FOR AREA (DPM/100 SQ CM) 1742.2 t%XIMlM BETA FOR AREA (DPM/100 SQ (N) 5605.5
jA 4 k. m b- A 4% a 4-L ,.u-a 4--k4 -=2 - -
't e
9 APPENDIX C FINAL RADIATION SURVEY DATA SHEETS SECT I C- 4 III 1 REACTOR ROOM FLOOR REACTOR ROOM WALLS (LOWER 2 METERS) REACTOR ROOM WALLS ABOVE 2 METERS REACTOR ROOM CEILING REACTOR TANK REACTOR DUMP TANK d
- - - - - -- . ,. _-. -- . - _ _ . .- .. .. _ - . - _ - _ _ _ =
SECTIG4111 SURVEY Sltt%RY HlHBER OF GRIDS SURVETED: 217 GRID DiMENSledS 1 X 1 NETERS REGIONS PER GRID SURVEYED 1 t%XIMLH FIXED ALPM CONTMIt% TION (DPW 100 SG CM) 139 AVEPAGE FIXED ALPl% CONTMit% TION (DPW 100 S0 Di) 31.0 t%XIMLN FIXED BETA-G#t% CORMit%T104 (DW 100 S0 m) 5912 AVERAGE FIXED BETA-G#t% CONTM!t%Tlai (DFH/100 SQ CH) 810 , FACILITY G#t% BACKGR0tND (MICRO-R/HR) 14.6 1%XIMLN G4t% PADIATION LEVEL (MICPO-R/HR) 15.8 AVER *GE G#th RADIATIR4 LEVEL (MICRO-R/HR) 13.2 l%XIPdi REMOJABLE BETA-G#t% CONT #11tMTIQ1 (DPW100 SQ 01) 137.7 t%XIMLN REMOVABLE ALPm CG4T#11t%TIR4 (DPW100 SQ D1) 5.6 Pa9e C-1
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WESTINGHOUSE NUCLEAR TRAINING REACTOR PAGE _ f fit %L RADIATI(N SURVEY DATA SHEET t%RCH 1988 i LOCATIGi l REGION SURVEY IG#t% SURVEY 1 METER I 91 EAR SURVEY ll i IGROSS t%XIMLN: CPM IGROSS AVERAGE: CPM i FROM SURFACE I (DPM/100 SQUARE D1) ll DATE I R001 i SECTIIN l GRID IBETA GMtB i ALPl% IBETA-GMtm i ALPHA I MICRO-R/ HOUR IBETA-G#NA I ALPHA 11 1 I I I I I I I I I ll 3/23 IREACTOR R001 - FLOORI III I (1,1) 1 761 1.51 66.41 .41 mLL 1 e i e ll OETA/GMt% I I (2,1) I 761 2.01 65.81 1,41 WALL I 63.41 e ll l 1 I (3,1) 1 611 1.51 57.41 .41 WALL I 53.31
- ll 3/23 I I I (4,1) 1 691 .51 59.01 .21 WAI.L I 95.91 a 11 ALPIM i i I (5,1) I 741 2.01 64.01 1.11 WALL i 87.81
- 11 1 I I (6,1) 1 741 1.01 70.8I .41 WALL I 30.91 m Il i I I (7,1) I 751 1.01 65.01 .61 WALL i 14.61 e ll 1 1 I (8,1) I Bil 1.01 65.21 .51 WALL I e i n 11 y I I I (9,1) 1 651 0.01 65.01 0.01 WLL I e I a 11 3* -I I I I I -l i I I l ll I I I (1,2) 1 701 1.51 59.01 .61 WALL i 18.91
- ll
? I I I (2,2) 1 761 2.01 61.41 1.01 13.51 41.71 2.611 W I I I (3,2) 1 781 1.51 69.41 .81 13.11 34.11 e 11 I I I (4,2) I 741 1.01 69.41 .31 13.81 e i 2.611 1 I I (5,2) I 801 2.01 73.61 1.11 14.31 64.41 m Il i I I (6,2) 1 751 2.51 67.01 .81 14.51 a 1 2.611 I I I (7,2) I 701 2.01 62.81 1.01 14.51 a i n 11 I I I (8,2) I 78I 1.01 70.01 .51 15.61 a 1 a 11 I I I (9,2) I 471 .51 47.01 .51 WALL i 102.3I
- 11 1 I I I I I I I I I il i I I I I I I I I I il PAGE E'ERAGE GROSS COLNTS: 64.3 .6 14.2 t%XIMlM GROSS COLHTS: 81 2.5 15.6 102.3 2.6 ettOICATES RESULTS OF SMEAR LESS THW ALPtM BACKGROGO FOR GRIDS (CPM) .6 STATISTICAL BACXGR004D LLD 8 ETA /049% (DPM/100 SQ D1) 28.2 IMXIMIN NET ALPl% COLNTS THIS PAGE 1.9 LLD ALPl% (DPM/100 SQ 01) .56 AVERAGE hET ALPtM C0lNTS THIS PAGE .04 E'ERM G4t% BACKGROGO (CFM) 55.0 IMXIMlN ALPl% CONTMilNATI(N: (DPM/100 SQ 01) 37.8 BETA EFFICIENCY = 4.47. AVEIMGE ALPl% CtNTMilNATION: (DPM/100 SQ D1) .9 AVERAGE BETA FIXED CONTM11t% TION (DPM/100 SQ 01)= 1417 tmXIMLM BETA FIXED CtNTM11NATI(N (DPM/100 SQ D1) = 3941
WESTINGHOUSE tR! CLEAR TRAINING REACTOR PAGE ,. FINAL RADIATION SURVEY OATA SHEET mRCH 1988 I LOCATION I REGICH SURVEY 104t% SURVEY 1 METER I SMEAR .iURVEY ll l IGROSS f%XIMLM: CPM IGROSS AVERAGE: CPM i FROM SURFACE I (DPM/100 SQmRE 01) 11 DATE I ROGi i SECTI(N I GRID IBETA C#t% i ALPl% IBETA-G4tm i ALPHA I MICRO-R/ HOUR 18 ETA-GMt% i ALFHA 11 I I I I I I -l i I I ll 3/25 IREACTOR R0(N - FLOORI III I (1,3) 1 641 1.01 57.61 .41 ELL I n i 2.61I OETA/GMt% I I (2,3) 1 661 1.01 61.81 .51 14.31 3.81 a ll 1 1 I (3,3) 1 621 1.51 56.01 .81 13.71 3.81
- ll 3/25 I I I (4,3) I 721 1.51 59.61 .81 12.91 e I a 11 ALPHA I I I (5,3) 1 701 1.51 56.21 .41 12.61 a I n 11 1 1 I (6,3) I 791 2.5I 62.6l .61 14.31 79.51 m ll 1 I I (7,3) I 871 1.51 67.51 .71 14.11 64.41 s 11 1 I I (8,3) I 791 2.01 66.21 1.71 14.81 e i e 11 y i I I (9,3) I 561 1.01 56.01 1.01 1%LL i 18.91 a 11
- c -l i I I I I I I l- I ll n i I I (1,4) 1 671 1.01 59.21 .91 WALL I e i e ll g i I I (2,4) 1 691 1.51 62.41 1.01 11.91 3.81 e il i I I (3,4) I 751 1.01 43.61 .71 12.91 94.71 a ll I I I (4,4) l 501 .51 47.81 .21 12.51 34.11 e ll I I I (5,4) 1 591 2.01 51.41 1.11 12.21 79.5I e ll l l 1 (6,4) 1 731 1.5I 53.21 .51 12.81
- I e 11 1 I I (7,4) I 831 2.01 62.21 .91 13.21 3.81
