ML20045H851
| ML20045H851 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 05/31/1993 |
| From: | Neely D SEG ENGINEERS & CONSULTANTS, INC. |
| To: | |
| Shared Package | |
| ML20045H850 | List: |
| References | |
| NUDOCS 9307220009 | |
| Download: ML20045H851 (500) | |
Text
{{#Wiki_filter:. . - ._ ARMY MATERIALS TECHNOLOGY LABORATORY Q RESEARCH REACTOR DECOMMISSIONING FINAL SURVEY REPORT Volume 1 of 1 ! Revision 1 Controlled Copy 24 i Prepared by: - Scientific Ecology Group, Inc. 1560 Bear Creek Road . (~. Approved by: , d)$ v
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~9 3 Qy Vice President Radiological Engineering & Decommissioning Services Under contract io:
Morrison Knudsen Corporation 7100 E. Belleview Avenue, Suite 300 Englewood, CO 80111 For the: United States Army Corps of Engineers, New England Division MAY 1993 O$0393\PUlrSIT.A MTIMIN' RX\AMINDM49 ItEVISION 1 p$k kOOOK o j7 P
INDEX 7q AMTL REACTOR FINAL IEPORT v INDEX FOR IEVISION 1 PAGES i TIIE PAGE NUMllERS LISTED BELOW IIAVE BEEN CIIANGED OR ADDED AS REVISION 1 TO tills REPORT Title Page 7-9 ii 7-15 v 7-16 vii 7-17 1-2 7-17a i 5-6 7-18 5-7 7-19 ; 5-8 7-20 5-9 8-1 5-10 8-2 5-10a 9-2 5-11 B-1 ) 5-11a B-11 through B-21 5-20 B-21a 6-12 B-22 through B-32 ) 6-15 C-1 ) 6-16 C-5 6-20 C-6 6-22 C-8 6-29 C-9 6-36 D-3 1 6-37 D-4 7-1 D-7 7-2 D-8 7-7 i esownua snwmmmanunum REVISION 1 l
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EXECUTIVE
SUMMARY
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EXECUTIVE
SUMMARY
EXECUTIVE
SUMMARY
The U.S. Army Materials Technology Laboratory (AMTL) Research Reactor Facility was operated by the U.S. Army for materials testing and research purposes. The AMTL site is a part of the old Watertown Arsenal, originally estab .hed in 1816 to store, maintain, and issue small arms and ammunition. The open pool materials o search reactor was constructed in the late 1950s and became operational June 1960 under the Atomic Energy Commission (AEC), later the U.S. Nuclear Regulatory Commission (NRC), License number R-65 (Docket 50-47), The reactor was used to study molecular and atomic material structures and solid-state physics. The Research Reactor Facility consisted of Building 100 (reactor building), portions of Building 97, Cistern 242 and the secondary cooling system. Building 100 served as the containment structure for the reactor and also housed the control room, fuel storage racks, primary cooling system, a i gamma-ray experimental facility, and the electrical and mechanical service centers. Building 97 contained the support offices, laboratories and liquid-waste processing system. Cistern 242, an in-ground retention tank, functioned as the low-level liquid waste storage tank for the reactor. The ! secondary cooling system, located outside of Building 100, consisted of several pumps, the coolant sump, and underground piping and conduit between the sump and Building 100. ; During reactor operations, two incidents occurred that impacted the radiological conditions of the facility. The first occurred upon initial start up: primary coolant was observed leaking through the ' walls of the concrete pool (bioshield). Corretive actions were ineffective until 1966. At that time, the concrete pool was lined with stainless steel, and the leaks were successfully terminated. The second incident occurred in 1969 when a leak from Cistern 242 was obcerved. Immediate evaluations concluded that any release was below federal limits. A deactivation report was prepared and submitted to the AEC in December 1970 after the termination of reactor operations in March 1970. Subsequently, the reactor fuel, exhaust filters and stack, radioactive waste processing system, and many reactor components and support systems were removed and shipped off-site for disposal. The primary cooling water was processed and discharged, under the requirements of 10 CFR 20, to the sanitary sewer, , A study carried out by the U.S. Army Corps of Engineers (COE) recommended that the Research Reactor Facility be decommissioned by decontamination and dismantlement. Following NRC approval of the EG&G Decommissioning Plan for U.S. Army Materials Technology Laboratory Research Reactor, the Corps of Engineers contracted Stone & Webster Engineering Corporation, through ABB Environmental Services, to prepare the General Contractor Specificationsfor the Decommissioning, Demolition and Site Restoration of the U.S. Army Materials Technology Laboratory Research Reactor and contracted the Morrison Knudsen Corporation (MK) to perform ; the decommissioning. Under MK administration, the AMTL Project Procedures Manual was developed to ensure that the requirements of the Decommissioning Plan were satisfied and that i personnel, the public and the environment were protected. , O mmuunwennw2xsoo: e i REVISION 0
EXECUTIVE
SUMMARY
Baseo on the Decommissioning Plan and the Project Procedures Manual, implementing procedures O were prepared. Decommissioning activities commenced in June 1992. These activities included the removal and disposal of Cistern 242, the secondary cooling system, the reactor pool and internals, concrete platforms, piping, sump liner, and the gamma facility liner. To reduce radioactive waste volume, concrete blocks from Building 100 and the surface of Cistern 242 were decontaminated (scabbled), surveyed and free-released. Approximately 28,000 cubic feet of radioactive waste with a total activity of approximately 150 millicuries was generated during the decommissioning. The radioactive waste was transferred, through the U.S. Army Armament, Munitions, and Chemical Command to Chem-Nuclear, Inc., for disposal. Mixed wastes were transferred to the AMTL Facilities license to await shipment for disposal. Decommissioning activities were completed in January 1993. The total accumulated personnel exposure for this work was 1.29 person rem. Following the completion of the dismantlement and decontamination work, final surveys were performed by Scienti5c Ecology Group, Inc., using procedures which specified measurement requirements, survey instrumentation, and methods for data reduction and evaluation. The final surveys evaluated 100% of the areas addressed by the Decommissioning Plan for alpha, beta and gamma radiations. Instrumentation was selected to detect activation and by-product nuclides at approximately 50% of the guideline values with a 95% degree of confidence. Applicable guideline values were established by the NRC and the Massachusetts Department of Public Healtij. The results of all measurements taken during the final survey were found to be below applicable guideline values. Residual activity was within background levels, therefore a source term could not be identified to perform a pathway analysis. In view of these findings, it can be concluded that the O AMTL Research Reactor Facility licensee has fulfilled the requirements of the Decommissioning Plan and satisfied the acceptance criteria for the termination of the possession-only license and the release of Building 100 for unrestricted use. Additionally, there were no significant difficulties encountered which hindered the successful decommissioning. O omm nunuumrnaxwuinns il REVISION 1
O TABLE OF CONTENTS LIST OF FIGURES LIST OF TABLES P f O
TABLE OF CONTENTS r TABLE OF CONTENTS Executive S u m mary . . . ..........................................i List o f Fig u res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi List of Tables .... ...........................................vii 1.0 In trod uction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 1 2.0 Background Information . . . . . . . . . . . , . . . . . . . . . . . . . ... . .... .. . . 2-1 2.1 Facility Overvi ew . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 1 2.2 Decommissioning Purpose and Objectives .....................2-4 2.3 Management Approach . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 3.0 Operating and Post-Operating History .... .. ..... .. .. ...... .. . .. .. 3-1 < 3.1 Reactor Operating History and Experiments . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Radioactive Waste Management ..... ..... . .. ... .. .. .. .. ... 3-1 3.3 1.cals from Reactor Systems ..... .. ...... .. .. ......... . .. 3-1 3.4 Release from Cistern 242 ........... ... .. .......... .. .. 3-1 3.5 Post-Operating History . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 4.0 Site Description as of June 199 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 - 1 4.1 Buildings / Systems . . . . . . . . . . . . .... ... ....... ...... . . 4-1 4.1.1 Building 100 . . . . . . . ... ...... .... .... ..... 4-1 4.1.2 Building 97 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1.3 Cistern 242 . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . 4-3 4.1.4 Secondary Cooling System . . . . . . . . . . . . . . . . . . . . . . . . 4-3 4.1.5 Exhaust Stack Foundation ........................4-3 4.2 React o r Yard . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 4 -3 5.0 Decommissioning Activities . . . . . . .. . . . . . . .. . . . . .. . . .. . . . . . . . 5-1 5.1 Results of Previous Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.1 Site Characterization ...........................5-3 5.1.2 Summary of Hazardous Materials ....... . . . . . . . . . . . 5 -5 5.1.3 Summary of Radionuclides . . . . . . . . . . . . . . . . . . . . . . . . 5-5 5.1.4 10 CFR Part 61 Characterization . . . . . . . . . . . . . . . . . . . . 5-7 5.2 Decontamination Approach and Procedures . . . . . . . . . . . . . . . . . . . . 5-12 5.2.1 Decontamination Procedures . . . . . . . . . . . . . . . . . . . . . . 5-12 5.2.2 Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-12 5.3 Summary of Decontamination Activities ..... . .. ........ ... .. 5-14 5.3.1 Building 100 . . . . . . . . . . . . . . . . . . . .......... 5-15 5.3.2 Building 97 . . ... .........................5-18 5.3.3 Cistern 242 and Piping .......... . ..... .. . .. .. 5-18 5.3.4 Secondary Cooling System . . . . . . . . . . . . . . . . . . . . . . . 5-19 5.4 Occupational Exposures ........... . ...... ..... -.. .. 5-19 5.5 Waste Disposal . . . . . . ...... . . .. . . . . . . . . . . . . . . . 5-20 mmwastrarwmxw:nD iii REVISION 0
TABLE OF CONTENTS p 6.0 Final Survey . . . . . . . . . . . ..... ...........................o-1 V 6.1 I n trod u c tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 6-1 6.2 Final Survey Guideline Values ............................6-4 6.2.1 Building Surface Contamination Acceptance Criteria . . . . . . . . 6-4 6.2.2. Exposure Rate Acceptance Criteria . . . . . . . . . . . . . . . . . . 6-4 6.2.3 Soil Activity Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 6-5 6.3 Surveying Organization ................................6-5 6.4 Survey Design . . . . . . . , . . . . . . . .. . . . . . . . . . . . . . . . . . . . . 6-6 6.4.1 S urvey A reas . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.4.2 G rid Division s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 6.4.3 Survey Packages . . . ....... ..... ..... ... .. .. . 6-12 6.4.4 Background . . . . . . . . . . . . . . . . . . . . . . ......... 6-12 6.5 Minimum Detectable Activity Criteria . . . . . .. . . . . . . . . . . . . . . 6-14 6.6 Instrumentation and Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . 6- 1 7 6.6.1 Field Instrumentation . . . . . . . . . . . . . . . . . . .. .. ... 6-17 6.6.2 Laboratory Instrumentation .......,......... . . . . 6- 18 6.6.3 Instrument Calibration .........................6-18 ; 6.7 Final Survey Techniques . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . 6-19 6.7.1 Building Surface Scanning . . . . . . . . . . . . . . . . . . . . . . 6-20 6.7.2 Building Surface Measurements - Direct . . . . . . . . . . . . . . . 20 6.7.3 Building Surface Measurements - Removable . . . . . . . . . . . 6-2 0 6.7.4 Accessibility Restrictions . . . . . ......... . . . . . . . . 6-21 6.7.5 Building Exposure Rate Measurements . . . . . . . . . . . . . . . 6-21 j 6.7.6 Yard Soil Measurements . . . . . . . . . . . . . . . . . . . . . . . 6-2 1 6.7.7 Background Measurements . . . . . . . . . . . . . . . . . . . . . . . 6-22 6.7.8 Disposal of Samples . ......... . . . . . . . . . . . . . . . 6-2 3 6.8 Documentation . . . . . . . . . . . . . . . . . . . ............ . . . . 6-24 6.8.1 Final Survey Data Records .... .. .. .. . .... .... . 6-24 ; 6.8.2 Data Processing, Management and Control . . . .. . . . . . . . 6-24 6.8.3 Laboratory Databases . . . . . . . . . . . . . . . . . . . . . . . . . 6-2 6 6.9 Quality Assurance / Quality Control . .. . . . . . . . . . . . . . . . . . 6-2 6 6.9.1 Quality Assurance Programs . . . . . . . . . . . . . . . . . . . . . 6-2 6 6.9.2 Field Instrumentation . . . . ... . ........... ... 6-27 6.9.3 Laboratory Instrumentation ............. ... . . . . 6-29 6.9.4 Radioactive Sources . . . . ........... ...... . . . 6-31 6.9.5 Verification Surveys . . .........................6-32 6.10 Data Reduction and Evaluation . . . . . . .. ... ......... ... 6-32 6.10.1 Surface Surveys ..... ......... ....... . . . 6-32 6.10.2 Removable Activity Surveys . . . . . . . . . . . . . . . . . . . . . . 6-34 6.10.3 Exposure Rate Surveys . . . . . . . . . . . . . . . . . . . . . . . . 6 -3 4 6.10.4 Yard Soil Sample Analysis . . . . . . . . . . . . . . . . . . . . . . . 6-35 6.10.5 Background . . . ........... .......... . . . . . 6-3 6 6.11 Statistical Evaluation .. . ....... .... . . ...... . . 6-36 cmmunmumuwonone iv REVISION 0
TABLE OF CONTENTS
- 7. 0 S u n ey Findings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7- 1 7.1 Final Survey Results .. ... .. ....... .. . .... . ... .. .... , 7-14 7.2 Background Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-14 7.2.1 Building 100 S urfaces ~. . . . . . . . . . . . . . . . . . . . . . . . . . 7-14 7.2.2 Radiological Characterization of Buildings 36,60,111 and 131. 7-14 7.2.3 Off-Site Soil Measurements ......................7-15 7.3 Comparison of Final Survey Results to Guideline Values . . ...... .. . 7217 7.3.1 Building 100 Alpha and Beta Activities . . . . . . . . . . . . . . 7-17, 7.3.2 Building 100 Exposure Rate . . . . . . . . . . . . . . . . . . . . . 7-17al 7.3.3 Reactor Yard . . . . . ..................... . . . 7-18 7.3.4 Comparison to Massachusetts Criterion . . . . . . . . . . . . . . . 7-20 7.3.5 Building 100 Local Background Considerations . . . . . . . . . . 7-20
- 8. 0 Con cl u sion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8- 1
- 9. 0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-1 Appendix A Building 100 Data Appendix B Reactor Yard Soil Samples Appendix C Background Data Appendix D Summary of Equations Appendix E Photographic Essay of the AMTL Reactor Decommissioning l
l i l l l l i i i l 1 1 l l o.wwnunnumtummemwn v REVISION 1 l
LIST OF FIGURES , LIST OF FIGURES 2-1 Geographic Location of AMTL . . . . . . . . . . . . . . . ,, . . . . . . . . . . . . . . . . 2-2 2-2 A MTL Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 2-3 Functional Organization for Decommissioning and Final Survey Activities . . . . . . 2-6 4-1 Reactor Containment Shell Cross Sectional View .....................4-2 4-2 Isometric View of Cistern 242 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4 6-1 Building 100 Cross-Sectional View (Facing South) ......... . . . . . . . . . . 6- 8 6-2 Building 100 Basement Floor Plan ..............................6 6-3 Building 100 Operating Deck Floor Plan . . . . . . . . . . . . . . . . . . . . . . . . . 6- 10 6-4 Reactor Yard ..........................................6-11 7-1 Building 100 Cross-Sectional View (Facing South) . ............... ... 7-10 7-2 Building 100 Operating Deck Floor Plan ............. ............ 7-11 7-3 Building 100 Basement Floor Plan ... . .......... ............. 7-12 7-4 Drawing of Reactor Yard Showing Excavated Trenches and Soil Piles .. .... . 7-13 i r i O 022mewsnuwwnmmo22m vi REVISION 0
TABLE OF CONTENTS , LIST OF TABLES 5-1 Summary of Radiation and Removable Contamination Survey Results . . . . . . . . 5-2 5-2 Summary of EG&G Radionuclide Results . . . . . . . . . . . . ..... ....... 5-6 5-3 Summary of SEG Radionuclide Results ..... .....................5-7 Table of Nuclides from 10 CFR Part 61 Characterization ... ............. 5-8 5-4 5-5 Summary of Occupational Exposure ............................ 5-20 5-6 Radioactive Waste from Reactor Decommissioning .... . ... ........ 5-22 l 6-1 AMTL Final Survey Procedures . . . . . . . . . . .....................6-3 , 6-2 Acceptable Surface Contamination Levels . . . . . . . . . . . . . . . . . . . . .. . . 6-5 , 6-3 Final Survey Instrumentation Minimum Detectable Activity Values . . . . . . . . . 6- 16 6-4 Final Survey Instrumentation . . . . . . . . . . ........ . . . . . . . . . . . . . 6- 19 6-5 Instrument Source Check, Response Check and Calibration Requirements ..... 6-30 7-1 Final Survey Measurement Index .......... ... .... ... ........ 7-1 7-2 Building 100 Direct Surface Alpha Summary Statistics . . . . . .... . . . . . . 7-3 7-3 Building 100 Direct Surface Beta Summary Statistics . .. . . ........ . . . 7-4 7-4 Building 100 Removable Alpha and Beta Summary Statistics . . . . . . . . . . . . . 7-5 ; 7-5 Building 100 Exposure Rate at One Meter Summary Statistics . . .... . . . 7-6 7-6 Reactor Yard Soil Gross Alpha and Gross Beta Summary Statistics . . . . . . . . . . 7-7 : 7-7 Reactor Yard Soil Exposure Rate at One Meter Summary Statistics . . . . . . . . . . 7-8 l 7-8 Summary of Gamma Spectroscopy Analyses for Reactor Yard Soil Samples . . . . . 7-9 ! 7-9 Summary Results of the One Meter Exposure Rate Measurements from AMTL Buildings 36,60,111, and 131 .. ... .. ......... .. . .... .... ..... 7-14 : 7-10 Summary Results of the Gross Alpha and Gross Beta Off-Site Soil Analyses . . . . 7-15 i 7-11 Summary Results of Off-Site Soil Gamma Spectroscopy Analyses . . . . . . . . .. 7216 7-12 Summary Results of the One Meter Exposure Rate Measurements Taken at Each ; Off-Site Location . . . . . . . . . . . . . . . . . . . . ... . . ... ..... ... 7-16 i 7-13 Comparison of Building 100 Alpha and Beta Final Survey Results to Guideline Values ........................ ............. . . . . . . . 7- 17 7-14 Comparison of Building 100 Exposure Rate Final Survey Results to Guideline Values .. .................................. .. ... .. . 7-18 7-15 Comparison of Reactor yard Final Survey Results to Guideline Values . . . . . . . 7-20 7-16 Comparison of Building 100 Local Background to Highest Mean Exposure Rates ........................ . . . . . . . . . . . . . . ... . .. . 7-21 + ownrumstrurrwwxxsrur:xusosi vii REVISION 1 i
a a--- A a s- k -- m
- es O
1 10 INTRODUCTION O I d O
c ; LNTRODUCTION i l
1.0 INTRODUCTION
l O This fmal survey report for the U.S. Army Materials Te inology Laboratory (AMTL) 1
]
Research Reactor Facility has been prepared to meet t. : U.S. Nuclear Regulatory l Commission (NRC) requirements in 10 CFR 50.82, Applicationfor termination oflicense, i and 10 CFR 30.36, Erpiration and tennination oflicenses. This report also describes the ; decommissioning activities and fulfills requirements set forth by the Decommissioning Plan j for U.S. Army Materials Technology Laboratory Research Reactor prepared by EG&G l Idaho,Inc. i The Decommissioning Plan cites NUREG/CR-2082, Monitoring for Compliance with l Decommissioning Tennination Survey Criteria, June 1982, as the primary guldance document ! for fmal surveys. Final surveys also employed additional guidance from NUREG/CR-5849 l (Draft), Manualfor Conducting Radiological Surveys in Support of License Termination, l June 1992. This latter document provided updated approaches to final survey design, data ! analysis and documentation used by the Environmental Protection Agency for evaluation of ; hazardous material sites under Superfund (CERCLA). i Final survey acceptance criteria were , specifled in Guidance arulDiscussion of 17te purpose of the final survey was Requirements for an Application jo 10 demonstrate that residual Terminate a Non-power Reactor Facihty Operating License, September 1984. '"NI""I'I'Y I'Y#I# " 0'I"# "II guideline values applicable to O I This document references guideline values set forth by NRC Regulatory releasing the Research Reactor l Guide 1.86, Termination of Operating Facility for unrestricted use. ' Licenses for Nuclear Reactors, June 1974. In addition, the licensee supplemented the Decommissioning Plan with a submittal to the NRC (reference 9.4.4). This submittal required that the annual dose to an individual, resulting from continuous exposure to residual radioactive materials at the final reactor site, not exceed the Massachusetts unrestricted criterion of 10 mrem. The purpose of the fmal survey was to demonstrate that residual radioactivity levels are below all guideline values applicable to releasing the Reactor Research Facility for unrestricted use. l The report organization and material addressed in each section is summarized as follows:
- Background Information, Section 2 0, provides a basic description of the facility and identifies the decommissioning objectives, management philosophy and project organization.
O ~ t mmeumstrarwwxwo RD l-1 REVISION 0
l INTRODUCTION
-l, N
- Operating and Post-Operating History, Section 3.0, provides a summary of the experiments and processes conducted, as well as subsequent activities that prepared the facility for final decommissioning. This section also describes incidents which I
may have impacted the radiological condition of the facility.
- Site Description as of June 1992, Section 4.0, discusses the reactor facilities and yard ;
at the onset of final decommissioning activities. This section describes the condition . of the facility following the removal of various components (reactor, fuel, liquid waste processing equipment, etc.), which occurred subsequent to the Deactivation. Report submitted to the NRC in 1970.
- Decommissioning Activities, Section 5.0, summarizes the dismantlement and decontamination activities. Radiological characterization data obtained before and ;
during decommissioning are also presented. Additionally, radiation protection 4 controls, accumulated occupational exposure and quantities of radioactive waste generated are adhessed.
- Final Survey, Section 6.0, describes applicable guideline values, final survey-
- acceptance criteria, survey protocol and data evaluation methods. Quality Assurance and Quality Control are also discussed.
= Final Survey Findings, Section 7.0, summarizes final survey results. Summary tables provided in this section correspond to data provided in Appendix A. This section also provides a comparison of the survey results to the applicable guideline values and background measurements.
- Conclusion, Section 8.0, summarizes the disposition of radioactive material and survey results with respect to license termination and releasing the facility for unrestricted use.
- References, Section 9.0, lists documents which provided guidance for the preparation of this report or were directly cited.
- The appendices, A through E, contain the individual survey results, a summary of equations used, and a photographic essay of the final decommissioning.
The Phase II soil samples outlined in' the Decommissioning Plan will not be perfdrsied? This
~
decisionivas based on direction provided through a telephone conversationf with the NRC; The Phase 11. soil samples:would ~not _ add to the information already obtained during. the Phase l' soil sampling provided in this report. The Decommissioning Plan does not address groundwater evaluations. Groundwater wells located on the AMTL site are not within the geographic bounds of the Research Reactor Facility. Groundwater evaluations will be addressed as part of the decommissioning of the ' AMTL Laboratory Facilities. O ese mr.scrwmemmrarsn* 1-2 REVISION 1
m INTRODUCTION
/
- Operating and Post-Operating History, Section 3.0, provides a summary of the 5
experiments and processes conducted, as well as subsequent activities that prepared the facility for final decommissioning. This section also describes incidents which may have impacted the radiological condition of the facility.
- Site Description as of June 1992, Section 4.0, discusses the reactor facilities and yard at the onset of fmal decommissioning activities. This section describes the condition of the facility following the removal of various components (reactor, fuel, liquid waste processing equipment, etc.), which occurred subsequent to the Deactivation Report submitted to the NRC in 1970.
- Decommissioning Activities, Section 5.0, summarizes the dismantlement and decontamination activities. Radiological characterization data obtained before and during decommissioning are also presented. Additionally, radiation protection controls, accumulated occupational exposure and quantities of radioactive waste generated are addressed.
+ Final Survey, Section 6.0, describes applicable guideline values, final survey acceptance criteria, survey protocol.and data evaluation methods. Quality Assurance and Quality Control are also discussed.
- Final Survey Findings, Section 7.0, summarizes fmal survey results. Summary tables provided in this section correspond to data provided in Appendix A. This section also provides a comparison of the survey results to the applicable guideline values and background measurements.
- Conclusion, Section 8.0, summarizes the disposition of radioactive material and survey results with respect to license termination and releasing the facility for unrestricted use.
- References, Section 9.0, lists documents which provided guidance for the preparation of this report or were directly cited.~
- The appendices, A through E, contain the individual survey results, a summary of equations used, and a photographic essay of the final decommissioning.
The Phase ll soil'sainples outliiied in the Decommissioning Plan will not be' performsd.1 This decision was based on direction provided through a telephone conversat_ ions.with the NRC. The Phase 11' soil samples ~ would not add to the information already obtained _during}the Phase i soil sampling provided in this report. The Decommissioning Plan does not address groundwater evaluations. Groundwater wells located on the AMTL site are not within the geographic bounds of the Research Reactor Facility. Groundwater evaluations will be addressed as part of the decommissioning of the AMTL Laboratory Facilities. O mamwnsnwnureuxurm a 12 REVISION 1
INTRODUCTION Upon completion of the decommissioning, original records associated with the final surveys
- will be retained by the licensee, as required by NRC regulations.
1 O 03m9uumstrw.trurw.nxiooi no 1-3 REVISION 0
2.0 BACKGROUND
INFORMATION Facility Overview Decommissioning Purpose and Objectives Management Ap; e, eh O O y---y - -w wg - .-m-,g ,ww-w q er-w q r--w --e" y
BACKGROUND INFORMATION
2.0 BACKGROUND
INFORMATION 2.1 Facility Overview The AMTL Research Reactor Facility, k>cated on the site of the old Watertown Arsenal in Watertown, Massachusetts, (Figure 2-1) was constructed in the late 1950s. The Research Reactor Facility consisted of Building 100 (the reactor building), portions of Building 97, Cistern 242, and the secondary cooling system. Building 100 was constructed as a containment structure for the one MW pool-type materials testing reactor. Building 100 also housed the control room, fuel storage racks, primary cooling system, a gamma-ray experimental facility, and the electrical and mechanical service centers. . Building 97 contained support offices, laboratories and the liquid radioactive waste processing system. Cistern 242, an in-ground retention tank, was used as a liquid radioactive waste holdup tank. The secondary cooling system adjacent to Building 100 was comprised of cooling towers, pumps and a sump. Figure 2-2 shows the location of the reactor facility on the AMTL site. The reactor became operational in June 1960 under the Atomic Energy Commission (AEC), later the U.S. Nuclear Regulatory Commission, license Number R-65 (Docket 50-47). The license was issued to the AMTL Commander. The reactor, operated by the Army for the Department of Defense, was used to conduct studies of radiation effects on materials and for solid-state physics research. The license was initially amended to increase the power level to two MW, and amended again later to increase the pcwer level to five MW. Reactor operations ended in March 1970. A deactivation Decointnissioning began in June 1992 report was prepared and and was cornpleted in January 1993. submitted to the Atomic Energy 1 Commission. Subsequently, the fuel, some reactor components, the liquid radioactive waste processing system and some radioactive and non-radioactive materials were removed. The initial characterization was performed in 1990, and a Decommissioning Plan was subsequently developed and approved by the NRC. Decommissioning began in June 1992 and was completed in January 1993. O m.wrumsmumwaxwuo 2_1 RD'ISION 0
BACKGROUND INFORMATION Boston Massachusetts Area i k Watertown North
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BACKGROUND INFORMATION 2.2 Decommissioning Purpose and Objectives O The purpose of the decommissioning project was to terminate the NRC license and release the reactor facilities for unrestricted use in conjunction with the closure of the AMTL base, scheduled for 1995. The objectives of the decommissioning were to:
- Comply with federal and state regulations regarding license termination;
- Ensure the health and safety of the decommissioning personnel and ,
public;
- Protect the environment from unmonitored releases of radioactive or hazardous materials;
- Reduce licensed radioactive materials to levels as low as is reasonably achievable (ALARA); ,
- Conduct the decommissioning activities in a cost-effective manner and dispose oflicensed radioactive materials by December 1992;
- Demonstrate that residual licensed radioactive materials were below acceptance criteria for license termination; and O
- Release the AMTL Research Reactor Facility for unrestricted use.
2.3 Management Approach The AMTL Commander, as the licensee, was responsible for the decommissioning project. Project management was conducted through the U.S. Army Corps of Engineers, New England Division, which contracted the Morrison Knudsen Corporation (MK) as the prime contractor for the decommissioning. MK was responsible for developing work procedures and work plans, directing construction, dismantlement and decontamination activities, and directing craft labor and subcontractors. MK subcontracted various elements of fae project. Scientific Ecology Group, Inc. (SEG), was contracted to support radiation protection, radwaste management and to perform the final status surveys. The Corps of Engineers also contracted the Stone & Webster Engineering Corporation to perform quality assurance reviews and audits to ensure that work was conducted in accordance with the contract terms. Roy F. Weston was contracted by AMTL to provide assistance to the Radiation Protection Office for project oversight. The U.S. Army Armament, Munitions, and Chemical Command contracted Chem-Nuclear, Inc., for radioactive waste disposal. O umsmmscrenwwmm 2-4 REVISION 0
BACKGROUND INFORMATION 1 i Additionally, the Massachusetts Department of Environmental Protection conducted on-site oversight through a contract with Mr. John Robinson. A qualified manager was responsible for each major aspect of the project. These ! managers had prior decommissioning, health physics and safety experience. The MK j Project Manager held the same position on a previous project and had over 12 yew of management experience. The Radiation Control and Safety Officer was a Certified i Health Physicist with experience in industrial safety and industrial hygiene. The ; Health and Safety Manager had over eight years experience developing and implementing health and safety programs for hazardous and radioactive waste sites l and was a Certified Industrial Hygienist. A management organization chart is provided in Figure 2-3. Project management personnel were required to complete comprehensive Radiation Worker Training and OSHA Hazardous Waste Operations Training. Additional site specific training detailing safety responsibilities associated with assigned positions was provided for management and supervisory personnel. Current regulatory guides and project plans were utilized by management to maintain a high standard of safety and quality throughout the decommissioning. All decommissioning activities were performed in accordance with federal and state regulations without compromising the schedule, budget or the Decommissioning Plan requirements. Personnel radiation exposures and residual radioactive materials were maintained ALARA. Decommissioning support programs were also implemented to review and monitor health and safety training, radiation monitoring instrumentation, security, maintenance i of ALARA conditions, compliance with regulations, and document control. Site specific plans and procedures, weeldy management and safety meetings, and surveillance and self-assessments in areas of health and safety and radiation protection were the approaches used by management to ensure quality and safety during the decommissioning. O ammuurrwrrtumm
- 2-5 REVISION 0
BACKGROUND INFORMATION s
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1 i l l 1 3.0 OPERATING AND POST-OPERATING HISTORY Reactor Operating History and Experiments Radioactive Waste Management Leaks from Reactor Systems Release from Cistern 242 ; Post-Operating History I l 1 l O
OPERATING AND POST-OPERATING IIISTORY t 3.0 OPERATING AND POS .'-OPERATING IIISTORY 3.1 Reactor Operating IIistory and Experiments The AMTL Research Reactor Facility was operated by the Army Ordnance Corps from 1960 to 1970. Various solid-state physics research programs and experiments were conducted by the Army Materials and Mechanics Research Center (AMMRC). ! Ixcal universities ude use of the AMTL reactor for diffraction measurements and l irradiations. Experiments with composite materials, metal alloys and ceramics were also performed before reactor operator were concluded on March 27,1970. Based on the operation reports and facility safety reports, there were no indications that fuel integrity was breached duriag reactor operations or fuel transfers. , 3.2 Radioactive Waste Management ' Past radioactive waste management practices by the licensee were reviewed. For the l ten-year period of reactor operations, no record or evidence of solid radioactive waste burial on-site was found (Reference 9.3.4). There was no storage or accumulation
- of such solid wastes in Building 100, Building 97 or the yard. Liquid radioactive wastes were process d in Building 97 prior to discharge to the sanitary sewer. No radioactive waste management practices associated with the operation of the reactor were identified that would impact the effectiveness of the decommissioning project. ;
3.3 Leaks from Reactor Systems i During initial operations, reactor cooling water was observed leaking through the ; concrete pool wall (biological shield). In an attempt to rectify the problem, the annulus was drained, and glass tape and epoxy resin were applied to all wall and floor joints and annulus surfaces. Aluminum drain lines were provided to draw off any water around the annulus when it was emptied. These lines also leaked and were subsequently plugged. Although this reduced the problem, it did not completely stop > l the leakage. , In 1961, a second attempt was made to stop the leakage. Two-inch diameter holes were drilled into the cavity, and lean cement mix was injected into the holes. When this proved to be unsuccessful, a liquid chemical grout was used. This method, along with the use of pressure-sensitive tape around each beam tube joint, eliminated approximately 75% of the leaks. Some small leaks continued intermittently, but did not affect reacter operations. l O : I mun-runummm num no 3-1 REVISION 0 l
OPERATING AND POST-OPERATING IIISTORY O A stainless steel liner was installed in the reactor pool in 1966, and this eliminawd the leaks. In 1968, the space between the stainless-steel liner and the pool wall was connected by a drain to the basement sump in order to remove any residual water. The water that leaked through the biological shield did not cause any major contamination spread outside the shield. In July 1963, the cooling system heat exchanger developed a leak. The heads were pulled, and a corroded leaking tube was plugged. Tube leaks developed on four other occasions. To remedy this problem, the aluminum tube bundle was removed and replaced with one made from stainless steel, and a recirculating water-cooling tower was installed to provide secondary cooling. No further leaks were detected following the completion of these actions in January 1965. 3.4 Release from Cistern 242 A loss of radioactive liquid waste occurred from Cistern 242 between February 20 and 27,1969. The loss was detected after a review of the records from the tank level recorder revealed that the level of the tank contents dropped from 15 to 11 feet during this period. An analysis of the cistern centents determined that the gross activity of the liquid was 5.7 x 10' pCi/ml. The Reactor Facility Safety Committee concluded that the radioactive material was below the limit set by 10 CFR 20 (AhiMRC, Report ofInspection, CO Report No. 47/69-1, U.S. Army Materials and Mechanics Research Center,1; cense No. R-65, Category E, May 8 and 9,1969). 3.5 Post-Operating IIistory On March 27, 1970, reactor operations were concluded, and the reactor was shutdown. A deactivation report, Deactivation Report ofthe AMMRC, December 8, 1970, was submitted to the Atomic Energy Commission, Division of Reactor ' Licensing, and to the Army Reactor Committee for Health and Safety in December 1970. Subsequently, materials and components were removed from the reactor facilities and yard and then disposed of as follows:
\
- 1rradiated and unirradiated fuel elements containing special nuclear '
material were removed and returned to the Atomic Energy Commission. Beryllium oxide (BeO) reflector elements, shim-safety rods, armatures and stainless-steel pieces from the guide tubes were disposed of as high-level radioactive waste. O omurunrrwen uwsx" " 3-2 REVISION 0 i 1
OPERATING AND POST-OPERATING HISTORY
- Fission chambers containing U-235 were transfe red to another reactor O' facility.
- Ionization chambers were disposed as low-level radioactive waste.
- Radioactive sources used for calibration and check of survey meters were transferred to the Army Radiation and Occupational Safety Branch, Army Materials and Mechanics Research Center Command.
- The reactor exhaust stack and the secondary cooling towers were disposed of as clean waste.
Water from the primary and secondary cooling systems, secondary coolant sump, main reactor pool, fuel stor ge racks, and Cistern 242 was drained and monitored for radioactivity. The water was discharged directly to the sanitary sewer if found to be below regulatory limits or processed to acceptable release criteria before discharging. The following radioactive liquid waste processing system equipment was removed from Building 97 for disposal in order to accommodate the installation of a particle accelerator:
- Three X)0-gallon liquid waste storage tanks.
- Disposable ion-exchange system vessels.
- Pool fill, make-up and laboratory demineralizer system.
- Pumps, valves and piping associated with the above systems.
O amanmrrun.,rersxu" " 3-3 REVISION 0
10 1 l l 1 . l O 1 I 4.0 SITE DESCRIPTION AS OF JUNE 1992 u Buildings / Systems
- Reactor Yard O
SITE DESCRIPTION AS OFJUNE 1992 4.0 SITE DESCRIPTION A3 OF JUNE 1992 s Following the deactivation of the Research Reactor Facility in March 1970, certain reactor hardware, auxiliary support systems and radioactive materials were removed. The following is a description of the Research Reactor Facility when final decommissioning began. 4.1 Buildings / Systems 4.1.1 Building 100 The inside of Building 100 was still divided into four elevations. The basement contained a 6-foot diameter experimental gamma ray facility that extended an additional 16 feet below the - foundation. The demineralizers and heat exchanger were in place. The basement also housed 16 vertical storage tubes, an electrical and mechanical equipment room, the building sump and floor drain system. The operating deck consisted of a high bay area and an experimental area equipped with neutron beam tubes. The first platform, located on the east side of the building, housed 6 neutron beam tubes. The second platform, located directly above the first platform, consisted of the reactor control room, a supply room, and an area for reactor servicing, loading and unloading. See Figure 4-1 for a cross section view of Building 100. Reactor system and service lines (electrical, water, air, steam and O- condensate) entered the facility from Building 97 through steel pipe and conduit that was sealed and welded to the containment building steel shell. The air intake and exiest ducts equipped with automatic closing dampers were intact. The perimeter o' '
. ',g 100 consisted of ordinary concrete 44-feet high and 24-inches . .k.1. > reactor vessel and liner were surrounded by a shield wall const. v +M 4 ' 30 feet of 16-inch thick ordinary concrete and 15 feet of 48-inch thick . h-density concrete. .
4.1.2 Building 97 Building 97 was connected to the west side of Building 100 through Airlock #1. Service line penetrations (electricity, air, water, steam and condensate) connected the two buildings. All that remained of the radioactive waste processing system was the reactor coolant transfer line, the sump pump drain line, the demineralized water line and a test collection line. These lines were closed and capped where they entered Building 97. O onsrunarrumawnuo ao 4-1 REVISION 0
SITE DESCRIITION AS OF JUNE 1992 l l l I l
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SITE DESCRIPTION AS OF JUNE 1992 1 4.1.3 Cistera 242 Cistern 242 was located approximately 25 feet southwest of Building 100. l The tank was 23.5-feet square,15-feet deep and constructed of 1-foot l thick concrete. A manhole on top of Cistern 242 provided access to the interior of the tank. Figure 4-2 provides an isometric view of the cistern. 4.1.4 Secondary Cooling System The secondary cmling sys em had been located southwest of Building 100. The coolant tower was disposed of prior to decommissioning operations. The secondary coolant sump concrete pad, three pumps, a secondary coolant sump beneath the pad, and the underground secondary coolant piping and conduit between the sump area and the reactor building remained. 4.1.5 Exhaust Stack Foundation ; The Building 100 exhaust stack was removed prior to decommissioning operations leaving only the exhaust stack concrete foundation. 4.2 Reactor Yard O The yard surrounding Building 100 encompassed an area of approximately 180 x 320 feet. Five Austrian pine trees were located in the reactor yard. Protective measures (e.g., pre-construction training, marking, fencing) were taken during work activities to prevent any damage to these trees. The remaining grounds have little vegetation and consist primarily of rocky soil. I r O ' onmwau,rrwunawanos no 4-3 REVISION 0
SITE DESCRIITION AS OF JUNE 1992 e
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l O 5.0 DECOMMISSIONING ACTIVITIES Results of Previous Surveys Decontamination Approach and Procedures Summary of Decontamination Activities Occupational Exposures Waste Disposal O
DECOMMISSIONING ACTIVITIES 5.0 DECOMMISSIONING ACTIVITIES The decommissioning of the AMTL Research Reactor Facility focused on Building 100, Cistern 242, the secondary cooling system and associated Building 97 piping. An EG&G report entitled Characterization Report for U.S. Army Afaterials Technology Laboratory Rcsearch Reactor, June 1990, provided an initial characterization of the radiological conditions of these buildings and systems. 5.1 Results of Previous Surveys The initial description of the radiological conditions of Building 100 and its support systems was based on results from surface radiological surveys and analyses for neutron activation products performed by EG&G during 1989 and 1990. Radiation surveys were performed using portable beta-gamma detecting instruments. Smear survey analyses were performed at the Idaho National Engineering Laboratory. Scientific Ecology Group, Inc., performed additional surveys in 1992 during the decommissioning activities. The results of these surveys were used as additional characterization data. Radiation surveys were performed using portable ionization chambers (Eberline Model RO-2). Surveys for fixed contamination were performed using portable friskers (Ludlum Model 177 with a Model 44-9 unshielded GM detector). Removable contamination surveys were performed and analyzed using a portable beta counter (Eberline Model BC-4), an alpha counter (Eberline Model O S AC-4), or a low background gas-flow proportional alpha-beta detection system (Tennelec Model LB-5100/W). Table 5-1 provides a summary of results from the radiological characterization performed by EG&G and SEG. O
""'3'P"'nstraurtwin xxwis.no 5-1 REVISION 0
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1 DECOMMISSIONING ACTIVITIES O Table 5-1 Summary of Radiation and Removable Contamination Survey Results Contact Radiation Beta-Gamma Alpha l Location (mR/hr) (dpm/100 cm 2) (dpm/100 cm 2) Basement .05-6.0 < 200-293 < 20 Demineralizer 2.0-6.0 Heat exchangers 0.3 Fission Product Monitor 0.05 Operatine Deck'* < 0.2- 16 < 200 < 20 Californium 252 Source 16 Mobile N-Ray 0.2 First Platform < 0.2-0.2 < 200 < 20 Reactor Keeper Slide 0.2 Second P1atform < 0.2-0.7 < 200 < 20 Reactor Top 0.7 Magnets in Cabinet 0.4 Reactor Vessel Intervals 8.0-550 < 200-2800 < 20 l Blind Flanges 15-550 l Slant Tubes-in place 8.0-550 1 Valves 10-60 i Pedestal 15-550 Reactor Annulus < 200-5700 < 20 : 1 Stainless Steel Racks 55 Below Reactor Gate 1300 l (relocated slant tube) ! Cistern 242* < 0.2 < 200 < 20 Building 97 Pipe Allev* < 0.2 < 200 < 20 ) l
- Denotes results determined by SEG during decommissiomng
**The Californium 252 source and Mobile N-Ray were removed prior to final decommissioning l O .
meerun.strw.rrwwsxm an 5-2 REVISION 0
DECOMMISSIONING ACTIVITIES 5.1.1 Site Characterization Building 100 EG&G characterization surveys performed inside Building 100 included the basement, operating deck, first and second platforms, reactor control room (focated on the second platform), top of the reactor, reactor vessel, reactor pedestal, and reactor annulus. Smears collected for Building 100 characterization and analyzed for alpha contamination were all less than the most restrictive guideline value of NRC Regulatory Guide 1.86. Smears collected from the operating deck - and the first and second platforms ' were analyzed for beta-gamma contamination and found to be less than the most restrictive guideline value of Regulatory Guide 1.86. Smears collected from the reactor basement, vessel and annulus areas were analyzed for beta-gamma contamination and found to have values ranging from less than 200 to 5,700 dpm/100 cm2 . Transuranic isotopes were not detected on any of the smears. Results of a radionuclide analysis performed on one of the more contaminated smears is provided in Table 5-2. The highest radiation readings were measured on components contained O within the reactor vessel and annulus. These values ranged from 8 to 550 mR/hr and 18 to 1,300 mR/hr, respectively. SEG surveys provided results similar to those observed during the EG&G characterization. The highest contact radiation level observed by SEG was 1,300 mR/hr. This reading was observed on a slant tube that had been previously removed from the vessel and relocated to the inside of the reactor annulus near the reactor gate. It was concluded that this reading was on the same component identified as 1,300 mR/hr during the EG&G characterization survey. An SEG water sample collected from the inside of a neutron beam tube showed no indication of radionuclides greater than the MPC values in 10 CFR 20, Appendix B, Table 2, Column 1. The californium-252 source and the Mobile N-Ray unit surveyed by EG&G in 1990 had been removed from the operating deck prior to final decommissioning. O ownrumstrwmuunmo" 5-3 REVISION 0
DECOMMISSIONING ACTIVITIES Ilyilding 97 At the time of the EG&G characterization rurvey, smears taken from piping inside Building 97 indicated radioactivity levels less than 200 dpm/100 cm2beta-gamma and less than 20 dpm/100 cm2 alpha. Since the piping connecting Building 97 and Cistern 242 was underground, it was not surveyed during this characterization. SEG surveys performed inside the pipe alley between Building 97 and Building 100 provided results similar to those obtained during the EG&G characterization. The reactor sump piping, running underground between Building 100 and Building 97, was found to have low levels of fixed contamination ranging from 5,000 to 10,000 dpm/100 cm2 beta. Removable contamination levels were less than 200 dpm/100 cm2 beta and less than 20 dpm/100 cm2 alpha. Contact radiation levels were less than 0.2 mR/hr. Cistern 242 The water in Cistern 242 was sampled and analyzed by EG&G during February 1990, and radioactivity levels from these samples were below the Environmental Protection Agency (EPA) drinking-water standards. O Other than natural potassium-40 and radon / thoron daughters from the natural uranium and thorium decay chains, there was no measurable gamma activity detected. The gross alpha and beta activity levels for the sample were 2 x 10" and I x 10" pCi/ml, respectively. Based on these results and on the low levels of contamination found in the reactor vessel, it was assumed for the purposes of decommissioning planning that Cistern 242 did not contain a substantial amount of radioactively contaminated sediment or sludge. In 1992, the accumulated water in Cistern 242 was sampled and analyzed for radioactivity with the result that no detectable activity was observed. The water was then processed through a treatment skid operated by MK, as required by the EPA, before the water was discharged to the storm drain. Subsequent SEG surveys indicated that the sludge and sediment inside Cistern 242 contained low levels of Co-60, Eu-152 and Eu-154. In addition, low levels of fixed contamination, ranging from 5,000 to 10,000 dpm/100 cm2 beta, were detected on the inside of Cistern 242. Removable contamination levels were less than 200 dpm/100 cm2 beta and less than 20 dpm/100 cm2 alpha. Contact gamma radiation levels inside the cistern were less than 0.2 mR/hr. O omrunrrwerwwu*" 5-4 REVISION 0
DECOMMISSIONING ACTIVITIES 5.1.2 Summary of Hazardous Materials In March of 1990, EG&G collected surface soil samples from locations around Building 100 and Cistern 242 and soil samples from below the surface at depths ranging from 2 to 17 feet. These samples were analyzed for metals, lead and mercury in accordance with EPA methods as specined in the Sampling and Analysis Planfor the MTL Cistern and Reactor Area of reference 9.3.3. , Analysis for a broad range of organic compounds was performed using EPA methods. There were no volatile organic compounds, semi-volatiles, PCBs, organochlorine pesticides, organophosphorus pesticides, chlorinated herbicides, lead, or mercury detected at levels above EPA regulatory limits. Although metals were detected at concentrations greater than the upper tolerance limits with 95 % conndence, concentrations were less than EPA limits for hazardous wastes. During decommissioning, lead and asbestos were the only hazardous materials identified that had any significant impact on decommissioning activities. Approximately 18 cubic feet of asbestos was removed from Building 100 and disposed as non-compactible low-level radioactive waste. Approximately 20,000 pounds oflead bricks used as shielding at Q L/ the experiment tubes was removed, surveyed, and unconditionally released to the Army. Radioactively contaminated lead-lined beam tube parts were removed from the Research Reactor Facility site and transferred to the AMTL Facilities license to await shipment for disposal. 5.1.3 Summary of Radionuclides A radionuclide analysis was performed on one of the more contaminated smears collected by EG&G from the reactor annulus area. The results of the radionuclide analysis identified Co-60, Eu-152 and Eu-154 with activities of 2,200,1,100 and 200 dpm/100 cm 2, respectively. Soil samples collected by EG&G during the characterization were also analyzed by gamma spectroscopy. The results are summarized in Table 5-2. I O om eumsnw trunnx" " 5-5 REVISION 0
DECOMMISSIONING ACTIVITIES
^ Two of the 6hir66fsrizalidh soil samples from the area betwee. Building 97 and Cistern 242 contained positive indication of Co-60. This area also showed elevated radiation readings during the EfjaiisltsiizatI6s surveys performed in September 1989. The maximum observed Co-60 value was 0.6 pCi/g. Cesium-137 was detected in 27 of the samples with a maximum concentration of 0.5 pCi/g.
SEG;&lldEled isferafsoifsidiblesniiiilnsfes SEtWsEii)6ildhijp7lE5il Cistern 242d The locatioris of;ths two EG&G soilTsampks%itbyositivs
~
in'dicati~o ns of'Cs60!could hbt"beTf6 sad /noGobldithMindiaation's"bs reprddhesd[ jElevAtedyaldistibnjesdingslappear@tdMdbijdijd , prdximity,of; severaljtfuctural ; walls; The values contained in Table 5-2 were reported after subtracting background. Table 5-2 Sununary of EG&G Radionuclide Results Sample Radio- Activity Uncertainty Average Uncertainty Maximum Type nuclide dpm/100 cm 2 (95% CL) Activity (95% CL) Activity dpm/100 cm 3 pCilg pCilg pCi/g Smear Co-60 2200 44 - - - Smear Eu-152 1100 67 - --- - Smear Eu-154 200 44 --- --- - i Soil Co-60 --- 0.4 0.5 0.6 Soil Cs-137 - 0.3 0.2 0.5 i i SEG collected and analyzed various samples by gamma spectroscopy. The analysis of smears collected from the fuel rack inside the gamma well identified the presence of Co-60. Concrete core samples were collected from the reactor cavity. The analysis of these samples indicated the presence of Co-60 and Eu-152 with activities of 50 and 71 pCi/ gram, respectively. Demineralizer resin was sampled and analyzed. Radionuclides identified were Co-60, Cs-137 and Eu-152 with activities of 720,12 and 213 pCi/ gram, respectively. The values given in Table 5-3 were reported after subtracting background. 1 O l 5-6 REVISION 1 ! mmrumsnuwrurmxmusmms ! l l
. = . _ -. . - . - -
l DECOMMISSIONING ACTIVITIES 1 Table 5-3 Summary of SEG Radionuclide Results Sample Type Radionuclide Activity Uncertainty pCi/g (95% CL) pCi/g l Smear Co-60 --- --- Concrete Co-60 50 2 Eu-152 71 2 Demineralizer Co-60 720 30 Resin Cs-137 12 2 Eu-152 213 6 5.1.4 10 CFR Part 61 Characterization Samples were collected to characterize waste for disposal. Six samples were collected from various materials representative of the waste stream. ' The samples collected are listed below:
- Carbon steel filings
- Resin from the demineralizer O.
- Aluminum filings Stainless steel filings 7
- Crud from Cistern 242
- Concrete These samples were packaged and sent to an independent laboratory, Controls for Environmental Pollution, Inc. (CEP), for analysis of the nuclides specified in 10 CFR 61. The results were then used as a baseline for characterization of the waste. The values given in Table 5-4 .
were provided by CEP and were reported after subtracting background. Note that the values for the sample of aluminum filings were comparatively high, although the relative ratios were found to be acceptable. hiiilfsiff6rT6bEsaisins ssidinjinddlidisindiddtsd thbyresenbibf Ci14 und?ID3:linithe?resiniendDaluminum;filinss? /EreView;6fLthetwasts khipmstiassocia'ted with ths reacts d6comrnissioni6g revealedthat more than 90%of the waste generat'edyds cbmprised.of D.A.Wiand concrete; Ths scaling factors forf-14 and Hi31for these two. waste' streams relative to lC&60Were less thsnt0'.005MTheLfactTthat'C214!an'd ~103%s only idsntified"in thbse i vo'is0 lated whiteltreams justifies the cohclusion that ti! ereli.s nkiilipsetnsinpyicriteris!or;gnideline vslues) ~ ' ~ ' ' ' ' " O 5-7 REVISION 1 NMW.1 PUD $n'AMTDFIVRTAMFNDiO36
DECOMMISSIONING ACTIVITIES Table 5-4 Table of Nuclides from 10 CFR Part 61 Characterization Sample
Description:
Carbon Steel Filings I Radionuclide Activity Uncertainty MDA pCi/g (95% CL) pCi/g pC1/g H-3 52 0:5
- 01~5 C.14 R0:5
- 0:5 Co-60 1000 2 0.02 Ni;59 20.5 ~*
0.'5
~
Ni-63 '21.0
- 1.0 Sr (89 +90) 2 1 0.5 20~'5
- 0:5 Nii-94 .