- Il i I I (8,4) 1 731 1.51 61.41 .81 14.61 e I a 11 I I I (9,4) 1 781 0.01 78.01 0.01 WALL l e i e il i I I I I I I I l l ll I I I I I I I I I I 11 PAGE M/EPAGE GROSS COLNTS: 59.0 .7 13.3 1%XIMLH GROSS COLNTS 87 2.5 14.8 94.7 2.6 sIPOICATES RESULTS OF SMEAR LESS TiVN ALPl% BACKGR0lN) FOR GRIDS (CPM) 1.5 STATISTICAL BACK90LND LLD BETA /C#t% (DPM/100 SQ D1) 28.2 MAXIMlN NET ALPHA LOINTS THIS PAGE 1.0 LLD ALPl% (DPH/100 SQ D1) .56 AVEMGE NET ALPHA C0lNTS THIS PAGE .78 AVERAGE C#t% MCKGR0tND (CPM) 55.0 f%XIMLN ALPHA CCNTMilNATI(N: (DPM/100 SQ CM) 19.9 BETA EFFICIENCY = 4.4% AVEl%GE ALPl% C(NTMilNATI(N: (DPM/100 SQ 01) 0.8
#1ERAGE BETA FIXED CCNTM11NATI(N (DPM/100 SQ 01)= 612 t%XIMiti BETA FIXED CONT 411NATI(N (DPM/100 SG DC = 4851
~
~
WESTINGHOUSE NUCLEAR TRAINING REACTOR PAGE FINAL RADIATION SURVEY DATA SHEET mRCH 1988 i LOCATICN I REGI(N SURVEY IGNtm SURVEY 1 METER I !NEAR SURVEY ll l IGROSS MAXIMLM CPM IGROSS #1ERAGE: CPM i Frat SURFACE I (DPM/100 SQUARE 01) 11 DATE I ROGI I SECTI(N I GRID 18 ETA G4t% i ALPm 18 ETA-G#tm 1 ALPIM i MICRO-R/ HOUR 18 ETA-GNt% i ALPHA 11 1 I I I I I I I I I ll 3/24 IREACTOR R001 - FLOORI Ill I (1,5) I 791 1.51 66.41 .51 mLL I
- 1
- 11 1 I I (2,5) 1 781 1.01 71.81 .41 13.21 a 1 e Il l I I (3,5) 1 791 1.01 57.41 .61 12.41 m I n il i I I (4,5) 1 631 2.01 53.41 1.31 12.81 11.41 2.611 1 I I (5,5) I 581 1.51 48.21 .71 12.61
- I
- 11 I I I (6,5) 1 641 1.51 51.41 .61 12.91 e I
- ll l l 1 (7,5) I 901 1.01 62.01 .41 13.81 34.11
- 11 I I I (8,5) 1 791 2.01 56.81 1.21 14.51 e i e ll m i I I (9,5) 1 671 1.51 67.01 1.5I ELL I a i
- II
$* -1 1 I I I I I I I I 11 I I I (1,6) l 771 2.01 66.21 .91 mLL I e i e ll
? I I I (2,6) 1 811 1.51 67.01 .81 13.41 64.41 a 11
- I I I (3,6) I 731 1.01 66.41 .51 12.71 3.81 e il i I I (4,6) 1 741 1.51 57.41 .51 12.21 e I a ll l t 1 (5,6) I 601 1.51 51.61 1.01 12.11 26.51
- 11 I I I (6,6) I 781 1.01 65.41 .91 13.41 26.51 m Il i I I (7,6) 1 691 1.51 62.21 .91 14.71 56.81
- Il i I I (8,6) 1 811 1.51 69.61 1.01 14.31 49.21 a ll l 1 I (9,6) 1 771 2.01 77.01 2.01 MLL I
- l
- ll l l l l I I I I I I il i I I I l 1 I I I I ll PAGE #1ERAGE GROSS COLNTS: 62.1 .9 13.2 t%XIMLM M LUES: 90 2.0 14.7 64.4 2.6 eltOICATES RESULTS OF 9 EAR LESS THAN ALPl% BACKGROLND FOR GRIDS (CPM) 1.5 STATISTICAL BACKGR0lt4D LLD BETA /C#t% (DPtt/100 SQ 01) 28.2 PMXIMLN NET ALPim COLNTS THIS PAGE .5 LLD ALPl% (DPM/100 SQ D1) .56 #)ERAGE NET ALPIM COLNTS THIS PAGE 0.08 4/ERAGE GMt% EACKGROLND (CPM) 51.0 MAXIMLM ALPim CONTM11tMTI(N: (DPM/100 SQ D1) 9.9 BETA EFFICIENCY = 4.47. #JERAGE ALPHA C(NTN11NATI(N: (DPM/100 SQ D1) 0.0 4/ ERASE BETA FIXED CalTM11 NATION (DPM/100 SQ 01)= 1678
!%XIMLM EETA FIXED CONTM11NAT1(N (DPM/100 SQ D1) = 5912
WESTINGHOUSE NUCLEAR TRAINING REACTOR PAGE
~,
- Fit %L RADIATIDs SURVEY DATA SHEET l* 1%RCH 1988 i LOCATIW4 i REGl@i SURVE/ IGNtm SURVEY 1 METER I SMEAR SURVEY ll l l l GROSS t%XIMW1: CPM IGROSS AVERAGE: CPM i FROM SURFACE I (DPM/100 SQUARE D1) ll l
DATE I R001 i SECTI@i I GRID 18 ETA GMt% i ALPtM IBETA-G4t% i ALPHA I MICRO-R/ HOUR IBETA-GNt% i ALPHA 11 1 I I I -l i I I I I ll 3/25 IREACTOR RO&l - FLOORI III I (1,7) 1 631 2.01 59.61 .71 WALL I 34.11 a 11 1 I I (2,7) 1 751 2.51 64.81 .71 14.41 m I e il i I I (3,7) I 871 2.01 68.41 .91 12.6I e i
- ll 1 1 I (4,7) I 811 1.01 68.61 .61 13.31 e i n 11 1 I I (5,7) 1 691 2.01 68.61 1.31 12.91 m I e 11 1 I I (6,7) 1 771 1.01 65.61 .81 13.51 26.51 2.611 I I I (7,7) I 761 1.01 64.61 .71 15.41 56.81 5.3ll I I I (8,7) I 861 1.51 76.81 .91 15.11 3.81 a 11 l g i I I (9,7) i 491 1.51 49.01 1.51 WALL I e i 2.611
- o -1 1 I I I I I I I i 11 I I III I (1,8) I 681 1.01 59.01 .61 WALL l n i n 11 9 ll
- I I I (2,8) I 761 2.5: 62.81 1.21 13.11 e i e I I I (3,8) 1 641 1.01 55.81 .51 12.51 e i 2.611 I i 1 (4,0) 1 621 1.01 57.61 .71 12.31 3.81 2.611 1
I I I (5,8) I 701 1.51 58.01 .81 12.81 m i 2.611 1 I I (6,8) I 871 3.01 63.21 1.21 12.71 41.71 m ll 1 I I (7,8) 1 691 1.51 61.61 .81 14.3I e i 2.611 1 I I (8,8) I 751 1.51 63.41 .71 15.81 11.41 a ll I I I (9,8) I 701 1.01 70.01 1.01 WALL i 26.51 a 11 1 1 1 I I I I I I i 11 I I I l-- 1 I I I I i 11 PACE AVERAGE GROSS C0tNTS: 63.2 .9 13.6 t%XIM01 VALUES: 87 3.0 15.8 56.8 5.3 ' alt 01 CATES RESULTS OF SEAR LESS TION ALPla BACKGR0lND FOR GRIDS (CPM) 1.0 S ETISTICAL BACKGR0lFS LLD 8 ETA /G#t% (DPM/100 SQ 01) 28.2 MAXIMLM NET ALPl% C0lNTS THIS PAGE 2.0 LLD ALPl% (DPM/100 SQ D1) .56 AVERAGE NET ALPla C0lNTS THIS PAGE 0.01 NUERAGE GMt% BACKGR0tND (CPM) 55.0 MAXIMWI ALPl% CONTMilNATION: (DPM/100 SQ DI) 39.8 l BETA EFFICIENCY = 4.4'. / AVERAGE ALPl% C93TM11NAT194: (DPM/100 SG D1) 0.8 l NUERf4E BETA FIXED CONTMtINATION (DPM/100 SQ 01)= 1241
!%XIMLM 8 ETA FIXED CtNTM11tMTIlN (DPM/100 SQ D1) = 4851 l
l _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ t __7 _ ________ _ _ __ _ ___.____
ESTINGHOUSE NUCLEAR TIMINING REACTOR PAGE .