Tc-99 10 5 3d 1.0
- l '.'0 12129 Cf;137 %0.7
- 0.7 U-234 6 0.7 0.5 O u.235 U-238 W o.5 5
1 0.5 0.5 Pu;239 2005
- 0.05 Pu-241 W 0.05
- 0.05
'Aris-241 2 0.05
- 0:1 Chii242 % 0.1
- 0.1 Gross Alpha 20 4
- Gross Beta 115 4
- Values not provided by CEP.
O 5-8 REVISION 1 I N7992-PUtrStr\AMTL'JW.RX'.011
DECOMMISSIONING ACTIVITIES O Table 5-4 (continued) Table of Nuclides from 10 CFR Part 61 Characterization Sample
Description:
Demineralizer Resin Radionuclide Activity Uncedainty MDA pCi/g (95% CL) pCi/g pCilg H-3 2600 110 0.5 , C-14 2700 350 Co-60 660 4 0.02 Ni-59 fR0.5 0:1 Ni 63 2 l~.0 .* 1:0 Sr (89+90) 3 0.3 0.5 -
- 0.5 Nti-94 T<0.5 Tc-99 84 7 I-129 R 0.1
- 1.0 Cs-137 11 1 0.01 ,
U-234 5 0.5 0.5 O U-235 2 0.5
- O'.'5 U-238 5 0.9 0.5 Pu-239 0.6 0.2 0.05
~
Pu-241 2 0.05
- 0.05 Xhi;241 ~<0.1
- 0;1 Cm-242 0.2 0.1 0.1 Gross Alpha 18 1 Gross Beta 621 7 Eu-152 200 7 Eu-154 39 3 Eu-155 6 2
- Values not provided by CEP.
O 5-9 REVISION 1 4 042492 Ptni.SITMMT1?JERXi0tt i
DECOh1MISSIONING ACTIVITIES , O Table 5-4 (continued) Table of Nuclides from 10 CFR Part 61 Characterization Sample
Description:
Aluminum Filings Radionuclide Activity Uncertainty MDA pCi/g (95% CL) pCi/g pC1/g H-3 900,000 20,000 0.5 C-14 103,000 900 0.5 Co-60 1,700,000 1000 0.02 ; Ni;59 2 015
- 0:5 Ni-63 2 1.0 1.0 Sr (89+90) 3500 300 0.5 k 0.5
- 0:5 Nbi94 Tc-99 3000 70 l-129 40,000 2000 1 Cs-137 4800 300 0.01 .
U-234 T<0.5
- 0;5
- 0.5 U-235 W O.5
- 0.5 U-238 % 0:5
' u-239 P
~
'< 0.05
- 0.05
% 0.05
- 0'.05 Pu~- 241 ,
i<0:1
- 0.1 Am-241 .
- 0:1 Cni-242 k O'.1 Gross Alpha <1
- 1.0 Gross Beta 285,000 2000
- 32,000
- Eu-152 2000 Eu-15 4 11,000 1000 Eu-155 1700 300 l Np-237 3000 500
- Values not provided by CEP.
9 i O 5-10 REVISION I f
..en +7 '
- , s , ,--7---- -
s -"-
DECOMMISSIONING ACTIVITIES O Table 5-4 (continued) Table of Nuclides from 10 CIM Part 61 Characterization Sample
Description:
Stainless Steel Filings Radionuclide Activity Uncertainty MDA pCi/g (95% CL) pCi/g pCi/g H3 WO:5 *: 0:5 C 14 < 0.5 T^ # 0:5 Co-60 450 13 0.02 Ni;59 70.05 * . 0.5 Ni!63 W1:0 *: 0.5 Sr (89+90) 12 4 0.5 Nti94 RO:'S & 0:5
~
Tc-99 k1TO
- 1.0 1129 t~1:0
- 1:0 Cs-137 W O.5 0.~ 5 U-234 R 0.'5
- 0.5 U;235 W 0.5
- 0.5
% 0:5
- 0:5 U-238
~
70.5
~
Pti:239
- 0.05
~
Pd-241 M O.05 0'.05 Wns-241 '<0.1
- 0:1 Cin 242 V0:1
- 0:1 Gross Alpha < 0.5
- 0.5 ,
Gross Beta 100 11
- Values not provided by CEP.
O 5-10a REVISION 1 N2992 l'Ulr5!TMMTUJIN'RX\0M
DECOMMISSIONING ACTIVITIES Table 5-4 (continued) O Table of Nuclides from 10 CFR Part 61 Characterization Sarnple
Description:
Cistern 242 Crud Radionuclide Activity Uncertainty MDA pCi/g (95% CL) pCi/g pCi/g 163 M O.5
- 0;5
~
C-14 <0:5 .* 0:5 Co-60 160 6 0.02 Ni-59 '40.5 '* 0.5 Nii63 % LO 8 1.'O Sr (89+90) 0.8 0.5 0.5
- 0.5 Nbi94 R O'.5 Tc-99 "41:0
- l';0
- 1:0 1-129 R 1.'O Cs-137 12 3 0.01 U-234 2 0.5 .* 0.5 U2235 '20.5
- 0.5
- 0.5 U-238 % 0.5 R0:05
- Pu-239 0:05 Pu-241 20.05
- 0.05 Arn-241' W O.1
- O'.1 l Cm-242 0.2 0.1 0.1 Gross Alpha 4 "
15 Gross Beta 110 7 j
- Values not provided by CEP. ,
l l l O 5-11 REVISION 1 (H1%'2-PUinSTITA MTI).FLV.R XWM 1
= .- - -. - - - . . . . . --
DECOMMISSIONING ACTIVITIES O Table 5-4 (continued) Table of Nuclides from 10 CFR Part 61 Characterization Sample
Description:
Concrete Radionuclide Activity Uncertainty MDA pCl/g (95% CL) pCi/g pCl/g H-3 '<0.5 * . 0:5 C214 % 0.5
- 0:5 Co-60 115 1 0.02 Ni-59 205 0.5 nim 3 W1.0 1.'O Sr (89+90) 1.1 0.3 0.5 Nb"-94 20'.5 0:5 Tc-99 19 5 12129 '<1:0
- 1.0
- 0.7 Cs-137 W O.7
'* 0.5 U1234 R 0.5 U-235 R0:5 0."5 U-238 2 0.5 0.5 lin'-239 W 0.5 D:05
- 0.05 Pti-241 % 0'.05 -
Ani-241 % 0.1 .* 0.1 l
- 0:1 Cni-242 % 0.1 .
Gross Alpha < 0.8 0.8 ; Gross Beta 13 2 Eu-152 200 5 Eu-154 105 2 Sif-~122 43 18
- Values not provided by CEP, O REVISION 1 5-1la N2992-ftTIr.SmAMTLU1N'.RX\0M
DECOMMISSIONING ACTIVITIES ( 5.2 Decontamination Approach and Procedures 5.2.1 Decontamination Procedures MK prepared work packages in accordance with the Decommissioning Plan. These packages were used to track demolition, decontamination, excavation and final survey activities. During preparation of the work packages, safety, quality, and. environmental programs, as well as regulatory considerations and requirements were addressed. SEG prepared procedures to provide radiological support for the decommissioning. Preparation was in accordance with the Radiation Protection Program described in Section 5.2.2. Technical basis documents were developed to support survey techniques and to interpret ; survey results. Organizations involved in the selection of decommissioning methods included: The Department of the Army, Headquarters, U.S. Army Material Command; The U.S. Army Corps of Engineers, New England Division; The AMTL Commander; Stone and Webster Engineering Corporation; EG&G Idaho; Roy F. Weston, Inc.; and Scientific Ecology Group, Inc. O %/ 5.2.2 Radiation Protection Personnel Protection Through administrative controls and procedures, every reasonable effort was made to reduce individual and collective radiation exposure during ; the reactor decommissioning. Preliminary planning and scheduling coupled with the use of proven and innovative engineering techniques enabled the ALARA program at AMTL to maintain the total accumulated ) exposure to less than thirteen percent of the original exposure estimate for the Building 100 decommissioning. Engineering controls were used to reduce the intake of radioactive materials prior to the use of respiratory protection. The work place, workers' respiratory protection and the effectiveness of protective equipment were assessed by means of air sampling and bioassay. Bioassay was performed on all decommissioning personnel prior to start of work and again upon termination. This included whole body counting for detection of radiation being emitted from radionuclides in the body. O werw.snwrurwxuxe" 5-12 REVISION 0 I
. . i
Ja + DECOMMISSIONING ACTIVITIES
\ Personnel exposure was controlled and monitored using routine s surveillance, engineering controls and personnel dosimetry. Dosimetry included the issue of two thermoluminescent dosimeters (TLD) and one self-reading dosimeter (SRD) for each individual performing decommissioning work. One TLD was issued and monitored by the Army. The second TLD and the SRD were issued and p,0 cessed by MK/SEG. TLDs were changed and read on a monthly basis.
Personnel contamination was controlled using engineering controls, area decontamination, RHWPs and protective clothing. An Eberline model PCM 1B was used to monitor personnel for radioactive materials when exiting from the Building 100 access control point. In addition, several portable friskers (the Ludlum Model 177 with thin-window GM detector) were also available for personnel monitoring. Radioactive Material Controls Radioactive material controls were used during the decommissioning to provide positive control of radioactive material and to prevent accidental release of radioactive material to uncontrolled areas. These controls also ensured that accidental personnel exposure to radiation from misplaced radioactive material did not occur and reduced to a minimum the radioactive waste material generated during the decommissioning. Radioactive Material Areas were established as controlled areas for holding radioactive materials. These areas were barricaded, posted and monitored. Radioactive material placed into or removed from these areas was surveyed by Radiation Protection personnel. An Eberline TCM-2 tool contamination monitor was used for monitoring hand tools, personal effects and small equipment for free release. Portable friskers (a Ludlum Model 177 with a thin window GM detector and a Nuclear Enterprises Model CM7A with a 100 cm 2gas-flow proportional detector) were used to verify that free release guideline values were not exceeded. Instrumentation was used and techniques implemented to ensure that free-released materials, equipment, etc., were free of licensed material in , accordance with guidelines specified in NRC IE Circular 81-07 Control of Radio Actively Contaminated Material and IE Information Notice No. 85-92 Surveys of Wastes Before Disposal from Nuclear Reactor Facilities. O aerumstrurrumw.u" 5-13 REVISION 0
DECOMMISSIONING ACTIVITIES Security Precautions During the Building 100 decontamination phase, personnel access to Building 100 was controlled through Airlock #1 from Building 97. A ; security guard was posted at this airlock to monitor all personnel entering and exiting. Equipment and materials were moved in and out cf Building 100 through the equipment hatch, where access was controlled by Radiation Protection personnel. During decommissioning activities, access to the reactor facilities and , yard was controlled through the use of warning signs, fencing, physical i barricades around excavations, and other standard construction practices. Personnel access to Radiation Areas, High Radiation Areas, and areas containing radioactive material was limited as required by NRC in 10 CFR 20 and was administratively controlled by the use of RInVPs. Environmental Monitoring i Air exhaust from Building 100 was monitored by a continuous air monitor : (CAM). The CAM was connected to the Building 100 exhaust damper valve and automatically shut the damper if a CAM alarm occurred. A O sample tube was installed inside the exhaust vent housing downstream of the HEPA ventilation unit. The sample tube was connected to the CAM, and the sample flowrate matched the velocity _ of the exhaust. Low l volume air samplers were located inside weather proof housings along the ! site perimeter. Both the CAM and the low volume air sampler filters l were changed weekly. The CAM filters were counted twenty-four hours after collection to allow radon daughter products to decay. No airborne radioactivity concentrations above the limits set forth in 10 CFR 20, Appendix B, Table 2, Column 2, were observed for these samples. 5.3 Summary of Decontnmination Activities j 1 Final decommissioning of the AMTL Research Reactor Facility began in June of 1992. Initial activities included the setup of management, industrial health and ! l safety, administrative support, labor support and health physics facilities. The major decommissioning tasks of decontamination and dismantling Building 100 and auxiliary support systems began in July. Appendix E contains a photographic essay illustrating 1 some of the decommissioning activities. O umanr.smantuwm"*
- 5-14 REVISION 0
DECOMA11SSIONING ACTIVITIES Several difficulties were encountered during the Building 100 decommissioning: the relatively small equipment hatch impeded the ability to remove dismantled equipment and components; the ten-ton capacity limit of the polar crane restricted the cut size and weight of concrete blocks; and the types of materials forming portions of the bioshield required alternative methods of removal. Upon the conclusion of decontamination activities, Radiation Protection Personnel performed release surveys preliminary to the final status survey. Subsequently, radiological postings were removed and RHWPs terminated. 5.3.1 Building 100 Control Room The reactor control room instrumentation and control panels were dismantled, surveyed and found to be free of radioactive material. This equipment was turned over to the Army to be packed and stored as an artifact. Cavity Liner O A water washdown of the cavity and annulus was performed prior to the beginning of work activities to remove loose asbestos. This water was subsequently processed through a demineralizer system, sampled, . analyzed, and released to the storm drains. Fuel handling tools, equipment and components were removed, and items identified with radiation levels in excess of 20 mR/hr (i.e., beam tube, fuel rack) were placed in the gamma well for temporary storage. This minimized radiation exposure to personnel dismantling the stainless steel :' lining. Remaining items were placed into low-level radioactive waste shipping boxes and removed from the building. Liner removal began with the use of grinding tools, but this method proved to be slow and ineffective. A plasma torch was then used with satisfactory results. Smoke and fumes generated were removed using two 2,000 cfm HEPA ventilation units, each having two 8-inch trunks. The l I intake trunks were placed near the bottom of the cavity to draw the smoke and fumes down and away from the work area. The trunks exhausted i through the building external exhaust. The top of the cavity was sealed , except for an access hole down into the cavity. Personnel working in the l cavity were required to wear supplied air respirators. Breathmg air was , l O 1 mnruitwavirrIN'.Rxco n' 5-15 REVISION 0
3 DECOMMISSIONING ACTIVITIES j 4 supplied by a cascade air system, established near the access point and monitored by safety personnel. Continuous low volume air samplers were operated inside and outside the cavity during work activities. The air samples were collected in a timely manner and analyzed. All airborne radioactive concentrations during these operations were below the limits set forth in 10 CFR 20, Appendix B, Table 2, Column 2. Gyity/ Annulus Dismantling operations began with the upper portions of the cavity and annulus and moved downward to the bottom of the annulus. Concrete was cut and removed using a diamond wire saw. As work progressed, the concrete surrounding the reactor from the bottom of the annulus downward to the operating deck was identified as magnetite and steelshot-
-impregnated high-density concrete. As this type of concrete could not be efficiently cut with the diamond wire saw, jackhammers were used for the removal of this material. The concrete debris from jackhammering was considered contaminated or potentially contaminated and was placed directly into low-level radioactive waste shipping boxes. Dismantling operations using a diamond wire saw were resumed for the remainder of O the concrete (i.e., below the operations deck and downward). Samples of the cooling water were collected during the concrete cutting operations and analyzed to assess the possibility of tritium leaching. There was no indication of tritium leaching.
The concrete was cut into blocks weighing up to 24,000 pounds. These blocks were removed from Building 100, wrapped in herculite and stored in the reactor yard awaiting scabbling. These blocks were then placed inside an enclosure where all exposed surfaces were scabbled, removing approximately 0.3 cm of concrete. The concrete blocks were categorized as category one, two, or three , concrete. Category one and two concrete is concrete which has been in contact with the primary coolant and/or potentially exposed to neutron fluxes. The free release of category one and two concrete was complicated by the need to verify the absence of absorbed fission or activation products. A technical basis document, ADM-D-203, Deviation ofSurface Contamination Limitfor the Free Release ofReactor Building Concrete, was written to delineate the protocols for free release of ; concrete. pd 010491PUlnSTMhfrD1WJtN* 5-16 REVISION 0
DECOMMISSIONING ACTIVITIES
/^ Briefly, category one and two concrete was assumed to be free of
( absorbed contamination if:
- The concrete is determined to be free of surface contamination.
- No fission and/or activation products are identified during the gamma spectral analysis of residue, collected uniformly from the i exposed surfaces of the concrete.
- No elevated readings are detected during a R survey of the concrete.
)
The technical basis actually allowed concrete to be assumed to be free of l absorbed contamination if the gamma spectral analysis did not quantify l Co-60 activity in excess of 2.6 x 103 pCi/g. It was originally thought ! that this level of Co-60 could be attributed to normal sources and/or environmental levels. Actually, analysis of the concrete demonstrated this , not to be the case, as there was not measurable Co--60 associated with the i free release of any category one or two concrete. The dust generated from jackhammering and scabbling activities was controlled using herculite enclosures and HEPA ventilation systems. Negative pressure fullface respiratory protection was used for activities O performed inside thejackhammering tent. Dust generated from scabbling activities was further controlled using a vacuum shrouded scabbling l system. Personnel performing scabbling activities wore dust masks on a voluntary basis. Basement Above ground system components and piping were removed using grinders, reciprocating saws and oxy-acetylene torches. The reactor sump j and gamma well liners were removed using a plasma torch. The cylindrical concrete storage racks embedded in the floor were removed by core boring and were extracted as individual units. The building floor drain system was excavated. i The demineralizers and heat exchanger were flanged-off and prepared for I shipment as strong-tight containers. These systems were disposed as radioactive waste. The reactor sump contained sludge and sediment which were removed and disposed as radioactive waste. Resins in the deminemlizers were removed using a barrel vacuum system and then disposed as radioactive waste. O omm ewstrurunnuo**
- 5-17 REVISION 0 ;
DECOMMISSIONING ACTIVITIES t Operating Deck. First and Second Platforms The concrete of the operating deck and the first and second platforms had not been in contact with primary coolant. This concrete was surveyed and unconditionally released. The concrete was cut into blocks of manageable size using a concrete saw and removed from the building. Post Decontamination Building Surface Conditions Remaining concrete surfaces were porous and mostly unpainted. The basement floor contained several trenches from excavation activities. The equipment hatch, personnel airlocks and the polar crane remained intact and operational. 5.3.2 Building 97 Only one component associated with Building 97 was excavated and removed during the decommissioning: the reactor sump piping running l 1 underground between Buildings 100 and 97. The piping was sun' eyed I and disposed as radioactive waste. As a part of the decommissioning work, soil samples were collected and analyzed by gamma spectroscopy j to verify that the soil decontamination work was completed. 5.3.3 Cistern 242 and Piping The water contained in Cistern 242 was pumped out and processed l through a demineralizer system. Residual sediment in Cistern 242 was then removed, analyzed and disposed as radioactive waste. The interior i surfaces were scabbled to remove re naining radioactive contamination. 1 The resulting debris was disposed as radioactive waste. Piping from Building 97 to Cistern 242 was excavated, surveyed, removed and I disposed as radioactive waste. l l Cistern 242 was excavated and then dismantled using a concrete saw to l cut it into manageable sections. Surveys of the interior and exterior were performed, allowing Cistern 242 to be free-released. As a part of the decommissioning work, soil samples were taken and analyzed by gamma spectroscopy to verify that the soil decontamination work was completed. l l ommnurrarrenmum 5-18 REVISION 0 1
DECOMMISSIONING ACTIVITIES 5.3.4 Secondary Cooling System The entire secondary coolant sump was excavated and removed as a single concrete unit. The pump motors and coolant sump were smveyed and free-released. The secondary coolant pump and piping were excavated, surveyed and disposed as radioactive waste. As a part of the decommissioning work, soil samples were taken and analyzed by gamma spectroscopy to verify that the soil decontamination work was completed. 5.4 Occupational Exposures Decommissioning personnel were monitored for radiation exposure during the period - from June 1992 to December 1992. Most of the personnel exposure was received . through decontamination activities during the removal of components inside the , reactor vessel and annulus. The highest individual exposure received during this , period was 0.120 rem. The original estimated man-rem for Building 100 ...an actual accumulated exposurefor decommissioning was 10 man- the decominissioning of only 1.29 rem. Th_s i estimated exposure inanvern. was based on estimated task durations, crew sizes and Os radiation fields. Seventy-seven percent of this estimate was calculated using estimated general area radiation fields of 1 to 4 mR/hr for removal of the bioshield and vessel base. Before beginning bioshield and vessel base removal, highly radioactive components'were removed. : Subsequent surveys showed general area radiation fields to be typically less than 0.2 mR/hr. Similar variances in estimated versus actual radiation fields using engineering controls resulted in an actual accumulated exposure for the decommissioning of only 1.29 man-rem. i With the removal of gamma radiation sources in the building and the elimination of radioactive materials areas, dosimetry was no longer required after January 1,1993. Table 5-5 provides a chronological outline of exposure received during decommissioning of the Research Reactor Facility. l l I O 030t93-PUD 6TnAMTIMERXVX A RD 5-19 REVISION 0 l 1
DECOMMISSIONING ACTIVITIES O Table 5-5 Summary of Occupational Exposure Accumulated Period Man-rem Man-rem June 1992 0.000 0.000 July 1992 0.690 0.690 August 1992 0.200 0.890 September 1992 0.280 1.170 October 1992 0.040 1.210 November 1992 0.050 1.260 December 1992 0.030 1.290 A. Waste Disposal Five types of waste were generated as a result of reactor decommissioning at AMTL. These were solid radioactive waste, liquid radioactive waste, mixed waste, releasable effluent and material free oflicensed material. Liquid radioactive waste WEs proEssssdihiond{ anlon3it(d_emirishilipry solidifi6d
~
piioftol disp 6 sal: Pisbeshd 1iijuifwaste was disposed as effluent to the storm drain. Dosefcalculatiord?:11ndichtsd { thit.YK10 h mrenil/yffvt6uldl66[r50Ei(ed Zfroisj subli effluents; A Radioactive Material and Waste Management Plan was developed and implemented to minimize radioactive waste. This program included methods such as work planning, personnel training, material control, volume reduction and decontamination. The most effective method of waste minimization was segregation of radioactive material from non-radioactive mate >ial. Several methods were used to determine if solid waste was radioactive or releasable. Direct measurements were taken on the surface of materials with instrumentation capable of meeting the lower limit of detection (LLD) monitoring requirements. Representative samples were taken from the waste for on-site analysis, and some-samples were sent off-site to Controls for Environmental Pollution, Inc. (CEP), in Santa Fe, New Mexico, for analysis. Large or bulky items from which a representative sample could not be obtained were analyzed using an EG&G portable gamma spectrometry system. O mmwwsmaurerix.nxsruo<nsos2 5-20 REVISION 1
DECOMMISSIONLNG ACTIVITIES Approximately 27,900 cubic feet of solid radioactive waste was generated during the O reactor decommissioning. Procedure AMTL-RW-I-204,10 CFR 61 Characterization and Radioactive Material / Waste Calculation, was used to determine the class (A, B, or C) of the waste. Waste was then packaged in containers appropriate to the waste ' class and stored in the reac:or yard, north of Building 100. Table 5-6 shows the volumes of waste per container and the nuclides present. 1 Radioactive waste was transferred to Chem-Nuclear, Inc., under contract to the U.S. Army Armament, Munitions, and Chemical Command, for shipping and disposal at Barnwell, South Carolina. Compactible items were segregated and sent to the Defense Consolidation Facility. All required shipping documenU; were prepared and I turned over to the U.S. Army Armament, Munitions, and Chemical Command as well. Shipments were made as Low Specific Activity or Type A, in exclusive use vehicles. Eleven Foxes of contaminated lead were removed from the reactor yard and transferred to the AMTL Facility license. A Mixed Waste Plan is being developed to address the disposition of mixed waste generated from the reactor decommissioning. Materials that were found through characterization to be free of licensed material were free-released to local landfills. Over 100 blocks (approximately 1200 tons) of category one and two (contact with primary coolant and/or potentially exposed to neutron fluxes) concrete associated with the reactor were free-released per the technical basis document, AMTL- ADM-D-203, Derivation of the Surface O Contamination Limit for the Free Release of Reactor Building Concrete. This document established a release guideline which was more restrictive than that specified in the IE Circular 81-07 (due to increased instrumentation sensitivity). Thir value, however, was not so restrictive that natural radioactivity would cause material to be unreleasable. Another technical basis document, AMTL- ADM-D-205, Eramination of Waste Concrete for Absorbed Contamination, was also used to establish that the concrete had not absorbed contamination. Other components of the reactor facility were also unconditionally released. The reactor control room instrumentation and any electrical conduit greater than three inches in diameter that could be satisfactorily surveyed with a portable instrument were unconditionally released. The cistern structure and secondary coolant sump were also found to be releasable. O m mumummmm 5-21 REVISION 0
1 DECOMMISSIONING ACTIVITIES Table 5-6 Radioactive Waste from Reactor Deconunissioning l Container Number of Total Volume Waste Type Containers ~o f Waste (ft') Class Nuclides Present in Waste , i B-25 Box 206 19,776 LSA Co-60 Tc-99 Cs-137 Scaland 6 7680 LSA Also present in very small 55 gal Drum 3 22.5 Type A amounts: H-3,1-129, Demin Units 2 201 LSA Sr-total, Eu-152, Eu-154, Heat Exch 2 206 LSA U-234, U-238, Pu-239 O . 1 O omrun srr utmrma e 5-22 REVISION 0
(~) kJ , O F 6.0 FINAL SURVEY , Introduction Final Survey Guideline Values Surveying Organization Survey Design Minimum Detectable Activ'ty Criteria Instrumentation and Equipment Final Survey Techniques Documenti . ion
~
Quality Assurance / Quality Control Data Reduction and Evaluation Statistical Evaluation J
FINAL SURVEY 6.0 FINAL SURVEY 6.1 Introduction The purpose of the final survey of Building 100 and excavated areas of the Thefinal sun.cy wasperfonned yard was to demonstrate that NRC and in accordance with the Commonwealth of Massachusetts . Decomun.ssioning Plan and criteria for unrestricted use were satisfied. This required the collection SPecifically dercloped AMTL of accurate and reliable data to procedures... determine surface alpha and beta activity levels, direct exposure rates and man-made radionuclide concentrations in soils. The final survey was performed in accordance with the Decommissioning Plan and specifically developed AMTL procedures listed in Table 6-1. The Decommissioning Plan and these procedures identified survey instrumentation requirements, measurement and sample collection, data quality objectives and data reduction and evaluation methods. A summary of the equations used is presented in Appendix D. The final survey was designed and performed such that:
- 100% of Building 100 and excavated areas of the yard were marked in O grids;
- 100% of each Building 100 grid was scanned for beta-gamma contamination to detect hot spots; l
- 100% of Building 100 grids were surveyed by direct measurements for surface alpha and beta activities, removable alpha and beta activities and for exposure rates at 1 meter;
- 50% of the yard soil grids were sampled for laboratory analysis to determine gross alpha, gross beta and gamma radionuclides;
- 100% of the yard soil grids were surveyed for gamma exposure rates at 1 meter and for contact alpha and beta activity;
- Instrumentation was capable of achieving Minimum Detectable Activities (MDA) at approximately 50% of the guideline values at a 95%
confidence level; 1 l O omu nwrrernuwnum" 6-1 REVISION 0 l i l
FINAL SURVEY /
- Other AMTL buildings with no history of radioactive materials b]/ contamination were surveyed for direct alpha and beta and.for gamma exposure rates in pR/hr at I meter to establish background benchmarks for Building 100;
- Off-site soil sampling and analysis for gross alpha, gross beta and gamma radionuclides and surveys for gamma exposure rates in. R/hr at 1 meter were performed to establish background benchmarks for the excavated areas of the reactor yard; and
- Survey data collections, transfers and calculations were conducted using computerized data processing, management, and data reduction capabilities.
The radionuclides identified in the EG&G radiological characterization report for the reactor facilities and yard were Co-60, Cs-137, Eu-152 and Eu-154. During the ' decontamination and dismantling work,10 CFR Part 61 analyses performed to characterize radioactive wastes indicated low levels of other activation and fission products. Instrumentation with appropriate detection capabilities was selected and operated in a manner to achieve the required MDA values. Implementation of the final survey included the following:
- Health Physics supervisory personnel performed a preliminary inspection of each survey area to identify survey requirements, including special survey situations, and to provide specific survey instructions as necessary.
- Survey packages were prepared for each survey area.
- Wall and floor survey areas were gridded to provide a systematic meth >d for the collection of survey data.
- Survey measurements were performed and samples were analyzed using appropriate and calibrated instrumentation. Daily source and background checks were carried out before and after each the day's work to verify that the data quality objectives were met.
- Completed survey packages were reviewed by Health Physics supervisory personnel to ensure that all required surveys were performed and that the packages contained all necessary information.
- Survey results were reviewed to verify that the guideline values were not exceeded. Areas of residual activity were identified, evaluated, decontaminated and re-surveyed, as required.
O 022291 PUB 3!T\AMTLWLv.RXWXT1.l* 6-2 REVISION 0
FINAL SURVEY Table 6-1 O- AMTL Final Survey Procedures AMTL-CHM-I-106 Subsurface Soil Sampling AMTL-CHM-I-107 Surface Soil Sampling AMTL-CHM-1-110 Laboratory Quality Control AMTL-CHR-I-106 Termination Surveys of Site Structures AMTL-CHR-1-107 Termination Survey Data Handling and Analysis AMTL-CHR-I-108 Termination Surveys of the Site Environment AMTL-INST-A-100 Radiation Protection Instrumentation Program AMTL-INST-I-101 Calibration and Test Requirements for Radiation Protection Instrumentation AMTL-INST-I-103 Quality Assurance of Counting Systems and Portable Counters , AMTL-INST-I-201 Operation of Ludlum Model 2350 Data Logger AMTL-INST-I-213 Operation of Reuter-Stokes Pressurized Ion Chamber AMTL-INST-I-405 Operation of Tennelec LB-5100 Alpha / Beta Counter AMTL-INST-I-406 Calibration of Tennelec LB-5100 Alpha / Beta Counter AMTL-INST-I-407 Operation of Genie - PC Gamma Spectroscopy System O- AMTL-INST-I-408 Calibration of Genie - PC Gamma Spectroscopy System AMTL-INST-1-411 Operation of the EG&G Portable Gamma Spectroscopy System AMTL-INST-I-412 Calibration of the EG&G Portable Gamma Spectroscopy System AMTL-OPS-1-103 Sample Chain of Custody AMTL-OPS-I-207 Survey Documentation and Review AMTL-OPS-1-209 Performance of Radiation Surveys AMTL-RAM-I-102 Radioactive Source Inventory, Leak Testing and Disposal l l O unm rw.strutrtsi xx.xxwo7.sw 6-3 REVISION 0
FINAL SURVEY 6.2 Final Survey Guideline Values This section identifies the applicable guideline values. Compliance with these values is presented in Section 7.0, Final Survey Findings, of this report. 6.2.1 Building Surface Contamination Acceptance Criteria The objective of the final survey of Building 100 was to The objective of the final demonstrate that residual fixed sm'cy of Building 100 and removable alpha and beta-gamma contamination was below was to demonstrate that residual fixed and acceptable levels, as specified in Table 1 of Regulatory Guide 1.86, reinorable alpha and beta-Termination of Operating License gamina containination was for Nuclear Reactors. Table 1 of below acceptable levels... this reference is reproduced, in part, as Table 6-2 of this report. Based on the nuclide data from the EG&G Characterization Report (reference 9.6.2), the guidelines for surface contamination levels associated with the uranium decay products, Sr-90 and iodine are not applicable. The alpha and beta-gamma guideline values taken from this Regulatory Guide 1.86 are applicable to the O interior of Building 100 and the Building 100 exhaust stack pad in the yard. The most conservative surface contamination levels for the alpha emitters listed in Regulatory Guide 1.86 were used as the acceptance criteria for those radionuclides. Additionally, the Commonwealth of Massachusetts required that residual radioactive materials at the final reactor site shall not cause exposure in excess of 10 mrem /yr to any individual continually present. The AMTL commitment to this guideline value appears in a letter from AMTL to the NRC, dated March 16,1992, written in response to an NRC Request for Additional Information, , Docket No. 50-47, dated February 5,1992. f 6.2.2 Exposure Rate Acceptance Criteria The exposure rate acceptance criteria for uprestricted use is 5 pR/hr l above background at 1 meter in accordan.e with NRC guidance in Guidance and Discussion ofRequirementsfor an Application to Terminate a Non-Power Reactor Facility Operating License, Rev.1, September 1984. Additionally, exposure rates at the final reactor site are not to i exceed 10 mrem /yr. j om9trunwinrwrtsiwaxvtrm 6-4 REVISION 0 i
FINAL SURVEY 6.2.3 Soil Activity Acceptance Criteria. /~ h C The gross alpha, gross beta and gamma radionuclide concentration guideline values, expressed in pCi/g of soil sample taken from the yard, were established as the mean off-site background value plus 3 standard deviations (Reference 9.4.4), The concentration guideline values apply individually to the gross alpha, gross beta and gamma radionuclide concentrations. Pathway analysis evaluations will be required when soil concentrations exceed background concentrations by three standard deviations to ensure that the 10 mrem /yr criteria of Section 6.2.2 is satisfied. Table 6-2 Acceptable Surface Contamination Levels NUCLIDES
- AVERAGE 6' MAXIMUM hd REMOVABLE 6' Alpha emitters 100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2 Beta-gamma 5,000 dpm /100 cm 2 15,000 dpm /100 cm 2 1,000 dpm /100 cm2 emitters
*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.
"As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
' Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area. the average should be derived for each such object.
*rhe maximum contamination level applies to an area of not more than 100 cm'.
"the amount of removable radioactive material per 100 cm2of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined. the pertinent levels should be reduced proportionally and the entire surface should be wiped.
NOTE: This table is an excerpt from Regulatory Guide 1.86. " Termination of Operating License for Nuclear Reactors." 6.3 Surveying Organization I l SEG provided the radiation protection services and the final survey team under contract to MK. The SEG Project Manager had overall responsibility for the Final. Survey Organization. The Radiological Control and Safety Officer had technical responsibilities for the final survey. The Support Services Manager, the Analytical , Services Coordinator, and the Radiological Engineer / Health Physics Supervisor ' assisted in managing the fm' al surveys. The Support Services Manager was responsible for data collection, data review and data management. The Final Survey
~ 1 l
022mnastnernuwmnarum 6-5 REVISION 0 )
FLNAL SURVEY Coordinator implemented the survey program and directed the activities of survey O personnel. An Operations Foreman supervised survey package preparation, tracked survey progress, and performed initial survey package review. Survey personnel were ANSI 3.1 qualified health physics technicians. A building foreman directed the surveying operations in the field. The Database Manager controlled the compilation and use of the . survey databases. Assigned personnel reviewed instrument Quality Control documentation and final survey packages for completeness and accuracy. These assignments ensured that survey documentation was consistent throughout the data review, compilation and evaluation process. The Analytical Services Coordinator maintained an on-site instrument facility and an on-site radiochemistry laboratory for decommissioning purposes. The instrument facility, staffed by health physics specialists, was responsible for the calibration, maintenmce and control of instrumentation, as well as control of calibration and check source inventory. The radiochemistry laboratory, also staffed by health physics specialists, provided analytical services for samples. The Radiological Engineer / Health Physics Supervisor provided on-site technical support to Snal survey personnel. Off-site technical support also was provided by . Health Physics engineers from the SEG Oak Ridge, Tennessee, office. Final survey technicians were trained in the operation of survey instrumentation, data collection and documentation. In addition, these survey technicians were given on-the-job training. Data entry clerks were given on-the-job training for performing Snal survey data entry. Instrumentation and radiochemistry specialists were given training by their supervisors on the operation, calibration and maintenance of instrumentation and laboratory equipment. 6.4 Survey Design 6.4.1 Survey Areas Building 100 and excavated portions of the yard were subdivided into easily identifiable and manageable survey areas. Smaller, radiologically similar sub-areas (walls, floors, ceilings, etc.), referred to as survey
. units, were also identi6ed. Location codes were assigned to associate the survey units to the original survey area. The areas selected provided the health physics technicians and supervisory personnel with relatively small areas that promoted the manageability of the survey data collection and evaluation process. The area selection criteria included consideration of the radiological consistency of an area so that the grids within a suncy unit would be radiologically similar.
J mmma.rranarmxx"' 6-6 REVISION 0
FINAL SURVEY ) The interior of Building 100 was divided into three elevations: (] V basement, operating deck and dome (Figure 6-1). To simplify data management, the basement was further subdivided into four quadrmts, 1 Survey Areas 1-4 (Figure 6-2). All wall, floor and ceiling surfaces in each quadrant comprised a survey area, and each wall, floor or ceiling in a quadrant was assigned a location code to identify it as a survey unit of the survey area. In addition, three other locations in the basement were designated as survey areas: the trenches in the basement floor (Survey Area 5), the gamma well (Survey Area 6), and both north and south stairwells (Survey Area 7). The operating deck was subdivided into two survey areas: Survey area 1 included all floor and wall surfaces, and Survey Area 2 addressed the two-personnel airlocks and the equipment hatch (Figure 6-3). The dome of the reactor building, including the polar crane, was a single survey area. The reactor yard was divided into three survey areas (see Figure 6-4). Survey Area 0 was the north section of the yard and contained one mound of excavated soil. Survey Area 1 extended south from Survey Area 0 to Building 100 and contained two mounds of excavated soil and the exhaust stack pad. Survey Area 2 extended south from Building 100 to the south O fence of the reactor yard. Survey Area 2 contained two mounds of excavated soil, the pits that once contained Cistern 242, the secondary cooling sump, and the trench between Building 100 and Building 97. 6.4.2 Grid Divisions All internal surfaces of Building 100 were marked into grids. The Decommissioning Plan specified grid sizes of one meter and three meters, but the actual grid sizes were measured using a tape incremented in feet. The grids were identified with chalk and the intersections of the chalk lines were marked with paint. One yard grids were applied to the basement floor and walls and to the operating deck. The walls at the operating deck elevation were marked in one yard grids for the first six feet in height. Above six feet, three-yard grids were applied up to the top of the wall, which supported the polar crane. Three-yard grids were also applied to the basement ceiling. Although three meter grids were prescribed in the Decommissioning Plan for the dome, the welded steel plates of the dome formed a suitable grid pattern and did not exceed the 3 meter grid size. This pattern was used for the dome final surveys. All of the Building 100 grids were included in the final surveys. cm93 ruinsmauri>auxxsoo7 no 6-7 REVISION 0
FINAL SURVEY t L)
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F11E. 9#1J.I i l Figure 6-1 Building 100 Cross-Sectional View (Facing South) 7 t x onm-rumstrurumm:un" 6-8 REVISION 0 1 l
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FINAL SURVEY -
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Prwc reaw Wa'Tf14h A47 m a ex N7===q N Figure 6-4 Reactor Yard O 02229FPUU'.STTiAMTL'JUARXVXT7.2 6-11 REVISION 0
FINAL SURVEY ' All excavations and their associated mounds of soil in the yard were Os marked into 1 yard grids. These areas were the Cistern 242 pit and trench to Building 97, the Secondary Cooling System sump pit, and the trench between Building 100 and Building 97. Tlis'Buildihi 100_~sihiiTM its61@didfstslpadD66h?6(In thdhrd[MijihrKsdhjpjnk;jfaj Tli[jjpsi offmsasuf6{henjshrformsdM6rs dsjfollojiii
- C6ntsst[siphaTahd7 bsbiTi6eas5YsrhentEshaT6iishideI6fTisiHHii exisolsure ratss werejcollected s.tieachj; rid surveyddj ~ ~ '~
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C ?$oll 5 amp [sstwere Tollehted infgrids'of pcipatEd' areas) 6.4.3 Survey Packages A portfolio, referred to as a termination . survey package, was prepared a.for each survey area. Within this package was a Termination Survey Package Worksheet identifying grid size, types of measurements required, : description of the area, any special sample requirements, historical information if available, survey data location code (s), and other O information pertinent to the survey area. Also provided in the package were survey drawings wb'ch included the survey grids. As each package was prepared, it was reviewed by supervisory personnel for both completeness and suitability to achieve the acceptance criteria. Survey packages were referenced during the performance of final surveys. Reports of survey data, smear data and the results of required sample analyses were placed into the packages. When the surveys were completed, the package was reviewed to ensure , that the applicable documentation was in order. Documentation is described in Section C.8. 6.4.4 Background Building 100 Surface Measurements Two types of background measurements in Building 100 were required for the final survey. The background for direct beta measurements was measured at the survey unit with the face of the detector shielded from beta radiation. Background measurements were made before and after each unit was surveyed.: G b osomrw.snwenuwaxautunso40 6-12 REVISION 1
FINAL SURVEY q Similar methods were used for alpha background measurements. For b/ alpha measurements, however, it was essential to store the detector in Building 100 so that the radon daughter products which plated-out on the detector remained in equilibrium with the building's environment and did not change during the course of the day's survey. Buildings 36. 60.111 and 131 Exposure Rate Measurements A determination of the background gamma exposure rates, in R/hr, was required to provide a background gamma exposure rate benchmark. This requirement relates to the exposure rate guideline value of 5 R/hr above background at 1 meter from a surface. The approach taken to establish this benchmark was to use the background survey data collected for the final surveys of the laboratory facilities at AMTL. This data also included evaluations for alpha and beta radiations, however, only the gamma data was referenced. Four AMTL buildings with structural concrete were identified as having no history of storing, handling, processing or machining radioactive materials. These buildings and their uses are as follows:
- Building 36 - Cafeteria, stores
- Building 60 -
Steam plant
- Building 111 -
AMTL Commander's house
- Building 131 -
Administration Background surveys of these buildings were designed to differentiate between various construction materials. Because Building 100 was primarily constructed of concrete, the survey data collected from the , concrete surfaces represent the closest models available for establishing a background gamma exposure rate benchmark for Building 100. The ! measurement protocol for this evaluation paralleled that of the final l surveys; gamma exposure rate measurements in R/hr were made at 1 meter from the surface being evaluated. Surveys from surfaces other than concrete were excluded from this concrete background set. l Off-Site Areas The background for excavated yard areas was determined from off-site radiological background levels to support the evaluation of final survey data collected from the excavated yard areas. The required characterizations included gross alpha, gross beta and gamma nuclide n onm.rumstrerrwmxum" 6-13 REVISION 0
FINAL SURVEY
/' analysis of off-site soil samples Contact measurements for gross alpha and gross beta were required to be collected, although this data was not necessary to demonstrate compliance with the applicable acceptance criteria. Exposure rate measurements in R/hr at 1 meter above the surface were also collected at the same locations as the soil samples.
The off-site locations were determined by drawing 12 radiallines on a map 30 degrees apart, centered at Building 100. Concentric circles with radii of 0.5,1.5 and 3.0 kilometers were then drawn, resulting in 36 off-site locations. The list of these 36 off-site locations and a map showing the locations are provided in Appendix C. 6.5 Minimum Detectable Activity Criteria Minimum Detectable Activity (MDA) ccnsiderations for the final survey were specified in AMTL procedure AMTL-CHR-I-107, Termination Survey Data Handling and Analysis, which established the criterion for acceptable MDAs as values equal to or less than 50% of the applicable guideline values. Minimum Detectable Activity is defined as the smallest amount or concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with a 95% probability, with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The value of the [x MDA for each specific measurement depends upon the type ofinstrument, counting time, geometry, detector efDelency and the background count rate. An average MDA was calculated for each of the following detectors used in conjunction with the Ludlum Model 2350 data logger:
- Ludlum Model 43 100 cm 2gas-flow proportional detector (alpha operating voltage)
- Ludlum Model 43 100 cm 2gas-flow proportional detector (beta operating voltage)
- Ludlum Model 44 15.5 cm2 shielded GM detector If the radiological characteristics of a survey area are uniform, use of an average MDA is appropriate. Because Building 100 concrete surfaces exhibited a high degree of uniformity in the alpha and beta measurements, the average MDAs, based on average background values, were acceptable. The results of these MDA calculations and the values of the parameters used for the calculations are given in Table 6-3.
The equation used to calculate the MDAs for these portable instruments is shown in Equation 6-1. Generally, the MDA values for portable instruments was less than 50% of the applicable guideline value, however, during the survey process, it was noted that the MDA for the direct alpha measurements averaged 58%. It was O onsrumsnwrruruman" 6-14 REVISION 0
FINAL SURVEY /'S hiso noted shif~ih^s*MfWf6E^nisisufi7dshisiisisj'thEludinniM5ddlW4D?afe6ised'56%. It was
~ ~ "
-d. conciucied'ihit increasing ifie count time ^Io isduce theMUEnoni3E%"to'50% was not cost-beneficial. [6-1] 2.69 B, '1 + t ,'
+ 3.28 -
MDA = '" ' A E (100i Where: t3 = Sample counting time R3 = Background count rate ta = Background counting duration E = Effeiency in counts / disintegration A = Detector area in cm2 The average MDA for the removable alpha measurements in Building 100 slightly exceeded the 50% criterion for the 20 dpm a/100 cm2 guideline value. The actual MDA values were slightly higher than the initial estimates made during the survey O design. 'ThiTennelec LB-5100/W was used for smear counting. The count time for alpha smears was 120 seconds. It was concluded that increasing the counting time to reduce the MDA from 60% to 50% was not cost-beneficial. The software provided by the vendor for the Tennelec Model LB-5100/W counting system automatically calculated the MDA for alpha or beta smear analyses. An explanation of the calculation method used by the Tennelec system is given in Appendix D. MDA values for soil analyses were manually calculated. The values of the MDAs for the gross alpha and gross beta on smears and in soil samples are provided in Table 6-3. The software provided by the vendor for the Canberra Genie-PC* gamma spectroscopy system automatically calculated MDAs using the methods developed by Carri' in L.A. Currie, Anal. Chem. 40 (1968) 586. SanipEiyefdic6dhisdJf6rtii niinininin16f"500 Tis 566di9hichTsRTUffidient;ib3foWds MI)ALyddes similarlo
'those"ofstandsdizedlNRCi Technical! Specifications' forJ dffluents.Lf Off-sitsf soil samples howeverfyere counted lfor 5000fseconds to, ensure opti.malpsults{for the background baseli_nei MDAs were calculated for all radionuclides listed in the software library for each sample. The values of the MDAs associated with Co-60, Cs-137, Eu-152 and Eu-154 are provided in Table 6-3.
O matrwsmrmxw.umm1 6-15 REVISION 1
FINAL SURVEV J -P Table 6-3 Final Survey Instnunentation Minimum Detectable Activity Values j l
$ariiple Average BAckgiound ;
instrument Radiation Count Background Count Time Efficiency MDA time (cpm) * (min) (cpm /dpm) (miti) ] 2 Ludlum beta 0105 150 1 0.171 ' 1400 d dpm/100 cm . Model 43-68 Ludlum alpha 1 1.7 10 0.154
- 47 dldpm/100}m2 Model 43-68 Ludlum beta-gamma j17 39 10 0.155
- 2700 8 di sm/10ffffn' l Model 44-40 1 1
Canberra gamma 8.3 footnote b fo6tnote b footnote b Co-60: 0.1 pCi/g
- I Genie
- PC Cs-137: 0.1 pCilg
- Spectroscopy Eu-152: 0.01 pCi/g
- System Eu-154: 0.1 pCi/g
- Tennelec beta-smear 2 2.6 600 0.252 27 dpm/100'hm2
- LB-5100/W Counting alpha-smear 2 0.08 600 0.206 12pni/100 am'
- System
- Background is an average of local backgrounds determined during termination surveys.
1 SMDA and backgrounds calculated by Canberra, Nuclide MDA Report. AMTL-7493/LC #0U2002AE09,3/5/93.
' Efficiency is an average of all efficiencies determined during termination surveys.
dMDAs are calculated using average background and efficiency values.
'The average of MDAs calculated by the Tennelee software during termination surveys.
' Average of samples col!ccted off-site.
' Counting matrix was a 1 liter marine!!i of sand.
l l l mannnustnrrmatxuur_sn' 32 6-16 REVISION I l l l l
FINAL SURVEY 6.6 Instrumentation and Equipment The instruments and equipment for the final survey were selected to meet or exceed the detection requirements specified in the Decommissioning Plan. A list of the instruments selected, the radiations detected and the sources used for source and response checks and calibration are provided in Table 6-4. The MDA capabilities of the instrument, are presented in Table 6.3. 6.6.1 Field Instrumentation The Ludlum Model 2350 data logger and appropriate detectors were used for the surface surveys in Building 100, the exhaust stack pad and the < yard. The data logge-r is a microprocessor-based portable counting instrument capable of running a wide variety of detectors. The data logger was used in the rate meter mode with the Nal(TI) detector, and in the scaler mode with gas-flow proportional and GM detectors. Detector parameters (e.g., operating voltage, threshold, dead time setting, etc.) can ; be changed either through a bar-code reader or through the RS 232 serial I/O port. Set-up parameters for 16 different detectors can be stored in memory. The data logger also has a memory capacity capable of storing up to 250 measurements. The detector selected depended on the survey to be performed, surface O contour and survey area size. For alpha and beta measurements oflarge flat areas (i.e., Door, walls, etc.), a Ludlum Model 43-68100 cm2 gas-flow proportional detector was used. By changing the detector parameters, this detector was used for both alpha and beta detection. For non-uniform areas or areas where it was impractical to use a large area detector, a Ludlum Model 44-40 GM pancake detector was used. For exposure rates, a Ludlum Model 44-2 Nal(Tl) high energy gamma scintillation detector was used. Additional detectors were. fabricated to survey the internals of small bore piping ( < 6"). The data from these detectors was difHcult to quantify and was used only for informational purposes. All detectors were source checked to determine detection efficiency or response checked to determine detector operability twice daily, both before and after use. These checks ensured the reliability of the assigned ef6ciency and veri 6ed that the data quality objectives were satisDed. Instrument responses which were twice background were investigated for the presence of radioactive materials. O emtrumsmurttwimaxum 6-17 REVISION 0
FINAL SURVEY 6.6.2 Laboratory Instrumentation All smears were counted on a Tennelec Model LB-5100/W, low background gas-flow proportional counter. The gamma nuclide analyses of soil samples were performed using a Canberra Genie-PC* gamma spectroscopy system with a high purity intrinsic germanium (HPGe) detector. Background checks and source checks were performed on a daily basis for in-use laboratory instrumentation, except for the Canberra HPGe system. Background and source checks for the Canberra Genie-PC8 were performed on a weekly basis. 6.6.3 Instrument Calibration The Canberra Genie-PCs and Tennelec LB-5100/W were calibrated on an annual basis. The Model 2350 data logger with the appropriate detector was calibrated off-site on a semi-annual basis by Ludlum Measurements, Inc. in accordance with procedure INST-I-101, Calibration and Test Requirements for Radiation Protection Instrumentation. Additional calibrations were performed following the change of essential components for maintenance purposes or upon failure of QC check requirements. As stated above, the efficiency for each detector used with the data logger was measured daily. The pre-use g G efficiency values were used for all calculations. The sources used for source checks, response checks and calibrations for the instrumentation used are identified in Table 6-4. O 02279FPUlr6TnAMTLUERXWT7.RD 6-18 REVISION 0
FINAL SURVEY Table 6-4 O. Final Survey Instrumentation INSTRUMENT DETECTOR RADIATION SOURCE USE DETECTED Ludlum Model 2350/ alpha Th-230 surface 43-68 gas proportional contamination
"" * """ E Ludlum Model 2350/ beta Tc-99 43-68 Ludlum Model 2350/ Nal scintillator gamma Cs-137 exposure rate 44-2 Ludlum Model 2350/ GM beta-gamma Tc-99 restricted access 44-40 Canberra MCA HPGe gamma Mixed soil isotopic ,
Gamma, Am-241 Tennelec LB-5100/W alpha Po-210 removable gas proportional surface Tennelec LB-5100/W beta Tc-99 contamination and soils 6.7 Final Survey Techniques The final survey techniques described below apply to the surface measureme.,ts made in Building 100 and in Buildings 36, 60,111 and 131. Techniques used for soil sampling and analysis that pertain to the excavated areas in the reactor yard and the off-site locations are also described. The results of these building surface and soil measurements are summarized in Section 7.0. l l l O amo nursrrurruiwnum" 6-19 REVISION 0 l I
FLNAL SURVEY / 6.7.1 Building Surface Scanning V] ' GHdi6hiEingWispiff6Hfi@Eoie6]reHtl yitlisabf5fWsEd&EsjBiidisi fippuppppsupmentsj The purpose of scanning was to identify the presence of elevated beta-gamma readings or hot-spots. The detector used to perform the scanning was the same detector used to make the direct surface measurements. The detector was maintained as close as ; possible to the surface (approximately 1/2") and was moved across the surface at a slow speed (no more than I detector width per second). To i provide optimum sensitivity to changes in the instrument response, audible output was monitored. Earphones were used in higher noise ! areas. If elevated readings were found, the suspect area was investigated for further decontamination. 6.7.2 Building Surface Measurements - Direct A direct measurement for beta surface activity was performed near each corner and center of each grid using the 100 cm2 gas-flow proportional detector calibrated to Tc-99. The data logger was used in the scaler mode with a count time of 3 seconds. Using daily calculated efficiencies and local background measurements, an MDA value of approximately 1400 dpm/100 cm2 was achieved. The beta counts were corrected in i Paradox
- for the local background.