~
FitML iMDIATION SURVEY DATA SHEET t%PCH 1988 I LOCATI(N I REGI(N SURVEY IGMt% SURVEY 1 METER I SMEAR SURVEY ll I IGROSS 1%XIMLM: CPM IGROSS #/EIMGE: CPM l FROM SURFACE I (DPM/100 SOUARE DI) 11 DATE I R021 1 SECTIGt i GRID IBETA GMtm i ALPl% IBETA-GMtm I ALPIM i MICRO-R/ HOUR IBETA-GMt% i ALPIM 11 I I I I --I I I I I I ll 3/25 IREACTOR R0Gl - FLOORI 111 1 (1,9) 1 641 11 56.01 .51 WALL I e i e il I I I (2,9) 1 701 21 60.51 1.01 WALL I e I e 11 I I I (3,9) 1 601 11 58.01 .51 WALL I 45.41 e ll t i I (4,9) 1 541 11 49.51 .51 WALL I 6.91 a 11 I I I (5,9) 1 641 41 62.01 3.51 WALL I 122.31 2.811 I I I (6,9) 1 671 31 63.51 2.51 WALL I e i e ll 1 1 I (7,9) 1 591 31 55.01 2.51 WALL I 37.71 m ll yi I I (8,9) 1 631 21 60.51 1.51 WALL I e i n 11 gi I I (9,9) 1 511 11 51.01 1.01 WALL I e I a 11 n i l i I I I I i 1 1 11 4Ii I I I I I I I I I I I I I I I I I I il ll I I I I I I I I I i 11 1 I I I I I I I I I il I I - 1 I i 1 1 I I I ll 1 I I I I I I I I I 11 I I I I I I I I I i 11 I I I I I I I I I I ll I i 1 1 I I I I i 1 11 1 I I I I I I i 1 1 11 1 I I I I I I I I I ll PAGE A'EIMGE GROSS C0tNTS: 57.3 1.5 t%XIMitt UALUES: : 70 4.0 122.3 2.8 alm)lCATES RESULTS OF SMEAR LESS THAN ALPHA BACKGROLND FOR GRIDS (CPM) 1.0 STATISTitW. BACKGROLND LLD BETA /GMtm (DPM/100 SQ 01) 28.4 t%XIMLM ET ALPIM COLNTS THIS PAGE 2.0 LLD ALPl% (DPM/100 SG D1) BACKGROLND 0 #lEl%GE NET ALPim C0lNTS THIS PAGE .50 m/ERAGE GMtM LMCKGR0lND (CPM) 55.0 1%XIMLH ALPIM CCNTM11tMTI(N: (DPM/100 S0 01) 39.8 BETA EFFICIENCY = 4.4"/. M/El%GE ALPm CCNTMtIPMTI(N: (DPM/100 SG D1) 9.9 A/El%GE BETA FIXED CONTM11NAT10N (DPM/100 SQ 01)= 354 t%XIMLPt BETA FIXED CONTMilNATI(N (DPM/100 SG D1) = 2274
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WESTINGHOUSE NUCLEAR TIMINIPS REACTOR PAGE FINAL RADIATIDI SURVEY DATA SHEET t%RCH 1988 i LOCATID4 i REGIR4 SURVEY IG#t% SURVEY 1 METER I SMEAR SURVEY ll i IGROSS t%XIMIN: CPM IGROSS AVE AGE: CPM i FROM SURFACE I (DPM/100 SOUARE 01) 11 DATE I R001 i SECTimi i GRID IBETA GNtm i ALPHA IBETA-GMt1A I ALPIM i hlCRO-R/ HOUR 18 ETA-G#tm I ALPHA ll 1 1 I I I I I I I I ll 1%RCH 28 i REACTOR ROGi SOUTH I III I V1-1 I 761 51 66.81 3.01 1 45.41 e 11 TERU 31 1 IJALL l i V2-1 1 641 31 58.21 1.21 15.11 14.61 e il i I I VI-2 1 691 31 56.81 1.41 1 68.51
- 11 I I I V2-2 1 731 41 65.81 2.21 15.21 6.91 m ll 1 G#t% SURVEYS DG4E I I I I I I I I I II I CNE METER FRG1 THE I I VI-3 1 731 31 60.81 1.81 1 137.71 e il 11JAli. 44D G4E NETER I I V2-3 1 761 41 61.01 3.21 14.41 45.41
- Il 1 ABOVE THE FLOOR I I VI-4 1 561 31 47.41 1.61 1
- I e ll y i I I V2-4 1 541 41 49.81 2.01 13.21 m I e II
-g l I i i I I I I I i ll
- I I I V1-5 1 611 51 51.41 2.01 1 45.41 m 11 p i i i V2-5 1 641 81 48.01 3.61 13.01 a I n 11
- I I I VI-6 1 591 51 47.61 2.01 1
- I 5.611 I I I V2-6 1 571 71 51.21 3.61 13.71 14.61
- 11 1 I I I I I I I l I ll l l l VI-7 1 791 41 66.01 1.81 I e I n 11 I I I V2-7 1 681 41 61.81 2.21 15.11 22.3I
- ll 1 I I VI-8 1 831 41 67.01 1.41 1 14.61 m 11 I I I V2-8 1 741 41 64.81 1.81 14.31 e I a 11 I I I I I I I I I I ll 1 1 I VI-9 I 661 11 66.01 .61 1
- I m 11 I I I V2-9 I 611 21 61.01 2.01 C0 iter I e i e 11 i l i I I I I I I I il PAGE E'EPAGE GROSS COLNTS: 58.4 2.1 14.2 t%XIMai VALUES: 83 8 15.2 137.7 5.6 eltOICATES RESULTS OF SMEAR LESS TIMN ALPHA BACKGROLND FOR GRIDS (CPM) 1.0 STATISTICAL BACKGROLND LLD BETA /G#t% (DPM/100 SQ D1) 28.4 t%XIMLN NET ALPHA COLNTS THIS PAGE 7.0 LLD ALPIM (DPM/100 SQ 01) (BACKGROLND = 0) AVERAGE NET ALPIM COINTS THIS PAGE 1.08 A'ERAGE G#t% IMCKGR0lND (CPM) 55.0 t%XIMLN ALPIM C(NTM11t%T1R(: (DPM/100 SQ CM) 139.3 BETA EFFICIDiCY = 4.47. AVERAGE ALPHA CG(TM11 NATION: (DPtt/100 SQ D1) 21.4 AVEPAGE BETA FIXED C(NT#11tMTION (DPM/100 SD 01)= 517 inXIMlM BETA FIXED CD1TR11 NATION (DPM/100 SQ CM) = 4245
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WESTINGliOUSE NUCLEAR TRAINING REACTOR PAGE ,. FINAL RADIATICH StWEY DATA SHEET MARCH 1988 i LOCATI&l i REGl(N SURVEY IG4tm SURVEY 1 METER I SMEAR SURVEY 11 I IGROSS t%XIMLM: CPM lGROSS #1ERACE: CPM i FR&1 SURFACE I (DPM/100 SQUARE CM) iI : DATE I RO&t i SECTI(N I GRID IBETA GNtm I ALPHA 18 ETA-G#tm i ALPIM l MICRO-R/ HOUR 18 ETA-Get% 1 ALPHA 11 1 --I I I I I I I- I -- - - I ll l REACTOR R0(N WEST I III I VI-10 1 631 41 55.81 1.41 1 5 1
- 11 l WALL i i V2-10 1 721 31 70.01 1.81 COINER I e i s I! i l i I V1-11 ! 621 31 49.61 1.41 I e I e 11 l I I V2-11 1 801 31 72.01 2.21 13.11 e i e ll i i i i V1-12 1 52i 31 44.81 2.01 I e I
- 11 I I I V2-12 1 741 11 64.81 .61 12.51 m i n 11 o i I I V1-13 1 521 31 46.41 2.01 I 45.41
- 11 ;
.$ I I I V2-13 I 771 51 64.41 2.41 12.31 m i n ll
- 49! i I I I V1-14 1 31 43.41 1.81 e I e ll
? I I I V2-14 I 80) 31 70.81 1.81 12.81 e I a ll d i I I VI-15 I 511 41 43.01 2.61 I 30.01 m Il I I I V2-15 I 711 21 60.61 .81 12.71 68.51 s ll 1 I I VI-16 1 591 31 50.81 2.01 1 6.91 a 11 1 I I V7-16 I 731 41 65.01 1.41 14.31 e i e ll 1 1 I V1-17 I 661 41 53.81 2.61 1 22.31
- ll I I I V2-17 1 751 31 69.41 1.61 15.81 17.61 e 11 I I I VI-18 1 46l 21 44.01 2.01 1 37.71
- II I I I V2-18 I 691 71 63.01 3.01 COINER I 6.91 e ll l I- 1 l i I l ---I I I ll PAGE #!ERAGE GROSS COLNTS: 57.3 1.9 13.4 tmXIMLM VALUES: 80 7 15.8 68.5 0.0
- eIPE)ICATES RESULTS OF 9 EAR LESS TIMN ALP!M IDCKGR0tND FOR GRIDS (C:11) 1.0 STATISTICAL IMCKGR0tND LLD BETA /G4tM (DPM/100 SQ 01) 28.4 MAXIMtM ET ALPlM COLNTS THIS PAGE t. 0 LLD ALPHA (DPM/100 SQ 01) (BACKGR0tND = 0) AVERAGE NET ALPim C0tNTS THIS PAGE .78
#>ERAGE GMtM BACKGROLND (CRI) 55.0 MAXIMLM ALPIM CONTMillMTION: (DPM/100 SQ D1) 119.4 BETA EFFICIENCY = 4.47. AVERAGE ALPHA C(NTM11NATI(N: (DPN/100 SQ 01) 15.4 #1ERAGE BETA FIXED C(NTM11 NATION (DPM/100 S3 01)= 350 t%XIMLM BETA FIXED C(NTN11tMTI(N (CPM /100 SQ Dt) = 3790
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IJESTINGHOUSE NUCLEAR TRAINING REACTOR PAGE FINAL RADIATION SURVEY DATA SHEET 1%RCH 1988 ,. I LOCATI(N 1 REGIIN SURVEY IGMt% SURVEY 1 METER I 91 EAR SURVEY ll i IGROSS MAXIMtti: CPM 10ROSS M RAGE: CPM 1 FRm SURFACE I (DPM'100 S0lmRE 01) Il DATE I R0(M i SECTIIN I GRID IBETA G#tM I ALPl% 18 ETA-G#tM i ALPHA I MICRO-R/ HOUR IBETA-G#t% i ALPHA 11 1 I I I I I I I I I ll 1 REACTOR RORt NORTH I III I VI-19 I 761 21 65.41 1.21 1 6.91 e il I WALL i i V2-19 I 761 II 63.01 1.01 14.61 60.81 e ll 1 1 I V1-20 1 761 51 66.21 3.21 1 6.91
- ll 1 I I V2-20 1 62 31 58.21 1.61 15.11 6.91 a il i GMt% SURVEYS DONE I I I I I I I I l- Il I (NE METER Frat THE I I V1-21 1 631 41 57.21 3.01 I n 1 2.811 IWALL MO (NE METER I I V2-21 1 721 21 57.81 1.01 14.31 37.71 e il y I ABOVE THE FLOOR I I V1-22 1 621 41 55.01 1.81 l n i e ll o 1 I I V2-22 1 761 31 57.81 1.41 14.51 76.21 m II
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- I I I I I I I I I i 11 V1-23 671 57.41 2.01 45.41 *
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i I I I I V2-23 1 1 811 31 31 63.41 2.01 14.61 1
- 1 e 11 il i I I V1-24 I 891 31 66.21 2.01 i e 1
- 11 1 I I VI-24 1 761 21 64.81 1.01 14.81 e I a 11 l- 1 1 1 I I I l- l 1 ll l l 1 V1-25 1 671 31 58.81 1.61 I e I e ll l l 1 V2-25 1 641 41 57.21 2.21 15.61 e i 2.811 1 I I V1-26 I 641 31 56.01 1.61 I e I a ll l I I V2-26 1 701 51 63.21 3.51 15.61 e i e ll 1 I I I I I I I I I ll l l 1 V1-27 I 601 31 60.01 3.01 1 22.3I e II I I I V2-27 I 551 21 55.01 2.01 CORNER I 60.81 e ll 1 I I I I I I I I I il PAGE MRAGE GROSS C0tNTS: 60.1 1.9 14.9 1%XIMLM VALUES: 89 5 15.6 76.2 2.8 alm)lCATES RESULTS OF SMEAR LESS THAN OR EQtmL TO ALPHA BACKGROLND FOR GRIDS (CPM) 1.0 STATISTICAL InCKGROLND LLD BETA /G#t% (DPM/100 SG CM) 28.4 1%XIMt.M ET ALPl% C0tNTS THIS PAGE 4.0 LLD ALPl% (DPM/100 SQ D1) (BACKGROLND = 0) MRAGE NET ALPHA C0tNTS THIS PAGE .9 AVERAGE GMt% SACKGR0tND (CPM) 55.0 1%XIMLM ALPIM C(NTM11mTI(N: (DPM/100 SG D1) 7?.6 BETA ErFICIENCY = 4.47. MRAGE ALPIM CCNTMilNATI(N: (DPM/100 SQ 01) 17.5
#>ERAGE BETA FIXED CINTM11 NATION (DPM/100 S0 01)= 780 1%XIMLM BETA FIXED CtNTMtINAT13: (DPM/103 SQ 01) = 5154
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WESTINGHOUSE P4JCLEAR TRAINING REACTOR PAGE .
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FitML RADIATIRI SURVEY DATA SEET t%RCH 1988 i LOCATI(N I REGI(N SURVEY IGNth SURVEY 1 METER I SMEAR SURVEY ll , I IGROSS MAXIt'LN: CFM IGROSS #>ERAGE: CPM i FROM SURFACE I (DPM/100 SOUARE 01) 'I DATE I R001 i SECTI(N I GRID IBETA GNt% i ALPHA 18 ETA-GNtta i ALFm i MICRO-R/ HOUR IBETA-GMtm I ALPHA ll I I -1 1 I I I I I I il i REACTOR R001 EAST I III I V1-28 I NI 61 52.61 3.61 i e I e ll 1 WALL i I V2-28 i 5Bs 31 53.21 1.01 15.61
- I a 11 i I i i V1-29 1 771 31 63.61 2.01 1 14.61
- 11 I 1 i V2-29 1 691 31 59.01 1.41 14.71 53.11 e il i GMt% SURVEYS D(NE I I I i 1 I I I I 11 ;
I ONE METER FROM THE I I V1-30 1 761 11 58.21 1.01 1 e I e 11 IWALL #4D (NE tETER 1 I V2-30 1 791 41 61.81 2.61 14.71
- 1
- ll o I ABOVE TE FLOOR I I V1-31 1 731 51 60.01 1.61 I 22.31
- 11
$ I I I V2-31 1 771 41 64.41 2.41 14.71 e i e 11
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? I l i V1-32 1 641 31 57.01 1.81 1
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% I I I V2-32 1 771 21 65.81 1.21 14.71 a 1 2.811 1 I I VI-33 1 621 31 56.81 2.01 i e I e il I I I V2-33 I 701 31 66 01 1.61 13.61
- I e il i I I I I I I I I i 11 I I i ' 34 1 691 41 60.21 2.61 I e I e il i I l V2-34 1 72: 81 61.01 2.01 STAIRS I e i e il l I I V1-35 1 751 51 61.41 2.21 I e I e ll 1 1 I V2-35 I 771 31 68.61 2.01 15.11 6.91 e il i I I I I I I i l l 11 1 -
I I I I I I I I I ll FACE AVERAGE LGOSS CotNTS: 60.6 1.9 14.7 t%XIMLN VALUES: 79 8 15.6 53.1 2.8
- eJM)lCATES RESULTS ~5 9FAR LESS T!5N OR EQtlAL TO ALPIM MCXGR0tND FOR GRIDS (CPM) 1.0 CTATISTICAL BACTER 0tr9, .