A direct measurement for alpha surface activity was performed at the center of each grid using the 100 cm2 gas-flow proportional detector system calibrated to Th-230. The data logger was used in the scaler mode with a count time of 60 seconds. Using daily calculated efficiencies and local background measurements, an MDA value of approximately 46ilpni/10Qcm 2was achieved. The gross alpha counts were corrected ; for the alpha background. 6.7.3 Building Surface Measurements - Removable A smear was taken at the center of each grid by wiping a 100 cm2 area of the surface with a dry cloth smear. Smears were counted for alpha and beta activity on the Tennelec counting system calibrated with Po-210 and Tc-99 sources, respectively. As shown in Table 6-3, the alpha and beta surface smears were counted for 2 minutes, yiciding MDAs of 12 l and 27 dpm/100 cm2 , respectively. ; l l
- c. ;
6-20 REVISION 1 Gt2293 PUBismAMTIAFI!LRX\AMPNin012
FINAL SURVEY Exposure rate measurements, in R/hr, were taken at I meter above the center of each grid in the pits, trench and mounds of soil. The Ludlum Model 2350/44-2 data logger / sodium iodide detector system, calibrated ; in pR/hr to Cs-137, was used for these measurements.. Direct alpha and beta surface measurements, in dpm/100 cm2 , were collected on contact with the soil at each grid in the pits, trench and mounds. The surveys consisted of 5 separate 3-second counts using the gas-flow proportional detector calibrated to Tc-99. To enable calculation of the fiet beta activity in dpm/100 cm2 , thiekjr6]ifidjaihnsijep6Ess~s were detehsifi5d at the beginning and end of each set of measurements. 6.7.7 Background Measurements Reactor Building Before a beta survey of eadi survey unit was performed, the background count rate was measured for the same survey unit. The same instrument was used for both the survey (Section 6.7.2) and background measurements. Three or more 1-minute (scaler) background measurements were made with the detector face shielded to screen beta radiation. Three additional background measurements were made at the end of the survey of each survey unit. The average of all six measurements was used as the background count rate in the data conversion calculation. Local alpha background values were determined in the same way as the beta background measurements. A plastic cover was placed over the detector face of the same instrument used for the alpha surface surveys (Section 6.7.2). A 10-minute scaler count was used for these alpha background measurements. These values were used for alpha background in the data conversion calculation. These alpha background measurements were performed before and after each alpha survey period, not necessarily by individual survey units. The alpha survey period was determined by the 250 data point memory 1 capacity of the data logger. It was necessary to keep the detector (s) in
]
Building 100 to maintain radon daughter equilibrium between the detector face and Building 100 environment. : O : 03amruusmemumoarmma 6-22 REVISION 1 l l l
FINAL SURVEY
- Q D
Buildines 36. 60. I11 and 131 Measurements
~
A series of measurements of concrete surfaces in Buildings 36,60,111 and 131 were collected to establish background for the laboratory , facilities at AMTL. These measurements included direct alpha, direct beta and gamma exposure rate in pR/hr at 1 meter. The same techniques and instrumentation used for Building 100 measurements described in - Section 6.7.5 were employed when collecting this data. Only the gamma exposure rate data was employed to determine the background benchmark. In an effort to more accurately reflect the true background exposure rate, a comparison was made between the micro-R meter and a pressurized ion chamber. This comparison was performed to allow for the correction of the energy dependent response of the - Nal(TI) detector. Unless calibrated to the specific energy spectrum of interest, instruments used to estimate exposure rate with high effective atomic numbers tend to over-respond as the photon energy decreases. Thirty measurements were taken simultaneously with each type of instrument throughout the basement of Building 36. The ratio between the average pressurized ion chamber reading and the average Nal(TI) - detector reading was 0.725; therefore, it is concluded that the micro-R meters used for the background study and the termination survey of the reactor building over respond by a factor of approximately 1.40. Unless specifically noted, none of the data presented in this report has been corrected. Off-site Soil Measurements Off-site radiological background data were obtained at the 36 locations discussed in Section 6.4.4. At each location, the vegetation and debris were cleared to expose approximately one square foot of soil. Samples of soil were obtained from each location using the procedure described-in Section 6.7.6 and were analyzed for gross alpha, gross beta and gamma radionuclides. Exposure rate measurements in pR/hr were made at 1 meter above the exposed area. As required by the Decommissioning Plan, alpha and beta surface measurements on contact with the soil were taken at the exposed surfaces to yield contact beta in dpm/100 cm2, , 6.7.8 Disposal of Samples All smear samples were disposed of as low-level radioactive waste. Soil samples have been archived in the basement of Building 36. O cmnew.snwerunmun" 6-23 REVISION 0
FINAL SURVEY 6.8 Documentation 6.8.1 Final Survey Data Records Records of final surveys were maintained in survey packages in accordance with AMTL-CHR-I-107, Tennination Survey Data Handling and Analysis. A separate package was prepared for each survey area. The specific records compiled in a survey package were:
- Termination Survey Package Worksheet giving the package identification, survey location information, historical information of -
area surveyed, general survey instructions and any specific survey instructions.
- Termination Survey Comment Addendum providing comments from the survey technician regarding any unusual situation that may have been encountered while surveying. If no unusual situation was identified, the survey package did not include this addendum. ,
- The Survey Unit Diagram provides a drawing of the area surveyed.
Survey grids are represented on the drawing.
- Photographs of the survey area were provided, as necessary, to O show special or unique conditions (e.g., the gamma facility, etc.)
- Printout of smear survey analyses. ,
- Printout of gamma spectroscopy results (if performed).
- Ludlum Model 2350 data files and Paradox
- converted values for all direct alpha, direct beta, and exposure rate measurements.
The survey work packages were tracked in a database for survey progress and maintained in a fireproof cabinet. 6.8.2 Data Processing, Management and Control Upon completion of a survey of an individual survey unit or combination of units, the contents of the data logger's memory were downloaded to a personal computer database. The download process utilized a proprietary program, developed by Ludlum Measurements, Inc., and th:n revised by SEG to fit specific needs at AMTL. Guidance for this data processing, management and control is given in AMTL-CHR-I-107, Termination Survey Data Handling and Analysis. O 1 mmwumsnumtuwn*"" 6-24 REVISION 0
FINAL SURVEY O During each data logger download, two data files were automatically ( generated. These files were sequentially assigned an identical index (file) < number by the software. The names of the two files were: DET_R AW and LOG _ RAW and are described as follows: DET _ RAW - This file contains the operating parameters for the detector used during the survey, including high voltage, threshold, window, count time, alarm settings, dead time correction value, calibration coefficient, operating mode, detector model and serial number. LOG _ RAW - This file contains all count data collected during the survey, including location code, logged counts, count time, alarm status (radiation, , battery status, overload current, etc.), surveyor ID, detector set-up number, time and date of survey. These files were automatically combined and translated into a Paradox
- database table. Additionally, in conjunction with the download process, a second Paradox
- table was manually updated. This file contained the p
s following information: the computer generated (assigned) file number, the survey description, data logger and detector serial numbers, detector efficiency in epm /dpm and the local background level in cpm. A printed report, referred to as Survey Report, was then generated for review. All raw data, converted data and information by survey location code were presented in the report. This report was reviewed by the survey technician for completeness, accuracy and flagged suspect entries. Any changes to the database tables sur'- as detector efficiency, background, etc., that could affect survey results required supervisor approval. In addition, changes to data in the primary table required a written explanation on a hard copy printout of the Survey Report. The marked-up hard copy was maintained as a permanent record. After review and correction (if needed) the local database LOGDDATA, was then transferred for analysis to two standard Paradox
- relational data tables. A discussion of the calculations for conversion of data is provided in Appendix D. All raw data, converted data and libraries were backed-up on tape daily; these backups were maintained in a separate building. An archive of all files was maintained off-site.
]
O !l 02229FPUinSTTW.TTUJLVJtX\007 RD 6 25 REVISION 0 l l i
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' FINAL SURVEY 'l ,
a f Data and document control included maintaining raw data files, translated data files (Paradox
- data files) and corrected data files showing l
documentation of all corrections. Paradox
- program scripts and related j data and information used for the development of the report were 1 identified and controlled, including modifications, to ensure accurate identification.
6.8.3 Laboratory Databases An Excel
- spreadsheet was used by the decommissioning radiochemistry laboratory to store alpha and beta-gamma removable surface contamination and soil gross activity measurements. Gamma . ,
spectroscopy results were maintained in a Canberra Genie-PCS database. These databases were backed-up and archived weekly. Printouts of smear and gamma spectroscopy results were generated for technician review and inclusion in the appropriate survey package. The Excel
- databases were transferred to a Paradox
- database for compilation and evaluation.
6.9 Quality Assurance / Quality Control 6.9.1 Quality Assurance Programs 4 Morrison Knudsen developed a O- Quality Assurance / Quality Control The GA/QC Plan was Plan based on the requirements of designed to provide 10 CFR 50, Appendix B as for described in Federal Register docuinentation tire (Vol. 53, No. 123), General protection of the health Requirements for and safety of project Decom:nissioning Nuclear personnel and the public Facilities, July 27, 1988. This and to provide verification QA/QC Plan incorporated of coinpliance with ' A NS1l A NS 1981 ,gguyugg,y ,.gquj,.ernents requirements 15.10gui, dance and . .
' # # # # I['.# 0 #" ###
provided in NUREG/CR-2082. . . The QAlQC Plan was designed to Decornnussioning Plan. provide documentation for the , protection of the health and safety l of project personnel and the public and to provide verification of l compliance with regulatory requirements identified in the l Decommissioning Plan. l 4 An essential element of the QA/QC Plan, the QC surveillance program, was implemented by Morrison Knudsen to assure decommissioning ; O om93-ruinstnxururxxxsocr7.r* 6-26 REVISION 0 i
FINAL SURVEY activities were performed in according with the Decommissioning Plan Os and project procedures. Audits were performed by Morrison Knudsen to determine proper implementation and measure the effectiveness of the Quality Program. QC personnel performed surveillances of all major activities associated with decommissioning. Specific activities examined included health and safety protection, radiological surveys and sampling, personnel and-environmental monitoring, and packaging of radioactive waste for disposal. Monthly QA Summary Reports were submitted to management ' to provide an assessment of surveillance results and evaluate. . implementation of the QA Program. Deficiencies identified through surveillances were documented on Quality Finding Reports and Non-conformance Reports. Deficiency documents were routed to supervision for evaluation and ' disposition. Each identified deficiency was assigned corrective action to be reviewed and approved by the Project Quality Manager prior to implementation. Once approved, corrective actions were then implemented to correct the deficiencies. QC personnel verified and documented correction of all deficiencies on surveillance reports. When completed, these reports and other project records were maintained in the records management system. 6.9.2 Field Instrumentation Radiation detection instrumentation used for the decontamination and dismantling work and final surveys were controlled, adjusted and calibrated at specified periods to maintain accuracy within specified limits. Procedures for calibration, maintenance, accountability,,yrtion and quality control of radiation detection instruments were developed to implement the guidelines established in American National Standard Institute (ANSI) standard ANSI N323-1978 and ANSI N42.17A-1989. t l r V marunumurrunmum 6-27 REVISION 0
FINAL SURVEY (^ ( A dedicated instrument repair and calibration facility was se: up to issue and control all radiation instrumentation and radioactive sources used by SEG at the AMTL site. A computer database and a status board were maintained for all instrumentation and sources to monitor status, location and calibration or leak check due dates. Health physics instrumentation engineers and specialists performed routine maintenance, repairs and calibrations throughout the decommissioning project with the following exceptions:
- All Model 2350's and associated detectors were calibrated by i Ludlum Measurements, Inc.
- All dose rate instruments were sent to an approved vendor contracted for the duration of the AMTL project.
Upon receipt of instruments calibrated by an off-site vendor, calibration certification paper work was reviewed for completeness and accuracy and, for dose rate instruments, initial response test data determined and documented prior to returning to service. All detectors used during surveys for direct measurement were given the following checks:
- All 100 cm 2detectors were subjected to a linearity check. This involved counting a NIST traceable source of known activity at each end of the detector, and ensuring that both counts fell within 20 %
of the mean of the counts. If an acceptable linearity check was obtained, an efficiency was calculated.
- An efficiency in cpm /dpm was determined for each detector used for direct beta-gamma and alpha measurements. The efficiency was determined daily before and after use. The pre-use efficiency was used to determine surface activity for all surveys done that day in dpm/100 cm 2,
- The post-use efficiency was used to check detector operability at the end of the day. An acceptability range of i20% was used to determine detector operability. If the post-use efficiency was not within the data quality objective of i20% of the pre-use efficiency, the lower efficiency of the two was used.
- The above checks were also carried out following any repairs or modifications to the Ludlum Model 2350/ detector set-up (e.g.,
mylar window change, change in high voltage cable, etc.) L cmurumstrumunmaxsoa7 an 6-28 REVISION 0
FINAL SURVEY f 7 Micro 2KWietefs::wsfe?id@onssibecEed[{oliletedhihf[6p6fhbililf hefore and after usecon a dailypasis. Any instruments that fa een the response or source checks were brought to the instrument facility ior testing. Due to the nature of gas-flow , proportional detectors, occasional pin hole leaks in the mylar covering were observed. Repairs to detector windows were made by the. instrumentation department or the vendor. All repairs were logged in a , maintenance history Gle. 6.9.3 Laboratory Instrumentation The decommissioning radiochemistry laboratory instrument QC program was developed and implemented to comply with requirements set forth in the Decommissioning Plan, QA/QC Plan and Sampling and Analysis
. Work Plan. The decommissioning radiochemistry laboratory contained a Tennelee low background gas-flow counter and a Canberra gamma spectroscopy system. The internal QC source checks and calibrations performed on this equipment are listed in Table 6-5. Procedures for calibration and operation oflaboratory equipment included AMTL-INST-1-406, Calibration ofLB-5100 Alpha / Beta Coimter, AMTL-INST-I-408, Q
NJ Calibration of Genie-PC" Gamma Spectroscopy System, AMTL-1NST 405, Operation of Tennelec LB-5100 Alpha / Beta Counter and AMTL-INST-1-407, Operation of Genie-PC* Gamma Spectroscopy System. i O 05m91 PUD %f\Ahfr!.\ FIN \RX\AMr.NDtDt2 6-29 REVISION I
FINAL SURVEY Any instruments that failed the response or source <: hecks were brought f] to the instrument facility for testing. Due to the nature of gas-flow (/ proportional detectors, occasional pin hole leaks in the mylar covering were observed. Repairs to detector windows were made by the instrumentation department or the vendor. All repairs were logged in a maintenance history file. 6.9.3 Laboratory Instrumentation The decommissioning radiochemistry laboratory instrument QC program was developed and implemented to comply with requirements set forth in the Decommissioning Plan, QA/QC Plan and Sampling and Analysis Work Plan. The decommissioning radiochemistry laboratory contained a Tennelec low background gas-flow counter and a Canberra gamma spectroscopy system. The internal QC source checks and calibrations performed on this equipment are listed in Table 6-5. Procedures for calibration and operation oflaboratory equipment included AMTL-INST-1-406, Calibration ofLB-5100 Alpha / Beta Counter, AMTL-INST-1-408, Calibration of Genie-PC* Gamma Spectroscopy System, AMTL-INST 405, Operation of Tennelec LB-5100 Alpha / Beta Counter and AMTL-INST-1-407, Operation of Genie-PC* Gamma Spectroscopy System, . O O onmwmsnwrrunn.axun an 6-29 REVISION 0
FINAL SURVEY , Table 6-5 Instrument Source Check, Response Check and Calibration Requirements Instrument Test Type Source Frequency References Ludlum Model 2350 instrument Electronic every six AMTL-INST-I-101 , data logger calibration calibration months Ludlum Model 2350/ detector source Th-230 twice daily AMTL-INST-I-101 43-68 (a) check when in t.se Ludlum Model 2350/ detector source Tc-99 twice daily AMTL-INST-l.101 43-68 (S) check when in use ; Ludlum Model 2350/ detector source Cs-137 twice daily AMTL-INST-I-101 44 2 (t) check when in use Ludlum Mode 2350/ detector source Tc-99 twice daily AMTL-INST-1-101 44-40 (67) check when m use 15.5 cm2 , Canberra Genie PCS gamma efficiency Mixed gamma once per year AMTL-INST-A-100 Gamma Spectroscopy calibration & Am-241 l System gamma energy Mixed gamma once per year AMTL-INST-A-100 l calibration & Am-241 or as needed gamma source Mixed gamma daily when in AMTL-INST-1-407 check & Am-241 use Tennelec LB-5100/W alpha efficiency Po-210 once per year AMTL-INST-A-100 (a.0) beta efficiency Te-99 once per year AMTL INST-A-100 source checks Po-210 daily when in AMTL-INST-1-405 Tc-99 use i Control charts, maintenance logs, calibration logs and sample analysis logs were maintained for all laboratory equipment. Chi-square tests were performed to check detection randomness and to define acceptable operating ranges for laboratory gas-flow proportional instrumentation. Calibration labels showing instrument identification number, calibration date and calibration due date were attached to all laboratory equipment. Background counts for the Canberra Genie PC8 Gamma Spectroscopy system were performed weekly, and source checks were performed daily. Background and source checks were performed on the Tennelec on a daily basis to ensure instrument operability. Reference standards traceable to NIST were used during calibration of instrumentation. ) i l l cnm-rumstrerrtsrtuixxsco7 no 6-30 REVISION 0
FINAL SURVEY - p 12boratory procedure AMTL-CHM-I-110, Laboratory Quality Control,
\ was developed to ensure that procedures for collecting and analyzing samples would not introduce variables into the sample chain. Field duplicate samples and a cross check program developed in AMTL-CHM-I-l10 were implemented to ensure accuracy and precision of analytical results.
Using the same sampling procedures,10 percent field duplicate samples were collected at the same time as the regular samples. Chain of Custody documentation accompanied the duplicate samples from the time of sampling to the time of analysis at the off-site environmental laboratories. Duplicate samples were collected by SEG technicians and these samples were sent to the U. S. Army Corps of Engineers for analysis.12boratory cross checks, supplied by Nonh America Scientific, Inc., were analyzed by the on-site laboratory to verify instrument calibration by checking instrument nuclide identification ability and counting accuracy. 6.9.4 Radioactive Sources Radioactive sources used at AMTL for decommissioning activities were controlled by Health Physics technicians in accordance with AMTL-RAM-1-102, Radioactive Source Inventory, Leak Testing and Disposal, and were maintained by the instrumentation facility. O Sources were stored in a locked cabinet and were issued as needed for field use. An issue log was maintained and reviewed daily to track the location of all sources issued. All sources were leak tested, using the smear method, upon arrival at AMTL. A source inventory was performed monthly, and subsequent leak tests were performed quarterly. Sources used for source checks, response checks and efficiency determination at AMTL are shown in Table 6-5. Sources used for calibration or efficiency determinations at AMTL, or by Ludlum Measurements, Inc., are traceable to National Institute of Standards and Technology. O marunrmrrwmxan" 6-31 REVISION 0
FINAL SURVEY 6.9.5 Verification Surveys , Verification surveys were performed following the final survey as required by the Decommissioning Plan. The Army Environmental Hygiene Agency was responsible to perform direct radiation measurements and soil analyses at a 1:10 ratio to the final survey. j Weston employees collected the soil verification samples for the Army Environmental Hygiene Agency. The purpose of these surveys was - to independently verify that final survey results were below the NRC guideline values for unrestricted use and the Massachusetts acceptance , criterion. The Army Environmental Hygiene Agency's verification survey results were not available at the time of this report. Additionally, representatives of the Commonwealth of Massachusetts collected confirmatory soil samples as requested by the NRC. 6.10 Data Reduction and Evaluation 6.10.1 Surface Surveys Direct alpha and beta surface measurements performed for the final surveys were conducted as discussed in Section 6.7.2. After the e direct surface survey for a particular area was completed, the raw data collected by the data logger were downloaded into Paradox *, A survey report of these alpha and beta surface measurements was 2 prepared showing the results in dpm/100 cm The contributions oflocal gamma radiation to the total counts of each beta measurement were subtracted as background in the conversion of 2 beta counts per unit time to beta dpm/100 cm It was conservatively assumed that 100% of the betas counted corresponded to the beta energies and abundance of Tc-99, which is a single beta emitter. 2 Data conversion from the raw counts per unit time into dpm/100 cm was performed as the report was printed. This report also flagged 2 any measurement result that exceeded 3,636 dpm/100 cm , or 73% of the 5,000 dpm/100 cm2 guideline value, which was an arbitrarily selected value for flagging suspect high readings. A discussion of this . conversion calculation is provided in Appendix D. Once a printout of the converted and flagged data file was available, the health physics technician who performed the survey reviewed the results. The purpose of this review was to ensure the data were properly coded for the area surveyed, recorded and complete, and to identify any data points that were flagged. In the event suspect high O mmrunscrwrtuwm" 6-32 REVISION 0
FINAL SURVEY readings were identified, a technician returned to the survey area and O' repeated the survey for each flagged location. Suca repeat surveys were expanded in scope to a 100% survey of the suspect grid plus the contiguous areas for a total of 9 square yards of 100% repeat coverage. When this repeat survey was completed, LOGDDATA was edited to replace the old data with the new survey results and the old data were transferred to an inactive file for retention. The surface beta survey results from Building 100 and the exhaust stack pad in dpm/100 cm2 were displayed for evaluation in a bar chart format. These graphs are presented in Figures A-39 through A-71. Graphs were produced for 32 areas within Building 100, which comprised the 10 survey areas in the building. They represent more than 16,500 data points for all 10 survey areas. The beta 2 2 dpm/100 cm values were plotted against the 5,000 dpm/100 cm average and 15,000 dpm/100 cm2 maximum beta-gamma guideline values. The graphs were evaluated by visual examination to identify any data points that exceeded the guideline values. The direct alpha surface measurements, data conversion reports and graphical representation used a similar method as described for the beta surveys. For the conversion of the raw alpha data, it was conservatively assumed that 100% of the alphas counted corresponded O' to the energy and abundance of Th-230. Background alpha readings in dpm/100 cm2 were subtracted in the conversion calculation. The converted alpha measurement results were reported for each grid 2 surveyed, and any readings over 50 dpm/100 cm , or 50% of the 100 dpm/100 cm2 guideline value, were flagged as suspect high results. Repeat surveys were performed as required. The surface alpha survey 2 results from Building 100 and the exhaust pad in dpm/100 cm are presented in a bar chart format in Figures A-10 through A-38. Graphs were produced for 28 areas within Building 100, which comprised the 10 smvey areas in the building. They represent more than 3,100 data points for all 10 survey areas. The alpha dpm/100 ; 2 cm2 values were plotted against the 100 dpm/100 cm average and 300 dpm/100 cm 2maximum alpha guideline values. The graphs were , evaluated by visual examination to identify any data points that exceeded the guideline values. O enwrw.srnurrmwnan" 6-33 REVISION 0
FINAL SURVEY 6.10.2 Removable Activity Surveys Gross alpha and gross beta removable activities were determined for all of the grids marked in Building 100 and on the exhaust stack pad by wiping a 100 cm 2area near the center of each grid and counting the smears in the decommissioning radiochemistry laboratory. The Tennelec alpha and beta counting systern used includes software 2 capabilities that convert the raw counts into alpha dpm/100 cm and beta dpm/100 cm2 . These smear results were reported from the Tennelec system in Excel *. The resultant report flagged suspect readings that were above the alpha and beta MDAs and any smears that exceeded the higher action level. If the action level was exceeded, the suspect grid was investigated for further decontamination and a new smear was taken. The results of the smear measurements were displayed for evaluation in bar chart format using Paradox
- software. These graphs are '
presented in Figures A-72 through A-131. Separate graphs were produced for 29 areas within Building 100 for alpha and beta removable activities. These 30 areas comprised the 10 survey areas 2 within Building 100. The alpha dpm/100 cm 2and beta dpm/100 cm 2 values were plotted against the 20 and 1,000 dpm/100 cm guideline values, respectively. These graphs represent more than 3,300 data O points for all 10 survey areas. The graphs were evaluated by visual examination to identify any data points that exceeded the guideline values. 6.10.3 Exposure Rate Surveys Exposure rate measurements at I meter were conducted for 100% of the grids in Building 100 and excavated areas of the reactor yard.- The data downloading from the data logger and the report preparation followed the same procedures as the surface surveys described above. The sodium iodide detector used for the surveys was calibrated to Cs-137. The data collected by the data logger were in units of R/hr. In the survey report, measurements that exceeded 25 gR/hr were flagged for further investigation. O m2m runsrrwrwwmarum 6-34 REVISION 0
FINAL SURVEY The survey results in pR/hr were displayed for evaluation in a bar chart format using Paradox
- software. These graphs are presented in Figures A-132 through A-158. Graphs were produced for 27 areas within Building 100, which comprised the 10 survey areas in the building. Graphs, shown in Figures B-2 through B-9, were also produced for 8 areas in the yard, which comprised the three survey creas in the yard. These graphs represent a more than 3,100 data points for all 13 survey areas. One graph was produced for the Building 100 exhaust stack pad, which is given in Figure A-159. The -
graphs were evaluated by visual examination to identify any data points that exceeded the guideline values. 6.10.4 Yard Soil Sample Analysis Yard soil samples were collected in 50% of the grids marked on the , excavated areas of the reactor yard and associated soil mounds. These 563 samples were analyzed for gross alpha and gross beta using the Tennelec Model LB 5100/W system, which was calibrated to Po-210 for alpha and Tc-99 for beta. The samples were also analyzed : for gamma-emitting nuclides using the Canberra gamma spectroscopy system, which was calibrated to a mixed gamma and Am-241 source. O Gross alpha and gross beta counts were reported by the Tennelec system. The gross results were manually entered into a spreadsheet where calculations converted the raw data into alpha pCi/g and beta pCi/g of soil and statistical evaluations were performed. In the spreadsheet, the gross alpha and gross beta concentrations reported for ' the 563 samples were compiled into the appropriate yard survey unit. There were 8 survey units in the yard, which comprised the 3 yard survey areas. The gross alpha and gross beta data from the yard samples are presented in Table B-1 through B-8. The gamma spectroscopic raw data were reported by the Canberra system software in pCi/g values for the radionuclides detected. The Canberra report produced for each of the samples analyzed was reviewed by a radiochemistry laboratory technician and supervisor for , completeness. The applicable guideline values were the average background concentration plus three standard deviations for each man- i made radionuclide detected. The results of the 563 samples were taken from the Canberra report and manually entered into a Quattro ; Pro
- spreadsheet for the conversion to pCilg and statistical evaluation discussed above. The gamma nuclide data from the yard samples are presented in Tables B-9 through B-24.