LLD BETA /GRM. (DPF/106 SQ T71) ' 26.4 PWIMLN NET ALPHA C0tNTS THIS PAGE ,, 7.9 LLD ALPIM Cftt/faf SQ IM)' '(WXGROLND = 0) #>EMGE NET ALPIM C0tNTS THIS PAGE .94 WEIMGE 049% IMCXGROLND - %~M) -
. 55.0 t%XIMLM ALPm CONTN11tMTI(N: (DPM/100 SG Dt) 139.3 EETA Frr1CIDCf = 45. AVERAGE ALPIM C(NTN11NATI(N: (DPM/100 SQ 01) 18.7
#>EMGE BETA FIXED CalTMIPMTI(N (DPM/100 SQ Di}* 849 t%XIttN BETA FIXED C31TM11NAT10N (DPM/100 50 011 = 3638
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WESTINGHOUSE NUCLEAR TIMINING REACTOR PAGE ,. FINAL IMDIATI(N SURVEY DATA SEET t%RCH 1988 i LOCATI@l I REF10N SURVEY IGMtM SUR'KY
- tETER I SEAR SLRKY ll i IGROSS t%XItiM: CPti 16ROSS M EIMGE: CPM i FR91 SURFACE I (DPtV100 S0tMRE 01) 11 DATE I RO@t i SECT 194 i GRID IBETA GMtm i ALPHA IBETA-GMt% i ALPIM i MICRO-R/H0tiR IBETA-GMtm I ALPim iI I I I l- 1 1 1 1 -l I il I REACTOR RORt i III 1 C(1,5) I 65.01 5.51 54.61 2.81 12.21 87.81 2.71I i CEILING l 1 C(1,7) 1 58.01 3.51 46.61 2.51 11.71 e i e ll 1 I I C(5.5,4) I 60.01 4.61 45.21 6.51 11.21 e I = 11 1 I l- 1 I I I I I I il 1 REACTOR R001 SOUTH I III i V4-2 1 70.01 3.51 53.01 2.11 12.01 87.81 e il i UPPER L&LL I I V3.5 - 4.5 1 77.01 3.51 61.41 2.41 12.71
- I e 11 I I I V7-5 1 77.01 6.51 67.6' 3.41 11.81 14.61 e 11
- m -l 1 I I I I I I -l -l 11 6.01 58.41 5.11 11.81 71.51 e
$* 1 REACTOR R00M WEST I III I V4-11 1 73.01 11 I UPPER WALL i i V4-15 1 61.01 3.01 52.01 2.51 10.71 6.51 2.711 V6-17 77.01 7.51 65.21 5.01 13.91 63.41 *
? I I I 1 11
-G -l ! I I I I I I - -1 I il i REACTOR RO&t NORTH I I V3-19 t 80.01 6.01 67.61 5.01 15.61 87.81 e 11 I UPPER WALL 1 1 V4-19 I 74.01 6.01 65.01 4.21 14.21 e i 2.711 1 I I V8-22 1 71.01 8.01 61.41 4.61 10.81 95.91 e il i I I I I I I I- 1 1 11 i REACTOR RD@t EAST I I V7-28 1 76.01 5.51 62.41 3.81 12.71 e i e il i UPPER WALL i I V4-30 1 68.01 6.51 58.21 4.11 12.41 104.11 e 11 1 I I V6-30 1 63.01 4.41 55.61 7.01 12.91
- I e il l I ! I I I I I l- l 11 PAGE #KRAGE CROSS C0tNTS: 58.3 4.1 12.4 t%XIMLM VALUES: 80 8.0 '194.1 2.7 c!NDICATES RESULTS OF 91 EAR LESS TlWN ALPHA IMCKGREND FOR GRIDS (CPM) _
2.9 ' LLD, N
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LLD BETA /GMt% (DPM/103 SQ Dt) 28 MAXIttM NET Alf% COLNTS THIS PAGE _ 5.1 LLD ALPHA (DPtV100 59 D1) .48 AVERAGE NET ALPIM COLNTS THIS PAGE 1.2
#KPAGE G#t% BACKGROLND (CPM) 55.0 f%XIMLM ALPIM C(NTM11tMTI(N: (DPtV100 SQ DO .~ G1.5 8 ETA EFFICIENCY = 4.4% WEIMGE ALPIM C(NTM11PMTI(N: (DPtV100 So 01) V f 23;ct -
g- _ WEIMGE BETA FIXED CDRM11tMTIGi (DPfV100 SQ 01)= ' W ImXIMLM BETA FIXED C[NTRIDMTI(N (DPtV100 SQ 01) = c GM ._ [^ ~ ; '
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WESTINGHOUSE NUCLEAR TIMINING REACTOR PAGE FINAL RADIATION StFKY DATA SEET I IGMt1A SURVEY 1 lETER 1 SME/Jt SURVEY 11 I LOCAT1(N REGIG4 SURVEY l IGROSS PMXIMLM: CPM IGPOSS MEl%GE: CPM i FR(M SURFACE I (Df*t/100 SQUARE D1) Il DATE I ROOM I SECTl[N I GRID IBETA GMt% I ALPIM IBETA-GNtM i ALPHA I MICRO-R/ HOUR IBETA-GMtM I ALPHA 11 1 I I I I I I I I I ll RTB-1 601 45.31 1.01 i e 1
- Il APRIL 4 I REACTOR TM4K 1 111 1 1 21 43.01 1.61 6.91 e i BOTT31 1 i RTB-2 1 491 31 1 il l I I RTB-3 1 461 11 35.31 .31 i e I e il i I I RTB-4 1 461 21 36.71 .71 i e i e il i I I I I I -I I I I ll 32.31 .71 1 14.6C- e 11 l l l RTB-5 1 471 11 RTB-6 541 41.01 .71 1 14.61 e 11 1 I I 1 11 I I I RTB-7 I 441 31 49.71 1.71 I e I
- 11 1 I I RTB-B 1 38I 11 35.31 1.01 i e i e II I I I I 11 2l i I I I I 36.31 .71049% SUR'KY 1 ITTER I 14.61 e 11
%1 REACTOR BUTTD1 I I RTS-1 1 411 21 38.71 .71FRD1 BOTT[M AT CBRERI e I e 18 t n i SHELF I I RTS-2 1 421 11 RTS-3 431 21 39.01 .71 0F TM4K I 45.41 e 11 L1 I I 1 36.31 .71 7.51 e i e O I I I RTS-4 1 421 21 il i I I I I I I I I I il 3el 31 34.31 1.31GNtM SURVEY AT CENTER 6.91 e i I I RTS-5 1 il i I I RTS-6 I 511 11 42.31 .310F TN4K AT WAllGaAY I e i e il I RTS-7 I 471 21 38.31 1.31 EIGHT 1 e I e il i I l I I RTS-8 I 501 11 45.71 1.01 7.21
- I e 11 1 1 1 I I I I I I I 11 I RTW-1 1 341 31 29.61 1.61 1 22.31 e 11 1 REACTOR TM4K I 41.21 1.01 6.91 e I WALL i I RTW-2 1 531 31 1 il i I I RTW-3 1 441 11 35.01 .41 i e i e ll I I I RTW-4 1 401 21 36.01 .81 I e i e il i I I RTW-5 I 401 11 35.01 .81 i e I e Il i I I I I I I I I I 11 PAGE #>EPAGE GROSS C0tNTS: 38.4 .9 7.3 16.5 ERROR PnXIMLM GROSS COLNTS: 60 3 7.5 elm)lCATES RESULTS OF !NEAR LESS THM4 OR EQUAL TO ALPM BACKGROLND FOR GRIDS (CPM) 0.0 TE STATISTICAL BACKGROLND LLD BETA /G#t% (DPM/100 S0 Di) 28.4 PMXIMLM ET ALPHA C0tNTS THIS PAGE 3.0 LLD ALPIM (Dft1/100 SQ D1) (BACKGR0tte = 0) #KIMGE NET ALPIM C0lNTS THIS PAGE .95
#1EPAGE G49% EACKGROLND (CPM) 40.2 PMXIMlH ALPIM C(NTM11PMTICH: (Ditt/100 SQ 01) 59.7 BETA EFFICIB4CY = 4.4% #KIMGE ALPim CDUM111MTI(N: (DPM/100 SQ 01) 18.I
#>EPAGE BETA FIXED C(NTM11PMT10N (DPM/100 SQ 01)= 0 IMXIMLM BETA FIXED CCNT411tMT104 (DPM/100 SQ 01) = 3001