O enmancsnwenwxam
- 6-35 REVISION 0 l
i
FINAL SURVEY-6.10.5 Background Exposure rate surveys performed in Buildings 36,60,111 and 131 were used to establish background exposure rates for application to Building 100. These surveys were made using the same instrumentation and procedures as discussed above. The readings were taken in pR/hr at 1 . meter. A total of 210 measurements of concrete floor and wall surfaces in these four buildings were recorded. The exposure rate survey results of the four buildings were displayed for evaluation in a br.r chart format. This graph of the combined results from all four buildings is presented in Figure C-2. The results from each of the buildings are graphically , displayed in Figures C-3 through C-6. It may be noted that the average exposure rate from Building 60 alone was lower than the composite of the 210 data points. The laboratory analysis of soil samples obtained at the off-site locations consisted of gross alpha, gross beta and gamma nuclide determinations. Exposure rates in pR/hr at 1 meter were also measured at these locations. The same instrumentation, analytical and data transfer procedures and calculations were used as discussed above. The gross alpha and gross beta results from the Tennelec system and results from the Canberra gamma spectroscopic system were manually entered into a spreadsheet for statistical evaluation, as discussed in Section 6.11. The gamma O spectroscopic values and the gross alpha and gross beta values are given in the spreadsheets in Table C-2 and Table C-3, respectively. The results of the exposure rate measurements at the off-site locations are given in Table C-4. 6.11 Statistical Evaluation The estimated mean a'.d standard deviatiori were calculated for the survey measurements and labor: tory analyses. These calculations were performed using data that are reported in sevtral locations in this report. The graphs of data (Figures A-10 through A-159, B-2 through B-9, and C-2 tfirough C-6) were prepared from s database. Tables of data (Tables B-1 through B-24 and C-2 through C-9) were prepared from spreadsheets. Equations used for calculation are presented in Appendix D. t iddi91 dual lddtsis6irds From a visualfexaniination 6fJthe giaphiand^ tables [illl6fi he were clearlyj belowf thelig corresponding average guidelipiyaluedthdreforedno additional; statistical evaluatioiis were requiredi O masmorstrmnunmmmma 6-36 REVISION 1
l FINAL SURVEY In^thEcisE6fliGildins100'alphiT5Kd beEdifscisdffice dieassresid51s766wei7sfithE O upper bosridyf i thimedngthe 95(confidence level:ivas caledist6d to evalsste the datal fSimilar/salestatidhs for,cxposure rstes at the 99% cotifidence Isvel were also
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FINAL SURVEY FINDINGS 7.0 FINAL SURVEY FINDINGS 7.1 Final Survey Results The final survey of Building 100 and excavated portions of the reactor yard consisted of the measurements referenced in Table 7-1. Table 7-1 Final Survey Measurement Index , Final Survey Measurement Summary Survey Data of Results , Buildine 100 direct surface alpha Table 7-2 Firures A-10 throuch A-38 Buildine 100 direct surface beta Table 7-3 Ficures A-39 throurh A-71 P Building 100 removable alpha and beta Table 7-4 Firures A-72 throuch A-131 Building 100 and exhaust stack pad Table 7-5 Figures A-132 through A-159 exposure rate at I meter l I Yard soil cross alpha and cross beta Table 7-6 Tables D-1 throuch B-8 Yard soil exposure rate at 1 meter Table 7-7 Firures B-2 throuch B-9 Yard soil pamma radionuclides Table 7-8 Tahis B-10 through B-17 The results of these final survey measurements are summarized in the seven tables that follow. The survey data for Building 100 are graphed and tabulated in Figures A10 through A159. Each of the areas listed in Table 7-2 inrough 7-5 corresponds to one of the 150 graphs in these figures. The yard soil survey data are presented in Figures B-2 through B-9 and Tables B-1 through B97. Cross sections of Building 100 and a drawing of the yard are provided in Figures 7-1 through 7-4 as an aid to understanding the spatial relationships of these areas. Additionally, the Decommissioning Plan required that contact beta and contact alpha measurements, in dpm/100 cm2 , of the yard excavations be performed. The results of these measurements are provided in graphical format in Figures B-10 through B-25. Although these contact measurements would be useful to indicate relative levels of soil contamination, no correlation was available to convert the units into pCi/g. Consequently, these measurements are not presented in this section for comparison to guideline values. O 450391 PUInSmA MTL\rINiRX\AMIND IH3 7-1 REVISION 1
l FINAL SURVEY FINDINGS l The results of off-site soil sample analyses and exposure rate surveys to establish O background benchmarks for comparison to the samples and surveys of the excavated areas of the reactor yard are presented in Section 7.2. The background exposure rate surveys for concrete conducted in Buildings 36,60,111 and 131 for comparison to Building 100 are presented in Section 7.2. SErvdps 6fjWstfati6hs aiid'elebirical b6xeslthroughout'Buildisifl00 indiasisd*that ' licensed radioacti0e materials were~not presentdThis~ survey;in~cluded direct readings _ as';well as nicasiiremsnts 6f rem 6vable contamination. Eight penetrntions sxhibited klightlylhlhvaiedShadings. [Shvenfof these;were: honed and[the)resulting(dsbfis collected foriammaspectral analysis. InLaddition,(these penetrations wsre wiped WithlMisslikbe.foi'e andldfter honing.1The masslikwas'savedifor gamma (spectral ahalysis.fThe jtsel! liner frbm;the eighth penetration was relnoVed hnd cutlopen for ; additional. Analysis: including gammaTspectroscopy; ;None;of the'gamina$spediral analyses, assobiated j withithesej penetmtions ;ideritified anyj licchsed }radioaEtive material; O O merw.strumswmummm 7-2 REVISION 1
FINAL SURVEY FINDINGS Table 7-2 Building 100 Direct Surface Alpha Summary Statistics (dpm/100 cm2) Area Mean St d. MDA Upper Bound of the Maximum Number of Standard Error Dev. Mesa at 95% CL Reedma Mammuresnents of the Mena heaement, Ceilms 11 18 58 15 44 67 2 Basement Drama 5 15 58 8 47 76 2 hamnent. Gamma Well 5 10 58 8 43 54 1 bement NE Quad. Ihr !! I'. 58 12 45 125 i Bamnent. NE Quad. Wall 9 13 58 11 59 236 1 Damernent, NW Quad. Floor 11 10 58 13 40 135 1 Danement. NW Quad. Wa11 9 12 58 10 56 190 1 homement. SE Quad, floor 6 13 58 8 52 129 1 Danement. SE Quad. Wall 12 16 58 14 93 263 1 Danement, SW Quad. Ihr 10 12 58 12 53 135 1 beacment. SW Quad. Wall 11 14 38 13 62 192 1 Flamement, Stairwell One 17 16 58 20 63 77 2 Basement, stairwe!! Two 20 14 58 22 56 139 1 Inmacment, Strudurce 4 10 58 8 26 17 2 s Benement. Sump 30 9 58 -8 13 40 1 Bamneet. Trenchen 5 15 58 8 47 61 2 Containment Dome 9 21 58 12 89 170 2 Crane 21 21 58 26 65 46 3 T4uipment Hatch 4 13 58 7 46 63 2 Operadng Deck. Airlock 1 7 15 58 9 57 107 i Operating Ded. Airkuk 2 10 14 58 12 52 98 i Operstmg 1Ak, NE Thr 5 12 58 -3 32 101 I Operating Detk, NW lhr 12 13 58 14 42 101 1 Operstmg Deck, SE Iloor 6 11 58 8 47 210 1 Operating twk, SW lhr 10 12 58 12 47 107 1 Operating Deck Wall to 2 Yania 20 15 58 22 64 150 1 Opendng Deck. Wall > 2 Yards 24 20 58 28 76 81 2 Remains of 11stforma !&2 24 15 58 30 59 20 3 TahaustS w kIW -6 5 58 5 to 60 1 02269numsrniwam.no 7-3 REVISION 0
1 FINAL SURVEY FINDINGS Table 7-3 Iluilding 100 Direct Surface Beta Summary Statistics - . (dpm/100 cm2) Upper bund Standard Area Mesa St d. MDA el the Mesa al Maximum Nmaber of Error of the tw. 95% CL Readmg Measuremmts Mesa bement, Ceiling 320 410 1400 360 1410 341 20 Nement. Drains 420 390 1400 460 1650 355 20 Nrment. ILctrical Pen. 4 60 530 2700 -310 580 35 90 Nement. Gamma Well 230 340 1400 260 1250 270 20 Nement. NE Quad. Ihr 290 380 1400 320 1770 630 20 Nement. NE Quad. Wall 190 400 1400 210 2290 1422 10 Nement, NW Quad, f%r 320 370 1400 340 1730 675 10 hement. NW Quad. Wall 190 360 1400 210 1620 948 10 bcment. Piping Penet. 70 790 2700 180 3360 148 70 l Neenent. SE Ound. Thr 520 400 1400 540 1800 651 20 bement. SE Quad. Well 390 430 1400 410 1900 1310 10
'l liancment. SW Ound. Ihr 300 410 1400 320 1750 675 20 Nement. SW Quad. Well 230 390 1400 250 1740 961 10
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Ncment. Stairwell One 390 400 1400 420 2040 542 20 l bement. Stairwell Two 420 410 1400 440 1760 759 10 k bement. Structures 520 1010 1400 630 3590 239 70 bement. Sump 400 400 1400 450 1370 200 30 bement. Trenches 440 380 1400 4B0 1650 310 20 { l Containment Dome 160 330 1400 180 1620 755 10 Crane 80 370 1400 120 1030 230 20 Equipment Hatch 50 400 1400 20 1380 345 20 1 Operstar thk Dec. Pen -20 650 2700 170 2500 34 110 Operating thk Wall to 2 Yania 320 400 1400 340 1870 000 10 Operatin; Deck. Airkx k 1 10 370 1400 20 1770 535 20 Operating Deck. Airkk 2 60 270 1400 80 1080 490 10 Operating Deck. NE Thr 390 400 1400 420 1650 505 20 Operating Deck. NW lhr 470 400 14'vl 500 1750 510 20 Operating thk. Pye Pen 150 780 2700 570 1590 11 230 Operating Deck SE Ihr 460 390 1400 490 1860 515 20 Operating Deck SW Roor 430 420 1400 460 1820 612 20 Operating Deck. Wall > 2 Yants 390 390 1400 420 1760 540 20 Remains of Matforms 18.2 390 370 1400 4RO 1390 50 50 Exhaun Stwk 1%1 660 490 1400 710 2730 300 30 ans93.Pumsmrwuum 7-4 REVISION 0 l
FINAL SURVEY FINDINGS (g Table 7-4 Building 100 Removable Alpha and Beta Summary Statistics (dpm/100 cm2) Cross Alpha Gross Beta Surface Samples Average Maximum MDA Average Maximum MDA Naemmt Ceil ng 67 0 7 12 0 15 27 bement Drama 10 0 2 12 -1 5 27 hement I'lectrical Pen. 35 0 2 12 1 11 27 Nement Gamma Well 54 0 2 12 -1 10 27 Naemmt NE Quad. Ihr 135 0 4 12 1 11 27 Nsement NE Quad. Wah 192 0 4 12 -1 17 27 Naemmt NW Quad. Ihr 125 0 4 .2 1 15 27 Naement NW Quad. Wah 2 54 0 4 12 0 13 27 bement lying Penet. 119 0 4 12 0 20 27 Nacment SE Quad. Ihr 135 0 4 12 0 13 27 Nement SE Quad. Walls 190 0 4 12 -l 13 27 bement SW Quad. Ihr 129 0 4 12 2 20 27 Nement SW Quad. Walls 262 0 9 12 1 20 27 Nacment Stairwen One 107 0 7 12 0 13 27 bement Stairwcu Two llo 0 7 12 1 18 27 bement Structurm 15 1 2 12 3 11 27 Naement Sump 20 0 7 12 1 A 27 bement Trenches 62 0 2 12 1 13 27 Containment Dome 152 0 2 12 -1 12 27 Crane 46 1 7 12 3 18 27 Equipmentitetch 63 0 4 12 0 16 27 Operating Deck Airksk i 105 1 7 12 1 18 27 Operating Deck Airlock 2 100 0 4 12 1 18 27 Operating De.k Dec. Pen. 30 0 4 12 0 9 27 Operating Deck ihr* 432 0 7 12 0 16 27 Operating Deck Piping Pen 37 0 7 12 I 10 27 Opern6ng De<k Wall > 2 Yards IOR 0 4 12 0 13 27 Operating De4 k Walls to 2 Yards 151 0 4 12 -2 9 27 Remairu of Platforna I&2 20 0 4 12 0 9 27 Exhaust Stack Pad 60 0 7 12 1 11 27 She Opernung Deck Thr consats of all four quadranis. On693-PumsmIwmoono 7-5 REVISION 0
44-- -s 4.4,4.--J--*4- .L- ,2 k., 4 .IM4 m4di 4f 4 w+=e a 4----.E3 -A+L--=4 # l FINAL SURVEY FINDINGS
- O Table 7-5
- Building 100 Exposure Rate at One Meter Summary Statistics
( R/hr) Area Mean Sad. Maximums Nmaher of Dev. Reading Measurunents l Basement Ceiling 13.6 1.2 16.7 75 i Besement, Draina 13 3 1.3 15.8 68 Basenunt, Gamma Well 13.5 0.7 14.6 8 Basement NE Quad. Floor 13.5 0.8 16.1 129 l Basement, NE Quad. Wall 13.6 1 16 286 Base.nent NW Quad. Floor 13.6 0.5 14.5 135 Basement, NW Quad. Wall 13 3 1 15.1 '192 Basement, SE Quad. Floor 14.8 1.1 17.5 129 Basement SE Quad. Wall 14.4 1.6 18.7 263 Basement, SW Quad. Floor 13.9 0.9 17.5 135 , Basenwnt, SW Quad. Wall . 14 1 16.5 191 Basement, stairwell One 13.1 0.5 14.5 107 Basement, Stairwell Two 13.4 - 1.1 16 3 111 Basement, Structures 14.3 0.9 18.4 70 Basement, Sump 15.2 0.6 16 6 Basement. Trenches 13.6 0.9 15.8 - 63 containment Dome 4.1 0.5 5.1 151 Crane 4.9 0.7 63 46 Equipment listch 11.5 ' 13 14 3 63 Operating Deck, Airlock I 73 1.1 12.1 108 Operating Deck. Airlock 2 6.6 0.5 8.2 98 Operating Deck, NE Floor 11.4 03 12 3 101 Operating Deck, NW Floor 10.8 0.6 12.5 102 Operating Deck SB Floor 11 0.7 12.6 103 Operating Deck SW Floor 10.8 0.9 13.4 117 Operating Deck Wall to 2 Yards Il' O.7 12.7- ~ 150
- Operating Deck. Wall > 2 Yards il 0.6 - 12.7 114 Exhaust Stack Pad '15.4 1.1 18 60 ons.rumsmnmammu 76 REVISION 0 -
FINAL SURVEY FINDINGS : Table 7-6 ; c p/ s Reactor Yard Soil Gross Alpha and Gross lieta Summary Statistics i (pCi/g) Analysir Gross Alpha Gross Beta Reactor Yard Soil Sample Mean Std Mean Std Location Dev Dev XMofPipsbliisiTSErfEEs? Bf 51 233 20)
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FLNAL SURVEY FINDINGS Table 7-7 Reactor Yard Soil Exposure Rate at One Meter Summary Statistics (pR/hr) Area hican" Std. Ataximum Number of Dev. Reading bicasurements Secondary Sump Trench 14.2 1.3 17.2 160 Ama 0, Dirt Mound A 12.9 0.6 14.1 28 Area 1, Dirt Mound A 14.1 1 16.4 165 Area 1, Dirt Mound B 14.7 1.3 18 104 Area 2, Dirt Mound A 13.8 0.8 15.3 31 Area 2, Dirt Mound B 11.5 1.3 14 72 Cistern 242 Trench 14.2 0.9 16.4 90 Pipe Chase Trench 14 1.1 16.5 64 "The weighted mean for all measurements is 13.9 R/hr; the standard deviation is 1.13. O I k f onen rumsrnnmax"" 7-8 REVISION 0
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O FINAL SURVEY FDmiNGS Table 7-8 Sununary of Gamma Spectroscopy Analyses for Reactor Yartl Soil Saniples (Mean in pCi/g) ANALYSIS K-40 Cs-137 TI-208 Bi-212 Pb-212 Bi-214 Pb-214 Ra-224 Ra-226 Ac-228 Th-234 Co-60 F#152 En.154 dha DT PipedaE surfasi'soll b.14;! D3i
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emm emm . , N LEGEND NOTES 1 PATTERNS SHOWN ON CONTAINMENT WALL DEPICTS ACTUAL DESIGN AND GRID LAYOUT USED FOR SURVEYING CONTAINMENT WALLS 2 GRIDS ON EASEMENT FALL AP,E 3 FOOT GRIDS 3 FIRST TWO ROWS OF GR!DS ON CONTAINMENT WALL ( 6 FEL'T UP FROM DPERATING DECK FLOOR) ARE 3 FOOT GRIDS ABOVE FIRST TWO R0nS OF GRIDS ARE 3 METERS X 3 METERS nr. sunu I Figure 7-1 i Building 100 Cross-Sectional View (Facing South) I 1 1 O v ) i cnm.rursrrnurnams.o 7-10 REVISION 0 ; i
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FLNAL SURVEY FINDLNGS FLOOR REMOVED DURING b-DECOMu1SS10NING STAIRWELL Tl NORTHWEST QUADRANT , NORTHEAST QUADRANT FLOOR 1 , FLOOR 2 AIRLOCK 1 \
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camamsmnmuwx*" 7-11 REVISION 0
a & aa - - FINAL SURVEY FINDINGS l NORTH STAIRWELL O e i, , GAMMA WELL
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NOTE EACH AREA SEPARATED BY OUADRANTS INCLUDES ALL 5 ALL AND CEILINC SURFACES. COLUMNS. STRUCTURES. AND PENETRATIONS CONTAINED RITH!N FI E ORX81A THE AREA Figure 7-3 Building 100 Basement Floor Plan t O , c:an.ruumrvurra*" 7-12 REVISION 0 1
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FINAL SURVEY FINDINGS 7.2 Background Results 7.2.1 Building 100 Surfaces The background measurements taken at each survey unit using the gas-flow 100 cm2 detector were averaged. The result, in epm, was used in the calculation to convert gross instrument responses to net beta dpm/100 cm2. The mean epm values for the background can be found in each survey file located in the survey packages. , This method was also applied to direct alpha surface measurements. The background readings for alpha included radon daughter products that were plated out on the detector face. The mean epm values for alpha background are presented in each survey file located in the survey packages. 7.2.2 Radiological Characterization of Buildings 36,60,111 and 131 Exposure rate measurements in R/hr in Buildings 36, 60,111 and 131 were conducted to provide background exposure rate data for the AMTL facilities. Structural concrete surfaces included in these background surveys were used to establish a background benchmark for Building 100 exposure rates. The rationale for selecting these buildings is presented in Section 6.4.4, and the measurement techniques applied are discussed in Section 6.7.7. The summary results of these exposure rate surveys are given in Table 7-9. A graphical presentation of these survey data are given in Figures C-2 through C-6. Table 7-9 Summary Results of the One Meter Exposure Rate Measurements from AMTL Buildings 36,60,111 and 131 Measurement Number of Mean Standard Maximum Mean + Measurements ( R/hr) Deviation Reading (pR/hr) 5 R/:a Buildings 36, 210 16.7 3.5 27.0 21.7 60,111 and 131 Building 36 90 16.9 2.0 22.1 21.9 Building 60 60 13.2 2.2 21.1 18.2 Building 111 30 20.3 3.5 27.0 25.3 Building 131 30 19.6 2.6 24.3 24.6 O M2693-PUInSTNWJtN" 7-14 REVISION 9
FINAL SURVEY FINDINGS 7.2.3 Off-site Soil Measurements Gross Aloha and Gross Beta The soil samples' collected at the 36 off-site locations were analyzed by !' the on-site decommissioning radiochemistry laboratory. The results of all 36 gross alpha and gross beta measurements are provided in Table C-3. The means of these gross alpha and gross beta background soil measurements plus 3 standard deviations are given in Table 7-10. Tiiiilliffi0iidiff1661il6iHiirisiEDTliEFEisiEE6iFelsil6iiTeiWisiiTtliEss Iss01hYdliS$1res0lisfof[tliNl gam $naNpectf$lidridljsssN1n[ decisions t bonceFning"s6iljsainple hnalysesfwer6jased/ prim;nilpynjanissped@ knalysis{after ytkiiijjntn6 count ths p@sibilitfpf puic hipha'and/otbeti ymjttersj Table 7-10 Summary Results of the Gross Alpha and Gross Beta Off-site Soil Analyses
= .
s Type of Number of Mean Estimated Mean + 3s Measurement Measurements (pCi/g) Standard (pCi/g) (~' Deviation (s) Gross Alpha 36 0.5 6 18.5 Activity Gross Beta 36 -8 60 172 Activity hI Soil Gamma Radionuclides The off-site soil samples were analyzed for gamma nuclides using the Canberra HPGe gamma spectroscopy system. The results are provided in Table C-2. These analyses showed that the gamma nuclides in the soil were naturally occurring, with the exception of Cs-137, and that they consisted of K-40 and members of either the uranium or thorium decay _l series. As shown in Table 7-11, the average concentration of Cs-137 i present in the 36 samples was 0.4 pCi/g. This value plus three standard j deviations yielded a guideline value for Cs-137 of 1.6 pCi/g of soil. l O : l oserumsnuunamxuma" 7-15 REVISION 1 l l
FINAL SURVEY FINDINGS /' Table 7-11 i Summary Results of Off-site Soil Gamma Spectroscopic Analyses l Radionuclide Number of Mean Standard Mean + 3s Measurements (pCi/g) Deviation (pCi/g) Cs-137 36 0.4 .4 1.6 t TWo 6f thE~shiiplesNerF~setjiloff-;siteffuricsl{ anal /sisGThETesnhish6W&fihil i C314lwss not.jp esen[in th.ese soil; samplesi Soil Exposure Rate At the off-site soil sampling locations, exposure rate measurements in R/hr were performed at I meter above the soil using the Nal(TI) detector. The results of the these measurements are provided in Table C-4 and are summarized in Table 7-12. The mean of these off-site exposure rate measurements was 12 pR/hr. This mean value plus 5 R/hr yielded the guideline value of 17 R/hr. Table 7-12 Summary Results of the One Meter Exposure Rate Measurements O Taken at Each Off-site Location Measurement Number of Mean Standard Mean + 5 Measurements R/hr Deviation pR/hr 1 Exposure Rate 36 12 1.3 17.0 at 1 Meter In addition to the soil background measurements given above, the Decommissioning Plan required that contact alpha and beta measurements be performed. The results of these measurements are provided in Tables C-5 EEd Cf6.isiiiEtisblj. l l l l l l O momrwsnwnurnmurm" 7-16 REVISION 1
FINAL SURVEY FINDINGS (G 7.3 Comparison of Final Survey Results to Guideline Values 7.3.1 Building 100 Alpha and Beta Activities A comparison of the direct and removable alpha and beta results from Building 100 with their respective guideline values is presented in , Table 7-13. Siiics^f 66~fsi5gidFdfi6ct%1phsTEsisifiEM6rin*sI6bsddd 2 300"dFni/100?cm fanUnoisingisidirsittbst@nieasnremeiitfeisceded 5000 dpm/100"bm 2measdrenients;averagedfoVs6:lisil ssre9 :ineter5sts 2 les_s(thanithe gnidelineralsesjfor[sveragelactiiitpMFurtheythelupper bound'of the?meanWaalcslated:for thesshsasurements to ceftify:that t the truelaysrage bf suivef3ata for 66ntiguduitspi6ss fest the guidelisss ht a 95'isonfidence levelf'Thilifrvef ressitigiveiiiTTable 7-lfWsrb ihkedTrbiiiTablsi712 ihr6 ugh 7-4. The guideline values given in Table 7-13 were taken from Table 6-2. Examination of Table 7-13 shows that all four parameters listed are far below the applicable guideline values. A summary of the exhaust stack pad results of the four parameters is provided as footnotes to Table 7-13, and these values are also well below - the guideline values. Table 7-13 Comparison of Building 100 Alpha and Beta Final Survey Results to Guideline Values Ifighest Value of Surface Iliphest Value of Surface Upper Bound of Guideline Value Maximmn Guideline Value Parameter the Mean at Average Reading Maximmn 95% CL' (dpm/100 cm 2) (dpm/100 cm2) (dpm/100 cm2) (dpm/100 cm2) 6 Direct surface 30
- 100 93 300 alpha Direct surface 630 ' 5,000 3,590
- 15,000 beta Removable NA NA 9* 20 alpha Removable beta NA NA 20
- 1,000
*rhe direct surface alpha and beta values for the exhaust stack pad were -5 and 710 dpnv100 cnf, respectively.