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IESTINGHOUSE NUCLEAR TPAINING REACTOR PAGE ~ Fital RADIATl[N SURVEY DATA SEET - l LOCATI(N I REGI(N SUR'KY IGM 9% SURVEY I METER I 9fAR StplVEY 11 1 IGROSS t%XIMLM: CPM 15POSS AL/EIMGE: CPM i FR&t SURFACE I (DfW100 SOUARE 01) 11 SATE I R0(N I SECTI(N I GRID IBETA GMt% i ALMM IBETA-E#t% i ALPIM i MICRO-R/ HOUR IBETA-GMt% i ALP 1M 11 I I l' I I I I I I I II APRIL 5 i REACTOR DtMP TME I ill I DTB-1 1 37I 21 29.31 1.01 9.91 14.61 e 11 i BOTT&1 1 1 DTB-2 1 471 01 43.01 0.01 10.31 37.71 e 11 1 I I DTB-3 1 381 11 34.31 1.01 10.21 e I e il i G#t% SUINEYS D(NE I I DTB-4 1 331 11 32.31 1.01 10.31 45.41 e 18 11 METER FR@t BOTT&l i I DTB 5 1 371 11 33.71 .31 10.41 6.91
- Il i JND IMLL i l DTB-6 1 381 21 34.01 .7I 10.71 14.61 e 11 I I I DTB-7 I 381 21 37.01 1.61 10.21 37.71 e II I I I DTB-8 I 44l 21 35.71 1.01 10.31
- I e ll I I I DTB-9 I 421 01 35.3I 0.01 10.61 22.3I e il i I I DTB-10 1 431 21 41.31 1.31 10.01
- I e ll 1 -I I l- 1 I I I I I 11 APRIL 5 i DtMP TM E WALLS - I I DTW 1-1 1 421 3I 33.61 1.41 i e i e il i 1 X 1 METER GRIDS I I DTW 1-2 1 381 31 35.61 1.61 i e I e ll IFIRST TWO NETERS FR@t i DTW 2-1 1 451 31 34.01 1.4! l 30.01 e il 2 i BUTT [M i 1 DTW 2-2 1 461 31 33.61 1.61 1 37.71
- 11 a 1 1 I DTW 3-1 1 371 31 33.41 1.21 I e i e II
- I I I DTW 3-2 1 44l 21 33.61 .81 I e I e ll n i I I DTW 4-1 1 361 21 30.21 1.21 i e i e ll 4, I I I DTW 4-2 1 401 41 31.21 2.01 1 53.11 e 11 m I I I DTW 5-1 1 411 41 33.41 1.41 I e i e Il i i 1 DTW 5-2 1 361 01 33.41 0.01 1 14.61 e il I I I DTW 6-1 1 331 31 27.51 1.21 I e i e ll I I I DTW 6-2 1 391 11 34.61 .61 i e i e 11 1 I I DTW 7-1 1 331 11 27.81 .8l I e I e il i i 1 DTW 7-2 1 361 11 33.61 .4I I e I e il i I I DTW B-1 1 431 11 31.81 .81 1 68.51 e il i I I DTW 8-2 1 411 21 34.01 .81 I e I
- 11 I I I DTW 9-1 1 391 31 34.21 1.01 I e I e il i 1 i DTW 9-2 1 401 01 31.41 0.01 I e i e il i I I DTW 10-1 1 341 31 31.01 1.21 1 68.51 e il i I I DTW 10-2 1 351 11 29.21 .41 i e i e 11 I I I I I I I l i I II PAGE #>ERAGE GROSS COLNTS: 39.2 1.9 33.3 .9 10.3 PMXIMLM UALUES: 47 4 43.0 2.0 10.7 68.5 allOICATES RESULTS OF 9fAR LESS THAN OR EQlIAL TO ALPIM BACKGROLND FOR GRIDS (Citt) 0.0 STATISTICAL inCKGROLND LLD BETA /G4t% (DPM/100 SQ D1) 28.4 f%XIMLM NET ALPle COLNTS THIS PAGE 4.0 LLD ALPIM (DPM/100 S0 (N) (IRCKGR0tto = 0) AVEP/4E NET ALPIM C0tNTS THIS PAGE .92
#>ERAGE GMt% BACKGR0lND (CPM) 40.2 !%XIMLM ALPIM C(NTM11 NATL [N: (DPM/100 S0 01) 79.6 BETA EFFICIENCY = 4.47. AVERAGE ALPIM C(NTM11teTI(N: (DPM/100 SQ 00 18.4 #>EIMGE BETA FIXED CINTMilfMTI(N (DPM/100 SQ 01)= 0.0 , t%XIlitM BETA FIXED C(NTM11NATI(N (DPM/100 SQ D1) = 1031
I APPENDlX D FINAL RADIATION SURVEY DATA SHEETS , SPECIAL SURVEYS HP LAB - LAB HOOD FACILITY UENTILATION AND DUCTS CEILING TILES CONTROL ROOM ELECTRICAL RACEWAYS TO REACTOR ROOM UTILITY ROOM SINK AND DRAIN DEMINERALIZER SYSTEM REACTOR WATER HEATER ; ONE & TEN INCH DUMP VALUES REACTOR TANK FILL P!PE BOTTOM REACTOR TANK AND SUMP AREA REACTOR TANK FILL PUMP - DEMINERALIZER PUMP REACTOR ROOM FUEL STORAGE AREA , REACTOR ROOM PIPE RACEWAY l REACTOR ROOM ELECTRICAL RACEWAYS REACTOR ROOM 1-BEAMS REACTOR ROOM CONTROL ROD PLATFORM l i l l
4 1 i l SPECIAL SUMYS $99Wrf L I NUh6ER OF CPECIAL $17/EY$ [24 [ 1%XIM FIXED ALPM CHMIST!W (DPW 100 SG CN) 99.5 MMGE FIXED ALPM CHMimTICH (DPW 100 SG CN) 23.0 i P%XIM FIXED BETA-G#t% CNM!mTION (DPW 100 SQ (M) 6973 MEGE FIXED BETA-G#t% CNMimTICH (DPW 100 SG CM) 237 i t%XIM RDG%BLE BETA-G#t% CNMimTION (DPW100 SQ CN) 144.7 1%XIM RDE%BLE ALPm CNM!mTI(N (DPW100 SG CN) 2.8 .1
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e WESTINGHOUSE NUCLEAR TMINING REKTOR PAGE FIEL IMDIATIM SURVEY DATA SHEET 1 LOCATI M FIXED CMTNilmTIM 36Mfm SUPVEY I METER I 9fAR SUINEY 11 I I GROSS CRI I FR91 SURFACE I (DfW100 SQUME DI) 11 DATE I IBETA-GNfm i ALPHA I MICRO-R/ HOUR IBETA-GNfm i ALPim 11 1 I I I I I I I I I 11 1 "ImitCH 31 i LAB HOOD: ImTER TIMP 1 481 21 1 71.51 e Il 1 1 1 I i 1 11 I INTERML SURFACES (10) 1 471 DI I e I e il i I 621 11 1 39.01
- Il l I 461 11 1 55.31 2.711 1 I 531 11 1 55.31 e II 1 I 411 11 13.41 128.51 e 11 I I 541 Oi 1 22.8I e II I I 561 01 1 39.01 e il i I 671 li I 79.71 e il l I 641 Il I 63.41 e il i I 631 11 I e I e il y
) $* 1 I I I I I e 11 I LAB HOOD: BEHIND TOP REAR PN4ELS 8 LOCATI@eS I 451 11 1 55.31 11
? I I 65I 11 1 144.71 e il y i I 611 Il I 47.21 e 11 I I 651 11 i e i e il i I 731 Il 1 30.91 e il i I 681 St I 71.51 e il i I 591 11 13.41 47.21 e il i I 491 Of I 112.21 e 11 I I I I I I 18 ILAB H000 EX)mUST VENT CAP #4D PIPE M ROOF I 501 01 7.91 79.71 e ll l l 1 I I I ll
- I 1A8 HOOD
- DfW4ERS #@ CABI!ET (12 LOCAT19fS) 1 541 01 1 55.31 2.711 I 501 11 I e i e 18 I l 701 Ol I 47.21 e 11 I I 571 01 1 47.21 2.7ll <
I I 611 Il i 22.81 e 11 i i I 651 11 1 30.91 e 11 1 I I 571 01 1 30.91 e il i I 451 St I 63.41 e 11 I I 591 11 i e i e II I I 661 81 1 55.31 e il i I 501 11 1 71.51 e il I I 54l 21 1 30.91
- Il I I I I I I 11
SPECIAL LAB SUPVEYS C(NTINUED I I I I I I ll 1 LAB HOOD: BEHIND DIWelERS (5 LOCATI(NS) 1 611 21 1 e i e il i I 441 11 1 95.91 e ll 1 I 541 21 1 39.01 e il i 1 421 31 1 55.31 e il l I 301 21 1 63.41 e ll l I I I I I ll 1 PLASTIC CATCH TN4K FRtM HOOD 2 LOCATI(NS I 471 31 i e i e il y i I 451 11 1 14.61 e 11 g I I I I i 1 II
- * -l i I I I I I I I I 11
? PAGE #>ERAGE GROSS COLNTS: 55.1 .?
y t%XIMlM VALUES: 73 3 144.7 2.7 cINDICATES PESULTS OF !MEAR LESS Tl#N OR E0lML TO ALP m DACKGROLND FOR GRIDS (CPM) 0.8 THE STATISTICAL BACKGR0lND LLD BETA /G#t% (DPM/ LOO SG D1) 28.4 t%XIMlM ET ALPm 00lNTS THIS PAGE 3.5 LLD ALPm (DPM/100 SG DO .48 #>ElmGE NET ALPim ColNTS THIS PAGE .92 NJUiAGE limtm imCKGR0lN) (CPM) 55 tmXIttM ALPHA CtNTN11tMTilN: (DPM/lOS SG D1) 57.7 BETA EFFICIENCY = 4.47. #1 Elm 6E ALPHA CtNT#iltMTI(N (DPM/100 SO Dt) 18.4 A/EPAGE BETA FIXED CINTMtIt%TIIN (DPM/100 SQ D0= B tmXIMLM BETA FIXED CINTM11mTI(N (DPM/ LOO SQ DO = 272? _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ - _ - o- -- _ . _ _
WESTINGHOUSE NUCLEAR TMINING REACTOR PAGE FINAL IMDIATIR4 SURVEY DATA SEET ; APRIL 1988 i LOCAT191 FIXED C(NTM11NAT![N 1G49% SURVEY 1 ETER I 9 EAR SURVEY ll i i I GROSS CPM i FRCH SURFACE I (DPlV100 SQUARE DD 11 l DATE I IBETA-GNt% i ALPm i MICRO-R/ HOUR 19 ETA-GMfm i ALPim 11 l 1 1 I I I I I I I 11 t%RCH 23 IAIR SUPPLY Cl#MBER LOCATED IN UPPER SECTICH OF WORKSHOP l 471 51 10.71 14.61 e II l TEN LOCATI(NS I 561 11 INSIDE I 55.31 e 11 l t INTERML SURFACES (10) I 531 21 10.11 e i e 11 l l l 481 11 INSIDE I 30.91 2.711 l l 1 481 21 11.81 55.3I e 11 1 I 621 11 OUTSIDE I 95.9I e 11 i l 1 561 31 12.41 e i e 11 I I 481 21 OUTSIDE l e i e il
,5 I I 561 01 13.91 e I e ll gE I I 671 11 OUTSIDE I 144.71 e 11 1 I I I I I ll
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I RETUDI AIR SUPPLY WORK SHOP AREA I 561 21 1 22.31 e 11 l . OFFICE AREA I 651 31 11.31 37.71 e 11 I I I I i l Il IREACTOR RD&l AIR SUPPLY GRILL i 481 11 1 30.91 e 11 1 I I I I I il IR00F MUSHRO@l E)0%UST CAPS FOR VENTILATICH (5) I 371 01 5.71 71.51 e il i I 491 21 1 55.31 e il i I 431 41 5.41 6.51
- Il i I 331 Oi 5.11 63.41 2.711 I i 54l 31 7.81 71.51 e 11 I I I I I i 11 ILAB HOOD EXIMUST VENT CAP MO PIPE IN ROOF I 501 01 7.01 79.71 e ll t I I I I i 11 1 I I I I I I I I i 11 PAGE # KRAGE GROSS ColNTS: 51.4 1.7 tmXIMLN VALUES: 67 5 144.7 2.7 ellOICATES RESULTS OF 91 EAR LESS TM4 OR EDUAL TD ALPm BACKGROWO FOR GRIDS (CPM) 0.9 TE STATISTICAL BACKGROWS LLD BETA /G4f% (DPM/100 SO 00 28.4 IR flWI ET ALPm C'E!S THIS PAGE 5.0 LLD ALPm (DPM/100 SQ DO .48 AVEl%GE NET ALPm COLNTS THIS PAGE 1.74
' #KTMGE G49% I%CKGR0lND (CPM) 55 f%XIliM ALPm C(NT#11mTIIN: (DPM/100 SQ 00 99.5 BETA EFFICIENCY = 4.47. AVEl%GE ALPm C(NTNtISTI(N: (DPlV100 SQ 00 34.6
#JERAGE BETA FIXED CDITM11mTIG4 (DPM/ LOO SQ 00= 0 t%XIMLM EETA FIXED CDITMiltMTIRI (DfW100 SD DD = 1819
ESTINGHOUSE NUCLEAR TMINING REACTOR I%GE f o FINAL 1%DIATID SURVEY DATA SIEET APRIL 1988 i LOCATI(N I REGI M SURVEY 1649% SURVEY 1 METER I 9fAR SURVEY ll i IGROSS t%XIMLM: CPM i GROSS CPM i FR(M SURFACE I (DfW100 SQtpRE 01) 11 DATE I RD91 i SECTI(N I GRID 18 ETA GMt% i ALPM IBETA-GMem I ALPl% 1 MICRO-R/ HOUR IBETA44tm i ALPl% 11 1 I I I -1 I i 1 1 1 11 1%RCH 31 IBRIEFING ROTI CEILING I I FR(NT I B61 31 81.41 2.21 I e I e il i TILE I I BACK l 991 21 86.41 1.01 I e I e Il i I I I I I I I I i 11 y ICINSOLE ROCM CEILINGl I I FR(NT I 801 31 73.61 1.01 i e i e 11 3* i TILE I I BACK I B61 51 76.81 1.81 i e i e 11 I I I I I I ll I I 82.41 2.01 I e I e
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10FFICE AREA CEILING I I FRONT 941 51 i e e 11 I TILE I I BACK I 891 21 78.21 .61 I il l I I I I I il IC(NTROL ROOM ELECTRICAL IMCEWAYS FROM REACTOR ROG1 4 SUR'KYS I 40.01 1.01 1 55.31 e 11 I I 30.01 3.01 I 87.81
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1 I 49.0; 1.01 12.7 1 55.31 e ll t 1 57.01 2.01 1 14.61 e il i I I -l i I II
-1 1 I I I I I I I I 11 PAGE MIMGE GROSS COLNTS: 66.3 1.6 t%XIMLF1 GRDSS COLNTS: 99 5.0 86.4 3.0 87.8 e s!!()lCATES RESULTS OF SMEAR LESS TM OR EQtML TO ALD
- MEYW0lND FOR GRIDS (CPM) 1.0 THE STATISTICAL EMCKGR0lte LLD BETA /GMt% (DPM/100 SG D1) 28.4 f%XIrilt1 Nff Alfr% COLNTS THIS f%6E 4.8 LLD ALPm (DfW100 S0 CM) (IMCKGROIND = 0) MP66 WT ALPm COLNTS TH15 PAGE .64 Mi%GE 649% IMCKGROLND (CPM) 55 r%XiliM AL** C(NTM11r%TI(N: (DfW100 SG CM) 79.6 BETA EFFICIENCY = 4.47. -MitcF ALPm CONT #GE71tN: (DfW100 SQ m) 12.7
#>E3MGE BETA FIXED C(NT# tit %TI!N (DPK/100 SQ D1)= 1710 tmXIMLM BETA FIXE 9 C(NTMIINATI(N (DPM/100 SQ D1) = 66M
- . - _ ~ _ . -. . . =. . _ .. IdESTINGHOUSE NLCLEAR TIMINING REACTOR MBE FINAL 1%DIATI(N SURVEY DATA SE ET APRIL 1988 4 LOCATI(N I REGllN SURVEY IGMfm SURVEY 1 tETER I 9 EAR SURVEY ll i IGROSS t%XIMLM: CPM i GROSS CPM i FROM SURFACE I (DfW !90 SQUARE 00 Il liATE I EOCM 3 SECTI(N I GRID IBETA GMt% i ALPtm IBETA-GMfm I ALPm i MICRO-R/ HOUR IBETA-GMfm I ALPm 11 'r_ ;~ -m ; I I -1 1 I I I I ll ttARD1 "J1 I leLLAY CEILM & 11 1 FRCHT I 851 41 73.01 1.21 I 6.91 e 11 1 T'LE i i BACK I 861 31 78.81 1.61 i e 1 2.811 1- - -----!-- 1 I I I I I I i 18 i 87.61 .81 68.51 e y I # LAB CEiniO I 11 FRCHT I 1011 21 1 11 i I 79.61 .81 I e I e