%e direct surface alpha and beta values for the exhaust stack pad were 10 and 2.730 dpnv100 cnf, respectively, "The removable alpha and beta values for the exhaust stack pad were 7 and 11 dpm/100 cuf, rupectively.
%iis'vahtaaicalculated to aid in data"evaluatiou pe[(draft);NUREG.5849, _
requation 8 3; m U osm93.runtsrrsruTttrintaxwursu" 7-17 REVISION I
k FINAL SURVI'N FINDINGS 7.3.2 Building 100 Exposure Rate , A comparison of the exposure rate , results from Building 100 and the The highest value of 78If
~
exhaust stack pad with the pgjg, jg, gygygggg fgg guidehne value is presented in Table 7-14. The survey results and the lidt~iliii value of
~ -
given in this table were taken 18] R/hrforthe exhaust from Table 7-5. The guideline stack pad were well below value is from an average of the guideline value of Buildings 36, 60,111 and 131 21.7 pR/hr. exposure rate measurements given , in Table 7-9 plus 5 pR/hr. The : highest value of ]8] pR/hr for Building 100 and the hijjin value of[18i0 pR/hr for the exhaust stack pad were well below the guideline value of 21.7 pR/hr. O l i l l l O owmwmstrerrunwsmurun" 7-17a REVISION 1
FINAL SURVEY FINDINGS A Table 7-14 .() Comparison of Building 100 Final Survey Exposure Rate Results to the Guideline Value Exposure Rate Guideline Value Area ( R/hr) ( R/hr) liighest hip 6sienismsasUismisd in Building 100 38!7 21.7
- NNhQyQQ%ppQi^tKi exhaust stack j8 Q 21.7 * ,
pad
*Mean value ol' Building 36,60,1I1 and 131 (see Table 7-9) plus 5 pRlhr.
7.3.3 Reactor Yard Gamma Nuclide Spectroscopy A comparison of the soil gamma nuclide spectroscopic analyses with the guideline value is presented in Table 7-15. The spectroscopic analyses were performed on soil samples collected from the excavated areas of the reactor yard. The comparison was made using the highest concentration of Cs-137 found in the soil samples. Cesium-137 was the only man-made gamma nuclide identified in the analyses. The Cs-137 result given in Table 7-15 was taken from Table 7-8, and the guideline value for Cs-137 was taken from Table 7-11. As shown in Table 7-15, the highest concentration of Cs-137 in the soil at the 8 yard areas was 0.57 pCi/g, which is less than the guideline value of 1.6 pCi/g. < These Esissithipb6fios25pi5"shilysEislsbithiddisil TIE 2 rih ^iW6siisp!si at cohceittiati6nslof 0;66ind10.96Ci/g? whi6h late giyenjn f51siBsil. andiB2154respestivelf@is234)is Edaughteridf'and lis?in?.squilibliurn
$sith(D12385Altb6ushlU-238 Mas'n6t A kitential
~
I 56.nlaisinani; ass 0ciaidd s i,vithithsfreactosfacilit 2 Wits;presenc@could-[6efaccosntsdNo
' depleted LUraniiimissd'iii ihelnonfresciorj facilities:aF^MTLfo$ nat
! i urasism:in"thdsdilhT66 rnean levef f6nTb
~
234 in'6ff siie soillhs d96 kCilg.JTherifolrettiie' levels *6fith%34[ir(ihitw(yard [samplssjan bj attributed ;tol naturally (ocestririgimaterials) TWbledstoy sifsisiplssWEfefisdi[6ff-sif636KC4145Ksiffsis3Ths resultishofed;that C-14~was x not present in thysoil samplss; ' i l O l m39numsm^ururannsrurstntao 7-18 REVISION 1 l
FINAL SURVEY FINDINGS Soil Exoosure Rate TEsirbs61[iTof?ioil' Esp 6sHf67stsT6iEds6feissehis"51MisitdEf6EEdEh'f'ifd hies:sre" iveniinLFi ures::B22iind?B-91 T506i~Irisdi 6f~ih5 ex'sird riie~iEEisui5inihiEo 'ih6 endiViiEd"fird areas with the guideline value is presented in Table 7-15. The exposure rate guideline value given in Table 7-15 was taken from Table 7-12. F65EiridiVidasF5iiesshrEdieHis EXE65dEdTihs"gdidulin69h16e"of717WA E!"Xfsh6WE'iE' Tab 1E'7:15;~thE ~ hijheit"Eiji6^sufEisiE^fdTthi excapated yErd areas was 18.'O R/hr. $611 sanipli hoesVe.n
~ .
fho 'inalyies' ass 6Blif6d5With?
. ~m_sn m. .hd.e nuclides^a.bbve'.the.E
- .. - .3P- plicable:ad
. - ~. j weir 67F6Yiised thi'sleistedifsidinji,iisi:le. Veishve pre,sent; Soil Gross Alpha and Gross Beta i
The Decommissioning Plan required characterization of the excavated areas of the reactor yard for gross alpha and gross beta activities. The means of off-site gross alpha and beta activities plus three standard deviations were computed for comparison to the yard results. The mean 6f ths]f65sTsiphi"Endyr6silbsti results of the 36 Bff-sits ^5611"shalp'ssi ahdjthe respsetiVe sEtibn levels of!!8 5fliCi[g[Elphhlandj72fpCilg bets are presented m Tabis.i7/1_0; THEir6ss~sipEa~ahd 6Eii~sdalises 6fihbsyaFdii6ilTsiusplis YisiifisEsiEd.
- in Tables lB-1:throughlB48hAn eihminhtion 6f thesefesnitsrevealsd that . 141sampl6sfexceeded?thefalphajsEtiohilevel[and(oneldf theselssmplsi bxceededfths"glros's Weie:revisked (Tables B 10;thf6bsts 1 ugh: actichilevelMNuclide'ddhlysesLof these nndThi2341Was^ndi"detebied .
one s thpid st%nss6tratiodiofthe in Any"oflthe341ssinpleidThsrefof67 0.5 gr pCilg'6sfsiklinjisbOVithb s&ti6h
.i.svelsf_ee_rei_co._nieLuen_ce_?of_nii_drs._li_id_ioasti_ds_0ns_ie.ri_al_s THETisaiysii?~ofEd6fii[isdijiiifEihlbilid7MI5AWaIEEiM69ETdiE Epplichble' action level due tollow sampishiasfRA"midagement' decision was made n61 to relanalyze'lliese saihplssbThbl cost-lisnefit'.wobid'noilbs ju'stifiables because2 theseM measurementsMsret hotM guidelideMalue measdremehtsf iTheiejis}no/sorrelAtioMbetWeenjthesedessifsfand thd reshits of hamma spectral anhlysesMAny dscisioniconcerhing soil sample analysisiwere based primarilyfon gdmma sspectmljan_alysistafter(taking '~
into adcount th6yossibilityjof pure alpha land/orlbe;ta3mitters! O N0591PUBiSITMMTurLv.Ra%MLNm030 7-19 REVISION 1
FINAL SURVEY FINDINGS Table 7-15 O Comparison of Reactor Yard Final Survey Results to Guideline Values Itighem enlue of Maximum Soil Guidelse Value liighed Value ripnede Soil Guideline Value Concentration from 8 Areas (pCilg) lit, ate from 8 Areas 4R'br) (pCilgt 4R/br) Gamma rwlionuciales 0.57 (Co-137) 1.6 (Cs-137) N/A N/A faposure rete N/A N/A 12.0 17.0 7.3.4 Comparison to Massachusetts Criterion Cesium-137 was the only man-made radionuclide identifiedin the Residual activities in reactor yard soil samples, and its Building 100 and at the concentration was at less than yard acarations wre at three standard deviations above bact: ground 1cvels. Residual background levels... activities in Building 100 and at ,. the yard excavations were at background levels, and a source term could not be identified for the performance of a pathway analysis; therefore, a pathway analysis to O demonstrate that the total annual dose to an individual continuously present would be less than 10 mrem /yr above background was not t necessary. 7.3.5 Building 100 Local Background Considerations The exposure rate measurements in Building 100 were performed after all licensed material had been removed to the extent practicable. Examination of the exposure rate mean values listed in Table 7-5 reveals a striking narrowness of the range of the standard deviations of these mean values. This narrowness suggests that the interior surfaces of Building 100 represent background for the building itself. This is supported by the results of the alpha and beta surveys. Further examination of the exposure rate means calculated for the 27 areas in Building 100 shows that the building can be radiologically classified into three elevations. These three elevations correspond to the basement, operations deck and dome. A comparison of the mean of each elevation, calculated from all the measurements made at that elevation plus 5 pR/hr, was made against the highest mean for each elevation. O mosnrumstrutnmumummo 7-20 REVISION 1
FINAL SURVEY FINDINGS (] \ This comparison is presented in Table 7-16. In each of the three cases, the mean plus 5 pR/hr was greater than the highest mean at each elevation. This finding provides additional evidence that there are no localized areas of elevated exposure rates in the building with respect to local background. Table 7-16 Comparison of Building 100 Local Background to Highest Mean Exposure Rates NI Exposure Rate Local Background - Area ( R/hr) plus SpR/hr Highest mean in basement 15.2 18.8' ; Highest mean from operations deck 11.5 15. l , Highest mean from dome and crane 4.9 9.3'
'Mean value of 16 arc.as in Building 100 basement plus 5 4Uhr.
Nesn value of 9 areas from Building 100 operations deck plus 5 pR/hr.
'Mean value of Building 100 dome and crane plus 5 pR/hr, O
anse.rumsrr.rmamoce no 7-21 REVISION 0 1
a 4 O
8.0 CONCLUSION
O O
7 l l CONCLUSION - l O ' ""s '
- The information presented in this report documents that the U.S. Army has complied with l
l the NRC regulations in 10 CFR 30.36, Erpiration and termination oflicenses, and 10 CFR -l 50.82, Application for tennination oflicense, to terminate the AMTL Research Reactor l l Facility possession-only license, License No. R-65, Amendment No. 9. Specifically, the licensee has performed the decommissioning in accordance with the Decommissioning Plan, the AMTL Response to an NRC Requestfor Additional hfonnation l (reference 9.4.4), and l the following NRC criteria: l
- By-product material was properly disposed;
- A reasonable effort was made to eliminate radioactive contamination; and i
- A final radiation survey was performed which demonstrated that the Research Reactor Facility was suitable for release for unrestricted use.
All radioactive components, scrap and debris removed from the Research Reactor Facility during the decommissioning were transferred to Chem-Nuclear, Inc., through the U.S. Army Armament, Munitions and Chemical Command for disposal at a licensed facility. Mixed waste removed from Building 100 was packaged and is temporarily stored at AMTL awaiting disposition under the jurisdiction of the AMTL Laboratory Facilities license. During the decontamination work, residual contamination levels were reduced below the NRC guideline O values to the extent practicable in order to meet the intent of ALARA. After the decontamination and dismantling activities were completed, Final Status Surveys were carried out in liF3//dlefdirdkIniddrcNiEIh ggceded!5000 Wpin/100 o Tcin2dbeta
"~
tar , the remaining portions of the reactor - --o^- 2r facilities. These surveys included: the ,100. dpgnH0h' in a@'"f 1 remainder of Building 100 in its _ entirety; the excavated areas of the reactor yard; and Building 100 exhaust stack concrete pad. The remaining Building 100 structure and exhaust stack pad exhibited surface radioactive contamination levels significantly less than aVEfike^ahdTihakiinlim'gbidelihiyaluEs jIhTfs0Qhofslihj;1Efdifest nicisiiremest7 exceeded 5000'dpuj/100jm2 ; beta,oQO0idpm/100 cm 2Talphai Removable 2 contamination levds were significantly less than 1000 dpm/10 'crn ijeta andllesithi6L20 2 apni/100l cm lalphi. Exposure rate surveys showed that all areas in Building 100 were less i than 5 pR/hr above background at I meter. The results of all measurements were similar to background. O oserumsnwmwmmxmeso 8-1 REVISION 1
. .. - - . - _- -. . -- - ~. . ,
CONCLUSION i i d$$v v The fmal surveys of the excavated areas of the reactor yard showed that Cs-137 .dRsn&2/illiab?3FFicillifildissis concentrations were oclow background levels plus three standard deviations and jNilNllEd
--w thef rde ' uircineSiM--dc d
Decomnussib'ning[ Plan ;an d met!!he. that exposure rates were below 5 pRlbr _ above background at 1 meter. Cesium. Criteria establishedfor termination of 137 was the only man-made nuclide licenses /fdr/ rhldase[fdM unrestricted identified in the reactor yard soil use, analysis, and its concentration was comparabic to typical fallout values. Since the levels of residual activity did not support identification of a source term, a pathway analysis could not be performed; therefore, the licensee has complied with the Massachusetts acceptance criterion that the dose to an individual continuously present at the reactor site not exceed 10 mrem /yr above background. In view of these findings, it can be concluded that the Research Reactor Facility licensee has fulfilled the requirements of the Decommissioning Plan and has met the criteria established for license termination and release for unrestricted use. : i O i i J b
?
t O omm run .straurtsi in .xxtr urwtr.oso g.2 ItFSISION 1
m, r- a--. m a m. O
9.0 REFERENCES
O 8 O
REFERENCES 9.0 References O 9.1 Standards 9.1.1 American National Standards Institute 3.1, Selection, Training and Quahfication of Personnelfor Nuclear Power Plants. 9.1.2 American National Standards Institute 13.1. Guide to Sampling Airborne Radioactive Materials in Nuclear Facilitics, American National Standards Institute. 9.1.3 American National Standards Institute 13.2. Guide for Administrative Practices in Radiation Monitoring, American National Standards Institute. 9.1.4 American National Standards Institute 13.4. Specification of Portable X-or Gamma Radiation Survey instruments, American National Standards Institute,1977. 9.1.5 American National Standards Institute 15.10-1981, American National Standardfor Decommissioning of Research Reactors.
- 9. '. 6 American National Standards Institute N42.17A-1989, Performance Specifications for Health Physics Instrumentation -
Portable Instrumentation for Use in Normal Environmental Conditions. 9.1.7 American National Standards Institute N323. Radiation Protection Instrumentation Test and Calibration, American National Standards Institute. 9.1.8 American Society for Testing and Materials E 181. Standard General Methods for Detector Calibration and Analysis of Radionuclides, American Society for Testing and Materials,1982. 9.2 Nuclear Regulatory Commission Documents 9.2.1 10 CFR 20, Standardsfor Protection Against Radiation. 9.2.2 10 CFR 30, Rules of General Applicability to Domestic Licensing of Byproduct Material. 9.2.3 10 CFR 50, Domestic Licensing of Production and Utilization Facilities. 9.2.4 NRC, 1981. Monitaring for Compliance with Decommissioning Termination Survey Cri'eria, NUREGICR-2082. O 0223mmmmaxsoio" 9-1 REVISION 0
o REFERENCES 9.2.5 NRC, 1984. Guidance and Discussion of Retjuirements for an \ Application to Tenninate a Non-power Reactor Facility Operating License, September 1984. 9.2.6 Oak Ridge Associated Universities,1992. Manual for Conducting Radiological Sun'eys in Support of License Tennination, NUREG/CR-5849, ORAU-92/C57 (Draft) June 1992. 9.2.7 Regulatory Guide 1.86 1974. Tennination of Operating Licenses for Nuclear Reactors, NRC. , 9.2.8 Regulatory Guide 3.651989. Standard Fonnat and Content of Facility Deconunissioning Plansfor Licensees Under 10 CFR Parts 30, 40, and
- 70. NRC, U.S. Nuclear Regulatory Commission Office of Regulatory Research, Washington, DC.
9.2.9 Regulatory Guide 7.1 1974. Administrative Guidefin Packaging and Transporting Radioactive Materials, NRC. 9.2.10 Regulatory Guide 7.41975. Leakage Tests on Packagesfor Shipment of Radioactive Materials, NRC. 9.2.11 Regulatory Guide 8.61973. Standard Test Proceduresfor Geiger-Muller Counters, NRC. 9.2.12 Regulatory Guide 8.10 1975. Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Reasonably Achievable, U.S. Nuclear Regulatory Commission, Office of Standards Development, . September 1975. 9.2.13 Regulatory Guide 8.21 1979. Health Physics Surveys for By-Product Matenal at NRC-Licensed Processing and Manufacturing Plants, NRC. 9.2.14 Regulatory Guide 8.29 1980. Calibration and Error Limits of Air Sampling Instrwnents for Total Volume of Air Sampled, NRC. 9.2.15 NRC IE Circular 81-07, Control ofRadioactively Contaminated Material, May 14,1981. l l 9.2.16 NRC IE Information Notice No. 85-92, Surveys of Wastes Before i Disposalfrom Nuclear Reactor Facilities. 9.2i1% ' [FEdein(Regisier,[l9.81i lb(sin &allo';Dh:SHQl5}Eki?bf r 7&ridir{or
,Urafing Wastefrom'Past Operatichs,; Volume 46lNo. 205[Octobfr 2}j 1.98.1; mmrursmumuunmuumus 9_2 REVISION 1
REFERENCES 9.3 Decommissioning Reports and Manuals O_ EG&G, 1991. Decommissioning Plan for U.S. Army Materials 9.3.1 Technology Laboratory Research Reactor, EGG-WM-9184, Revision 1, October 1991. 9.3.2 Manson, W.J. and T.S.12Guardia. 1980. Decommissioning Handbook. U.S. Department of Energy, Nuclear Energy Services, Inc. DOE /EV/10128-1. 9.3.3 MK,1992. Project Procedures Manual, Decommissioning, Demolition and Site Restoration of the Research Reactor and Decommissioning ofthe Radiation Facilities at the U.S. AMTL, Watertown, Massachusetts, June 1992. 9.3.4 Stone & Webster,1992. General Contractor Specification for the Decommissioning, Demolition and Site Restoration of the U.S. Army Materials Technology Laboratory Research Reactor, Watertown, Massachusetts, April 1992. 9.3.5 Stone & Webster,1992. Basis of Design / Design Analysis of the Decommissioning, Demolition and Site Restoration of the U.S. Army Materials Technology Laboratory Research Reactor, Watertown, h( Massachusetts, April 1992. 9.3.6 Weston,1992. AMTL Facility Decommissioning Plan (Draft final), April 1992. 9.4 AMTL Documents 9.4.1 MTL,1984. Inventory ofIonizing and Non-ionizing Radiation Sources, June 1984. Located in MTL Health Physics files. 9.4.2 MTL,1987. Army Materials Technology Laboratory Disaster Control Plan, Department of the Army Materials Technology Laboratory, Watertown, MA 1 June 1987. 9.4.3 MTL,1991. Memorandum ofAgreement between U.S. Army Materials Technology Laboratory and the City of Watenown, MA, 25 January 1991. 9.4.4 Letter from AMTL to the NRC, dated March 16, 1992, written in response to an NRC Request for Additional Information, Docket No. 5047, dated February 5,1992. 08 v m239mmumm.ncoso.no 9-3 REVISION 0
REFERENCES o 9.4.5 MTL,1970. Deactivation Report of the AMMRC, December 8,1970. b 9.4.6 AMMRC, Report of Inspection, CO Report No. 47/69-1, U.S. Army Materials and Mechanics Research Center, License No. R-65, Category E, May 8 and 9,1969. 9.5 Army Documents 9.5.1 Army Regulation No. 40-14, Medical Services Control and Recording Procedurefor Erposure to lanizing Radiation and Radioactive Materials. 9.5.2 Army Regulation No. 385-11, lonizing Radiation Protection. 9.6 Reports 9.6.1 EG&G,1988. Preliminary Site Assessment / Site Itupectionfor the U.S. Army Technology Laboratory, EG&G, March 1988. 9.6.2 EG&G, 1990. Characterization Report for the U.S. Army Materials Technology Laboratory Rcsearch Reactor, EGG-WM-8978, June 1990. 9.6.3 EG&G,1992. Demolition and Reclamation Planfor Building 100 at the p U. S. Army Materials Technology Laboratory at Watertown, Q Massachusetts, EGG-WM-9854, January 1992. 9.6 4 TRC Environmental Consultants,1990. Asbestos Building Assessments, Army Material Technology Laboratory. May 1990. 9.6.5 Weston,1991. Phase 1 Remedial Investigation Report, Army Material Technology Laboratory, April 1991. 9.6.6 Weston,1992. Radiological Field Survey Report (Draft), January 1992. 9.6.7 Weston,1992. Phase 2 RemedialInvestigationforBase Closure, AMTL, May 1992. 9.6.8 Currie, 1968. Limits for Qualitative Detection and Quantitative Determination. Analvtical Chemistry, Volume 40, No. 3,586-693. c223n - nwn w - m 94 REVISION 0
REFERENCES 9.7 Technical Basis Documents 9.7.1 AMTL-ADM-D-203, Derivation of the Surface Contamination Limitfor the Free Release ofReactor Building Concrete, Revision 0, October 1992. 9.7.2 AMTL-ADM-D-205, Eramination of Waste Concrete for Absorbed Contamination, Revision 1, November 1992. 9.8 Final Survey Procedures 9.8.1 AMTL-CHM-I-106, Subsurface SoilSampling, Revision 2, October 1992. 9.8.2 AMTL-CHM-1-107, Surface Soil Sampling, Revision 2, October 1992. 9.8.3 AMTL-CHM-I-110, Laboratory Guality Control, Revision 2, December 1992. 9.8.4 AMTL-CHR-I-106, Tennination Surveys ofSite Structures, Revision 2, December 1992. 9.8.5 AMTL-CHR-1-107, Tennination Survey Data Handling and Analysis, Revision 1, October 1992. 9.8.6 AMTL-CHR-1-108, Termination Surveys of the Site Environment, Revision 0, November 1992. 9.8.7 AMTL-INST-A-100, Radiation Protection Instrumentation Program, Revision 1, September 1992. 9.8.8 AMTL-1NST-1-101, Calibration and Test Requirements for Radiation Protection Instrumentation, Revision 1, September 1992. 9.8.9 AMTL-1NST-1-103, Quality Assurance of Counting Systems and Portable Counters, Revision 2, December 1992. 9.8.10 AMTL-INST-1-201, Operation of Ludium Model 2350 Data Logger, Revision 1, September 1992. 9.8.1 l AMTL-INST-1-213, Operation ofReuter-Stokes Pressurized Ion Chamber, Revision 2, September 1992. 9.8.12 AMTL-1NST-1-405, Operation ofTennelec LB-5100 Alpha / Beta Counter, Revision 1, September 1992. O 02239LPUD'$mAMTL\FINAX\010.PJ) 9-5 REVISION 0
REFERENCES 9.8.13 AMTL-INST-l-406, Calibration of Tennelec LB-5100 Alpha / Beta ( ( Counter, Revision 1, September 1992. 9.8.14 AMTL-INST-I-407, Operation ofGenie-PC Gamma Spectroscopy System, Revision 0, September 1992. 9.8.15 AMTL-lNST-1-408, Calibration of Genie - PC Gamma Spectroscopy System, Revision 0, September 1992, 9.8.16 AMTL-INST-1-A ll, Operation of the EG&G Portable Gamma Spectroscopy System, Revision 0, December 1992. 9.8.17 AMTL-INST-1-412, Calibration of the EG&G Portabic Gamma Spectroscopy System, Revision 0, December 1992. 9.8.18 AMTL-OPS-I-103, Sample Chain of Custody, Revision 1, September 1992. 9.8.19 AMTL-OPS-I-207, Survey Documentation and Review, Revision 1, Septebmer 1992, 9.8.20 AMTL-OPS-I-209, Performance of Radiation Surveys, Revision 1, September 1992. 9.8.21 AMTL-RAM-1-102, Radioactive Source Inventory, Leak Testing and Disposal, Revision 1, September 1992. 9.8.22 AMTL-RW-1-204, 10 CFR 61 Characterization and Radioactive MateriauWaste Calculations, Revision 1, September 1992. 9.8.23 AMTL-SASP-A-100, Radiation Protection Self Assessment Program, Revision 1, September 1992. O amurumsnumumuwo" 9-6 REVISION 0
-+
APPENDIX A BUILDING 100 DATA O O
' APPENDIX A F i
d E F APPENDIX A O REACTOR BUILDING DATA
)
?