,g TELE I I BACK B71 41 11
-r g- - . ~ . - - - 1 I I I I Il p i E71LITv E(@l E!!M INSIDE SURFACE I 561 31 I e i e il c' I INSIDE SURFACE I 461 01 13.11 22.31 e il i DRAIN L&TER TIMP 1 491 11 1 45.41
- II l --- -- - 1 I I I I Il IbTit!TY RO&l FLCOR DICIN Tid 0 LOCATI(NS I 321 81 1 60.81 e 11 i I 531 01 I e I e il i I i l I i 11 4- I l --- I I I Il
- =-1-- ~ I I I I I i I I I il PAGE AGAGE GROSS COLNTS: 63.8 .9
!%KittJ1 VALUES: 101 4.0 87.5 3.0 68.5 e s!NDfCATiS RESULTS OF SMEAR LESS Tl#N OR FOUAL TO ALPm BACKGROLND FOR GRIDS (CPM) 0.8 THE STATItTICAL BACKGR0lte LLi BETA /G#f% (DfW150 S9 DD 28.4 t%XIMLM NET ALPIM C0tNTS THIS PAGE 4.8 LLD i Wie (DPM/198 sis 00 (SACKGR0lfe == 0) #EIMGE IET ALPm C0tNTS THIS PAGE .93 AGAGE G#tm BAL'GP0tND (CPP.) 55 f%XIt1LM ALPm CDNTMt!!# TION: (DPM/1BO SG 00 79.6 BETA EFFIL'ENCY = 4.47 #>ElmGE ALPim CINTM11PMTitM: (DPM/180 SQ DD 18.6 NEIMGE BETA FIXED C0NTn.'4TilN (DPMfla0 SQ 00= 1334 tmKIMLM BETA FIXED C(NTM11PmTI(N (DPM/1@ SG 00 = 6973
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WESTINGHOUSE NUCLEAR TMINING REACTOR PAGE ', FINAL IMDIATICN SUR'KY DATA SEET APRIL 1988 i LOCATI(N I REGItN SUPKY IGNtm SUR'KY 1 METER I 9 EAR SIRVEY 18 I IGROSS t%XIte: CPM IGROSS # KRAGE: CPM 1 FRW SURFACE I (DfW180 SQUARE DO 11 DATE I ROCH I SECTI(N I GRID IBETA GMt% I ALPHA IBETA-GNt% i ALPm i MICRO-R/ HOUR IBETA-GMt% I ALPm Il 1 -l i I I i 1 1 I I II APRIL 5 IPEACTOR TANK BUTT (N I III I DTR-1 1 501 31 42.01 1.31 l% 1 76.21 e 11 IINSIDE THE DW1P TmKI I DTR-6 I 421 21 33.01 2.01 tm I 6.91 e il i I I I I I I I I I 11 1Diff TmK SWF AREA I 32.01 1.01 I e i e ll l 1 I I I i 11 110 INCH DW1P t%LVE OUTLET I 19.01 2.01 1 37.71 e 11 I I I I I i 11 11 INCH DW1P LINE OUTLET I 39.01 1.01 1 14.61 e il 27 I I I I I I 11 W IRECIRC (RX TmK FILL) Ptte - IKET I 24.01 0.01 I 14.61 e il l OUTLET I 29.01 0.C8 1 60.81 e 11 a
& I I I I I I ll IDEMIN PLMP - I K ET I 27.01 2.01 i e i e 11 i OUTLET I 43.01 2.01 1 14.61 e il i I I I I I il 1 1 1 I I I I I I I il PAGE AVE E GE GROSS COWITS: 32.0 1.3 1%XIts GROSS C0lNTS: 50 3.0 43.0 2.0 76.2 0.0 c!NDICATES RESULTS OF 91 EAR LESS Ti#H OR EQUAL TO ALPim IV'XSR0tN) FOR GRIDS (CPM) 0.0 Tif ST;TISTICAL BACKGR0tN)
LLD BETA /GMtM (DPtV100 SG 00 28.4 tmXIts etT ALPIM COLNTS THIS PAGE 3.0 LLD ALPm (C4WIDO SG DD (IMCKGR0tND = 0) AVEMGE tET ALPtm COLNTS THIS PAGE 1.26
- XINGE GNtm IMCKGR0tN) (CPM) 40.2 t%XIMLN ALPlM CtNTm!!%TI(N: (DPM/100 SG DO 59.7 BETA EFFICIENCY = 4.4% 4KimGE ALPtm CtNTMIt%TIIN: (DfW100 SQ DD 75.8
- >DMGE BETA FIXED CLNTMINAT1(N (DPM/ LOO SQ D0= 0 f%XIMLN BETA FIXED CtNTmitmTI(N (DPM/1OO SQ 00 = 1986
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) .* f nESTINGHOUSE NUCLEAR TMINING REACTOR PAGE FImL IMDIATim SURVEY DATA SEET , APRIL 1998 1 I LOCATIM FIXED C M TMI mTI M 1G49% SURVEY 1 lETER l 9fAR St#VEY ll i I GROSS CPM I FIGI SURFACE I (DfWitt SOUARE 00 II , DATE I 19 ETA-Gefm I ALPm i MICRO-R/ HOUR IOETA-GM9% I ALPm Il i I I I I I I -l i I il 19RCH 25 IREACTOR Rom - FUEL ST0lmGE AREA 10 LOCATI WS I 431 11 1 30.81 e 11 I I 411 11 I 45.4I e il l I 401 81 l 91.61 e II I I 391 11 I e 1 2.tll l 1 461 Il i e I e il i I MI 41 I e I e il I I 62I 21 i e i e il y i I 63I 31 1 53.11 e 11 j I I 291 11 i e i e il
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f IESTINGHOUSE NUCLEAR TMINING REACTOR I%GE FINAL RADIATI(N SURVEY DATA SEET t%RCH 1988 I LOCATI(N I REGl[N SUR'KY 16M9% SUlFKY 1 tETER I 9fAR SUR'KY li i IGROSS 1%XIMLM CPM IGROSS #>E MGE: CPM i FR91 SURFACE I (Dfw100 SQUARE D1) 11 DATE I R0(M i SECTIIN 1 GRID IBETA GMt% i ALPm IBETA-GNt% 1 ALPm i MICRO-R/ HOUR IBETA-GMfm 1 ALPm Il I l- 1 i i I I I I I 11 1 REACTOR R091 I III I (1,2) 1 59.01 2.01 48.21 .91 i e i e 11 ICtNTROL ROD PLATF0lO11 I (2,3) 1 52.01 3.01 45.01 1.61 11.81 e I e il l I I (3,2) 1 60.01 2.01 50.PI 1.21 1 83.91 e 11 IP1ATFORM W S GRIDDEDI I (4,3) 1 57.01 2.01 49.4 .41 12.11 30.01 e 11 2 I IN 1 X 1 ffTER SQ l I (5,2) 1 56.01 2.01 49.61 1.21 I e I e 18 l$ !WITH INE THIRD SLPJEYED I (6,3) 1 68.01 3.01 49.81 1.61 10.11 45.41 e 11 o -l i I I I I I I I I 11
- 1 -l i I I I I I I I I il PAGE AVERAGE GROSS C:1NTS: 58.7 2.3 48.8 1.1 11.3 l%XIMlti UALUES: 68 3.0 50.8 1.6 12.1 83.9 CINDICATES RESULTS OF 9fAR LESS THet DR EQt%L TO ALP m BACKGROLND FOR GRIDS (CPM) O.I STATISTICAL BACKGROLND LLD BETA /G#f% (DPM/100 SG Dt) 28.4 t%XIMLM PET ALPim 00tNTS THIS PAGE 3.0 LLD ALPHA (DPM/100 SG D1) (DACKGROLND = 0) #JEM6E ET ALPm C0tNTS THIS PAGE 1.1 ATRAGE GMt% BACKGROLND (CPM) 55 1%X!MIM ALPm CONTM11mTI(N: (I W 100 SO Df) 59.7 BETA EFFICID4CY = 4.47. AVEl%GE ALPim CINTNtISTI(N: (DPM/100 50 01) 22.6 A'ERAGE BETA FIXED CINTN11PmTICH (DfW100 50 D1)= 0 t%XIMlM BETA FIXED C(NTN11mTI(N (DPM/100 SQ D1) = 1971
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