5 O : mm93-ruseiTsrinixxw21.Ro REVISION 8 ,
APPENDIX A j APPENDIX ~ A > Building 100 Data The data contained in the graphs of this Appendix are presented to facilitate a comparison of the ' final survey results with the applicable guideline values. This appendix is categorized and arranged in six sections as follows:
- Survey area diagrams -
e Direct alpha measurements e Direct beta measurements e Removable alpha measurements e Removable beta measurements
- Gamma measurements at I meter
- i The graphs in each of the last five sections are arranged in a geographic order, starting from the -
basement and working up to the dome of Building 100. When reviewing the data presented in this appendix, a few observations should be noted: . o In the SE quadrant of the basement, a re-occurring pattern of increased gamma measurements is apparent. These elevated. measurement were collected under the stairway. i The structural geometry beneath the stairway is such that several different concrete surfaces' O (underside of stairs, wall and floor) are in close proximity of the 1 meter survey points below the stairway. The elevated instrument responses were attributed to a collective influence of the natural radioactivity in these surfaces. ! e Gamma radiation measurements at Wall 5.of Airlock One appear to be higher than other. readings within the airlock. This due to the fact that the higher measurements were actually collected on Wall 5 outside of the airlock at the Operating Deck of Building 100. These higher measurements are consistent with other measurements collected in that area. Direct Aloha and Beta Survey Graphs 2 Bar graphs are used to present net dpm/100 cm about the zero value on the y-axis. The maximum .l value of the y-axis correlates to the maximum acceptable value for any single reading. The values ! in the graph are net dpm/100 cm2after subtracting background resulting in some negative net values. The lower limit of the graphs correspond to the negative value of the average limit. For the beta direct survey graphs, the maximum limit of 15,000 dpm/100 cm 2, and the average limit of 5000 dpm/100 cm2 are shown. The typical MDA is about 1400 dpm/100 cm 2, which corresponds with the normal range of values about the zero y-axis. For alpha direct survey graphs, the maximum value is 300 dpm/100 cm2 , the average limit is 100 dpm/100 cm2 . The MDA was approximately 50 dpm/100 cm2, l
" " " " " " Page 1 of 163 REVISION #
APPENDIX A A_1pha and Beta Removable Contamination Graohs Graphs of removable contamination measurements are similar to the direct survey graphs, however, because there is no applicable average guideline value, the maximum value of the y-axis is the limiting guideline value for any single measurement. Since many of the measurements were close to zero, the results presented on the beta graphs appear insignificant with respect to the scale of the beta graphs. Gamma Radiation Graphs Gamma radiation graphs are different than the other data graphs in that the maximum and average limits are not absolute radiation levels. The maximum value was selected as 35 R/hr, a value slightly higher than the normal range of naturally occurring radiation at the AMTL facility including Building 100. The y-axis of the gamma graphs is divided into 5pR/hr zones to facilitate identifying areas with radiation fields 5 R/hr above background. The gamma background is not subtracted from the gamma measurements; therefore these graphs do not present negative values (ie. the lowest value on the y-axis is zero). /~T C/ l O O , l mmmwstruwaxwn.no Page 2 of 163 REVISION 0 , 1
APPENDIX A NORTH STAIRWELL - GAMMA MELL NORTHWEST QUADRANT AREA 1 1 NR EAM QUADRANT
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, SOUTH STAIRWELL
/i A[d
',y LEGEND O
f f hE'N!l - STRUCTURES hMICH AP,E NOT PART SUCll OF FLOOR AS WALLS COLUMNS. ETC O^ - INDICATES TRENCHES. DRAINS AND SUMPS NOTE EACH AREA SEPARATED BY OUADRANTS INCLUDES ALL WALL AND CEILING SURFACES. COLUMNS. STRUCTURES AND PENETRATIONS CONTAINEI) WITHIN FILE ORXB1A THE AREA Figure A-1 Reactor Building Basement Floor Plan O
""8'3""#" ' "
Page 3 of 163 REVISION 0
APPENDIX A p i, / A.s/ CowTAINWDff RAM.
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, - ItOICATES PPfNG PDCTRATIONS.
(( - STRUCTURES MSCif ARE PART OP SUCNnDoft AS TAMS. COLUMNS ETC. Figure A-2 Reactor Building Basement Wall Penetrations
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s amanmsmmrmaon.RD Page 4 of 163 REVISION 6 m _ _. ._
I I APPENDIX A l P f a a f g
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+
1 DIAGRAW D1PICTS THE PENETRATIONS ON THE INNER WALLS OF THE BASEMENT. J Figure A-3 i Reactor Building Basement Inner Wall Penetrations , 1 i mm8"""N Page 5 of 163 REVISION 8 i I
APPENDIX A NORTHWEST QUADRANT NORTHEAST QUADRANT AREA 1 - AREA 2
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- H0id20NTAL ACTUAL BASD4ENT SUkf ACF.S CDLING. EXCUJDING IN THE WALLS. AND OVERCOLUMNS. HEAD THAT MAKE - UP pygg' - INDICATES WALLS OR VERTICAL CONCRETE COL 1MNS VfMICH AFI NOT PART Of BASEMD*T CDLING
)
- INDICATES PIP!N" PENETRATIONS.
NOTE-ACTUAL CRDS AN COUNC SURFACES NOT SHovrN ON DIAGRAW SIZE OF GRIDS ON BASEMENT CDLING ARE 3 METE CRIDS. , i Figure A-4 Reactor Building Basement Ceiling s
" " " " "
- Page 6 of 163 REVISION 0
APPENDIX A FLOOR RDJOVED DURtNG (m DEC0kWISS10NING . NORTHWEST QUADRANT , NORTHEAST QUADRANT FLOOR 1 , FLOOR 2
.g,
.L e
AIRLOCK 1 m
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I I _ i & - ----- - --:r CUT OUT HOLES
-------TO BASEMENT- - - -- -- lN FLoch SIZE OF CRlDS '
ON OPERATING DECK FLOOR IS 3 FEET i 8 O l N :. s
=
FLOOR 4 ' SOUTHWEST QUADRANT : FLOOR 3 SOUTHEAST QUADRANT EQUIPMENT HATCH EQUIPMENT HATCH BUILDING L STAIRWELL #2 P AIRLOCK 2 J f.b Figure A-5 Reactor Building Operating Deck
"""""""D Page 7 of 163 REVISION 0
1 1 l 1
~ APPENDIX A l i
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' BUILDING 97 L
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- 3 7 HERE AND _E END AT AIRLDCK I E e
7-/ e LEGEND
+ INDICATES ELECTRICAL PDETRATIONS h -INDICATES PIPING PENETRA110NS Figure A-6 Reactor Building Operating Deck Wall Penetrations i
i
" " " " " * " 8*" Page 8 of 163 REVISION 8 I
APPENDIX A r's v: sa artn h j 7_ .m D.w_1 atwntO OF SECOND MTf0RWd *
, APWK I ftp 5 REmMLO OF FIRST PLATTORW %
1- - - B AW, ) f WLMS y Inau n, i por am. I
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mwm rmAn. . / N o,m If_ LEGEND NOTES 1 PATTERNS SHO*N ON CONTAINMENT m ALL DEPICTS ACTUAL DESIGN AND GRID LAYOUT USED FOR SURVEYlNG CONTAINMENT WALLS 2 GRIDS ON BASEMENT WALL ARE 3 f 00T GRIDS 3 FIRST TMO ROWS OF GRIDS ON CONTAINMENT WALL ( 6 FEET UP FROM OPERATING DECK FLOOR) AP.E 3 FOOT GRIDS ABOVE FIRST TWO ROWS OF CRIDS ARE 3 METERS X 3 METERS rni an m l
)
l Figure A-7 l Cross Section View of Reactor Building ( ( oxs95runsmmmoim Page 9 of 163 REVISION 8 1 a
APPENDIX A
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i w HORIZONTAL . GRANE RAll Figure A-B Reactor Building Dome ' O
" " "*""" Page 10 of 163 REVISION 9
APPENDIX A F N WOOLEY AVDfJE
.g/ --
m un { LEGEND ___
" N B5"E^T T 2 i me a exuum orn
& TREES IN REACTOR
.- - TARD vmt rENCE AREA 0 k D i
-((lhfgdf llt WOUND OF DIRT '
E_l _ ,, , . . mum ., EXCAVATED TRENCH
' _II lllE IE g! !b AREA 1 amsun
,INE
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I .o ,a r. BUtth!NG sT m 1 g REACTOR @ BUILDINO 100
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NORTH BEACON STREET AREA MAP OF REACTOR YARD - '
,.2mm ,_ SHOWING EXCAVATED TRENCHES AND DIRT PILES
""* Entre A 4 em Reactor Yard
""8"*" N Page 11 of 163 REVISION 9
APPENDIX A O aidg 100, Basement, NW Quad. Floor Direct Alpha Survey N.XX] AbhaCbm/ 200 a g 100 m E O se a.Jbu.I.d _a.h. uwwdmak,)Wu --
-100 p u.... "...,3.u.u......3....u.u"...r""~'r"'~~~"r"'""""r""'"'"1' OO10000F01 OO10000F01 OO10000F01 OO10000F01 OO10000F01 0010000F01 OO10000F01 OO10000F01 Stney Meca.rement Loccitn Cochs O 3/24/93 Alpha Radiation Measurement Statistical Summary for 9:56 am Bldg 100, Basement, NW Quad. Floor dpm/100 sq. cm.
95% Confidence Level Upper Bound on Mean Maximum N Radiation Mean Alpha 11 13 40 135 File Name for this graph: RBNWFA .EPS Figure A-10 Direct Alpha Survey Results of Basement NW Quadrant Floor l
""*"""" ## Page 12 of 163 REVISION 6 i
APPENDIX A O Bidg 100, Basement, NE Quad. Floor Direct Alpha Survey 2w wxara Abha cbm/ 200 N sr 8 'N q O a...i.l.d.NlleEh - - J .n.
. MldNL.1 b.ui..a.
-100 gu u".nio.o.r oonn u.i oso..oooio.opnio"u o u ro""i n u n"inino" o o ruinnoi o."r""
0020000F01 0020000F01 0020000F01 00z000701 0020000F01 0020000F01 0020000F01 0020000F01 Suney Mecnsement Lrcot~m Codes O 3/24/93 9:52 am Alpha Radiation Measurement Statistical Summary for Bldg 100, Basement, NE Quad. Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 11 12 45 125 File Name for this graph: RBNEFA .EPS Figure A-11 Direct Alpha Survey Results of Basement NE Quadrant Floor O V
""" """"" Page 13 of 163 REVISION 9
t r APPENDIX A F O Bldg 100, Basement, SW Quad. Floor Direct Alpha Survey xo _ . Abha dpm/ 200 b sr g 100 E I O d. lain.d.a!an.edAIEdL.t8 . } l 1-u.L. .ul 1
-100 r u o m . * *r " '"~' ~~ r ' == '"-"r"'""" "-" 'i= ' ="'=mr "'" " " ~ r""'~'"'""' r ;
OO40000F01 OO40000F01 OO40000F01 OO40000F01 OO40000F01 OO40000F01 OO40000F01 DO40000F01 ] Surey Mecn.rmwnt Lccatbn Cochs l O 3/24/93 Alpha Radiation Measurement Statistical Summary l 9:59 am for l Bldg 100, Basement, SW Quad. Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 10 12 53 135 File Name for this graph: RBSWFA .EPS Figure A-12 Direct Alpha Survey Results of Basement SW Quadrant Floor j
****""**"" Page 14 of 163 REVISION 8 1
l
,-,c . . - , . . -- ..
t APPENDIX A l Bldg 100, Basement, SE Quad. Floor j 1 Direct Alpha Survey 3 - , Abha dpm/ i 200 i st : g 100
...,_ slh, .ti,t,), isE.b.da.k.i.!.e.L.u i O 6.R J .. . h a . .E.
?
" 4345 E 465 BBIg5 8 l144 EIllia dia 886IIg 33I333 Il 685 318IIJ gasIII45515154 466 tj4 di 571 Ill his ils Ig4 la Ill III5313 3 3 53 g Ill 588 L.5 33 Ele 14s gliil OO3000CF01 0030000F01 0030000F01 MMO1 ' i 0030000F01 0030000F01 0030000F01 OO30000F01.
Suney Measuremmt Locatbn Co&s ; 3/24/93 Alpha Radiation Measurement Statistical Summary 9:57 am for ; Bldg 100, Basement, SE Quad. Floor i dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean -Maximum N i Alpha 6 8 52 129 File Name for this. graph: RBSEFA .EPS , f i Figure A-13 Direct Alpha Survey Results of Basement SE Quadrant Floor t
" " " " " " " ' " Page 15 of 163 REVISION 8 j i
i APPENDIX A O Bldg 100, Basement, Gamma Well + Direct Alpha Survey w wm Abha cim/ 200 a g 100 m h 2 0 =3% d b "8 C% "Bko " d " "a a%=B2_ _i m .......,,... 1. ..................................... ooecoooFoi ooCOoooWo2 co60000Wo2 ooGooooWo2 ooooooowo1 ooooooowo2 cocoooowo2 Surwy Mecrmment Locaton Ccxhs O 3/24/93 Alpha Radiation Measurement Statistical Summary 9:51 am for Bldg 100, Basement, Gamma Well , dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 5 8 43 54 File Name for this graph: RBGWOA .EPS Figure A-14 Direct Alpha Survey Results of Basement Gamma Well O mcenrwsmrm xwn.a Page 16 of 163 REVISION 8
APPENDIX A O Bldg 100, Basement, sump Direct Alpha Survey 3x wm Aphacbm/ 200 a g 100 5 4 o =%rf==u%as-ga%=strD3H"H353;f38535333
-100 i,....i....,,,,...i,,,,.i,,,.,i.....i...
30000s 1 30000S 1 Suney Memurement Locatbn Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary for 10:02 am Bldg 100, Basement, Sump dpm/100 sq. cm. 95% Confidence Level Upper Bound on Mean Maximum N Radiation Mean
-10 -8 13 40 Alpha 9
File Name for this graph: RBSU0A .EPS Figure A-15 Direct Alpha Survey Results of Basement Sump
""""""* Page 17 of 163 REVISION 9
APPENDIX A dr- Bldg 100, Basement, Drains Direct Alpha Survey w wan Abho cbm/ 200 a g 100 m E - 0 hR o _ u g uu - ___nQilbb%L m - - gy a _$_M yu uu nu B uu O_ b A--
-100 p u n i o p o o n i i i p u u n i o p i n o i n i p u i i n i o i n o n n o s i n n u i i 0050000DAO 00500000B0 0050000DHD 0010000001 0050000DAO 0050000DF0 0050000DHD Surwy Measurement Locat'en Cots O 3/24/93 Alpha Radiation Measurement Statistical Summary for 9:55 am Bldg 100, Basement, Drains dpm/100 sq. cm.
l 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 5 8 47 76 File Name for this graph: RB00DA .EPS Figure A-16 Direct Alpha Survey Results of Basement Drains
"""'3"""'" Page 18 of 163 REVISION 8
APPENDIX A O Biag 100, Basement, Trenches Direct Alpha Survey 3m - Abha dpm/ 200 b sr g 100 R o _ l'Y1 _ _ _n Q B b 0 R9 9 m8 of _u $o_a Q 0 a y wo - -- u - p u u ma
-100 iiiiii>>>iiiiiiiiig>>>iiiiii>>>>iiiiiiiiiiiiigisisiiiiiiii>>i OO500000A0 OrF W AO OOTOOOOFO OO500nOOHO OC500000A0 00500000C0 N HO Surwy Memurement Locatin Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:02 am for Bldg 100, Basement, Trenches dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N j Alpha 5 8 47 61 File Name for this graph: RBTROA .EPS l Figure A-17 i Direct Alpha Survey Results of Basement Trenches O
" " " " " " Page 19 of 163 REVISION 9 l
APPENDIX A O Bldg 100, Basement, structures Direct Alpha Survey 3w w,can Abbo dpm/ 200 N a g 100
-s 0 -WW *
- ss8-
" " " " " * " ~ " "
-100 i ..i..i .i. i..i.
0020000SO 0010000 0010000S10 Suney Memumment Locat'en Codes 3/24/93 Alpha Radiation Measurement Statistical Summary 9:53 am for Bldg 100, Basement, Structures dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 4 8 26 17 File Name for this graph: RB00SA .EPS Figure A-18 Direct Alpha Survey Results of Basement Structures q
" ' * " " " " '8 " Page 20 of 163 REVISION 8
e b APPENDIX A O Bldg 100, Basement, NW Quad. Wall Direct Alpha Survey . KKKXX)G l Abha @m/ ; - 200 sr g 100 0 ri- r
'I'-
I ' - 0 3- a i -Y
-100, , , ,- , , , , ,
0 0000 1 00 0000 0000b 00COWO3 Stney Meerstment Locatbn Cces i 3/24/s3 Alpha Radiation Measurement Statistical Summary 9:56 am for Bldg 100, Basement, NW Quad. Wall , dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum- N Alpha 9 10 56 190 File Name for this graph: RBNWWA .EPS i Figure A-19 j Direct Alpha Survey Results of Basement NW Quadrant Wall
" ' * "'# " " * '8 "
Page 21 of 163 REVISION 8 i
----- .m ,. . , . - . -, _
APPENDIX A O Bldg 100, Basement, NE Quad. Wall Direct Alpha Survey 3* Abha dpm/ T 200 j b a ; g 100 m 1,1l .I l u t h *I" '
.! --L EN i t! I I I bmir 0 ai > - .1.m- - a i 3-
-100 ;---- , - - - - ,- ruewress - , 7.-- , -3s C$ 00 u0uGW 01 Surwy Memuremmt Locatin Codes 3/24/93 Alpha' Radiation Measurement Statistical Summary 9:54 am for l Bldg 100, Basement, NE Quad. Wall dpm/100 sq. cm. ;
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 9 11 59 236 File Name for this graph: RBNEWA .EPS l l
-l I
Figure A-20 Direct Alpha Survey Results of Basement NE Quadrant Wall
" " * " " * " " Page 22 of 163 REVISION 6 l
i
APPENDIX A \ iQ lV Bldg 100, Basement, SW Quad. Wall Direct Alpha Survey 1' KXXXXX] Abha ctm/ l 200 a 8 100 l {
;IJ-r iL,L,L.rr sili llal ASki.uu ti ill v laldiLil -- - i 0 - -
-100 7 , , , , , , ,
Co40000wo1 0040000wo) 0040000wo1 0040000wo4 0040000wo1 0040000w01 0040000wo2 0040000woS Suney Memurement Leccitn Ccdes f O 3/24/93 Alpha Radiation Measurement Statistical Summary : 9:59 am for Bldg 100, Basement, SW Quad. Wall ' dpm/100 sq. cm. 1 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 11 13 62 192 File Name for this graph: RBSWWA .EPS Figure A-21 Direct Alpha Survey Results of Basement SW Quadrant Wall O
" " " * " " " " Page 23 of 163 REVISION 8 t
(
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APPENDIX A O Bldg 100, Basement, SE Quad. Wall Direct Alpha Survey 3" - Abha dpm/ 200 j g g g 100 m dhli[I I H .u Ju.. lhk.uld b -- 0 M ..llii.u.hD.I
.. li ] unb.lilu
-100 c-- __., -, , - - - - 7 -. , , r
$h]000W 00 0 $bo9 Suney Measurement Locafm Cochs O 3/24/93 Alpha Radiation Measurement Statistical Summary 9:58 am for Bldg 100, Basement, SE Quad. Wall dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 13 14 93 263 File Name for this graph: RBSEWA .EPS l 1 Figure A-22 Direct Alpha Survey Results of Basement SE Quadrant Wall
" " " "
- Page 24 of 163 REVISION 8. ,
APPENDIX A 1 O Bldg 100, Basement, Ceiling Direct Alpha Survey
- 300 Abha dpm/
i 200 . 6 ! a - g 100 n3 ir - b irgrun 0 g y b _y-O -_ g _"U 0_ ENk
-100 p , . . . . . . . . . . . . . . . . p , . . . . . . . i . . . . . . . . p . . . . . . . p , . . . . . . . ptrrrr 0010000CD trmd3 -
Suney Memurement Location Codes O 3/24/93 Alpha Radiation Measurement Statistical' Summary ' 9:51 am for Bldg 100, Basement, Ceiling dpm/100 sq. cm. 95% Confidence Level Radiation .Mean Upper Bound on Mean Maximum N : Alpha 11 15 44 67 File Name for this graph: RB00CA .EPS i Figure A-23 i Direct Alpha Survey Results of Basement Ceiling O
" *" "**"" Page 25 of 163 REVISION 8
. - , - -., , - - - . - + > . . , , ~ , .--,,- -,-.,,n. .-,,-e , , - 4 -,~ -
, APPENDIX A O Bldg 100, Operating Deck, NW Floor Direct Alpha Survey 3m -
Abha dpm/ 200 N g g 100 0 m--a L JJ dunl.1h - n_. .NAa.Jul4112=.Ub a s - - -
-100 . . i. . . . " . . . . " "i p i n i > > ii " . p o i ii i . "i r ' ' """ " 'p i i"' '" " u r i " """ r i h1100 $1100N $11000F 11000F01 Suney Memtnrnent incotion Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary for 10:07 am Bldg 100, Operating Deck, NW Floor dpm/100 sq. cm.
95% Confidence Level Upper Bound on Mean Maxlmum. N Radiation Mean 12 14 42 101 Alpha File Name for this graph: ROF1FA .EPS Figure A-24 Direct Alpha Survey Results of Operating Deck NW Quadrant Floor O
" " "" Page 26 of 163 REVISION 0 1
APPENDIX A O' Bldg 100, Operating Deck, .NE Floor-Direct Alpha Survey i KXXXXX] Athe cbm/ 200 i b a g 100 1 I " 0 5 ,'p m" isis,g r y",. ,'s"',,y peq'gif i s"s
-100.............,,,.......................,i.............i.........................i.....u,,,,,.i..
0011000F02 0011000F02 0011000F02 0011000F02 0011000F02 0011000F02 0011000F02 0011000F02 Suney Memumment Locatbn Codes 3/24/93 Alpha Radiation Measurement Statistical Summary 10:08 am for Bldg 100, Operating Deck, NE Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum _N Alpha -5 -3 32 101 ! File Name for this graph: ROF2FA .EPS ' l 1 Figure A-25 Direct Alpha Survey Results of Operating Deck NE Quadrant Floor
-1 ""* """"" Page 27 of 163 REVISION 8 l
- APPENDIX A O Bldg 100, Operating Deck, SW Floor Direct Alpha Survey t
t XXXXXX] Abha chm / 1 200 a g 100 k.d EA. .It I R E 84 In am . 9.1 .J O . .. .
-100 i nn.onnn. inn.n o.n nponon.nni n n noon.co nonnn.pn u.n nn nin no.n n n.p OO11000F04 OO11000F04 OO11000FCL OO11000F04 OO11000FO4 OO11000FO4 OO11000F04 OO11000F04 Suney Mecnnment Lccaron Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:09 am for Bldg 100, Operating Deck, SW Floor dpm/100 sq..cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 10 12 47 107 File Name for this graph: ROF4FA .EPS Figure A-26 Direct Alpha Survey Results of Operating Deck SW Quadrant Floor O m e s m e n n.u Page 28 of 163 REVISION 8
APPENDIX A (~
' Bldg 100, Operating Deck, SE Floor Direct Alpha Survey 3m _
Abha @m/ 200 a g 100 t O N ".b I '." I . Ar d o". " ' I " '." ' .# "P l E.' '
-100 p .n ., n n. ,po n n n n.p. .. n. n n . p n n .n. n p n. n u. n . p. n n .u n n p <,o n n u p in OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000FO3 0011000F03 OO11000F03 Suncy Mcatnyvet Location Co&s O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:08 am for Bldg 100, Operating Deck, SE Floor dpm/100 sq. cm.
95% Confidence. Level Radiation Mean Upper Bound on Mean Maximum N Alpha 3 4 29 103 File Name for this graph: ROF3FA .EPS Figure A-27 Direct Alpha Survey Results of Operating Deck SE Quadrant Floor O
""" ""*"" Page 29 of 163 REVISION 8
APPENDIX A , O Bldg 100, Basement, Stairwell One Direct Alpha Survey : 3" - 1 Alpha @m/ 200 a g 100 s 0 ' r'M "- - l
--100,,,,,,,,,,,,,,,,,,,,,,,,,,,..........................,,,,,,,,,,,3,,,,,,,,,
0070SW1C01 0070SW1F01 0070SW1WO1 0070SW1WO4 0070SW1F01 OO70SW1WO1 0070SW1WO1 Suney Memurement Locot'm Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:00 am for Bldg 100, Basement, Stairwell One j dpm/100 sq. cm. ~ 95% Confidence Level .j Radiation Mean Upper Bound on Mean Maximum N Alpha 17 20 63 77 l 1 i File Name for this graph: RBSOOA .EPS
.)
Figure A-28 Direct Alpha Survey Results of Stairwell One 1 l
" " * " " " Page 30 of 163 REVISION 9 i
i l
APPENDIX A O Bldg 100, Basement, Stairwell Two Direct Alpha Survey - 35 - Abha dpm/ 200 sr g 100 m 0 hJ i = l l "8 Jdb "u ,JL E EJd -
-100r"""'''''r'"'""i'"'"'*'i""i" 'r'"'"'r"'"t
0070SW2F01 0070SW2WD1 0070SW2WO3 0070SW1WO3 0070SW2F01 0070SW2WD1 0070SW2WO3 0070SW1WO3 Suney Measurement Locatbn Cedes O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:01 am for Bldg 100, Basement, Stairwell Two dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 20 22 56 139 i File Name for this graph: RBST0A .EPS ; l l l l l Figure A-29 Direct Alpha Survey Results of Stairwell Two O
" " " " " * " " " Page 31 of 163 REVISION 6 l
APPENDIX A Q' Bldg 100, Operating Deck, Airlock 1 Direct Alpha Survey . 3* -m Abha ctm/ 200 sr g 100 m om bs--ll .n...!Ih I _1 RI Al b .nAll . . . 0 - s--u-- ag-- g as-
-100 . ....m i o. u o i ... u o o.uici o . ..u o..p o. o o o u ..iu o o .o o.o p o. ." o o oio ..o o o. o p 0021AL1CD1 0021AL1F01 0021AL1WO1 0021 AL1WO4 0021AL1C01 OO21AL1F01 0021AL1WO3 0021AL1WOS Surwy Meaxroment Lecot'o n Ccxts O
V 3/24/93 Alpha Radiation Measurement Statistical Summary 10:05 am for Bldg 100, Operating Deck, Airlock i dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 7 9 57 107 File Name for this graph: ROAOOA .EPS Figure A-30 Direct Alpha Survey Results of Airlock One fO
" *'"" " * " " " Page 32 of 163 REVISION 9
~ . .. _ _ . . _ __._. _ . . _ _
i APPENDIX A : t i O Bldg 100, Operating Deck, Airlock 2 - i Direct Alpha Survey !
.- 300 ,
Abhacbm/ . 200 ; sr . g 100 m A .. L, . Alm AL tlL LILa 0 - --
-- a a -- - a -
-100 o . oi . . . o . . i . . o . o o u. i . , n o . o " i . . . . . . . . . o .i u . o . . . . o . i . o . . . . . . . . . o o u o o i . . o u .;
0021AU2C01 0021AL2F01 OO21AL2WO1 0021AL2WO4 0021AL2CD1 0021AL2F01 0021 AL2WO3 0021AL2WO5 Suney Mecnnrnent Locatbn Codes , t O 3/24/93 Alpha Radiation Measurement Statistical Summary i 10:05 am for Bldg 100, Operating Deck, Airlock 2 dpm/100 sq. cm. , 95% Confidence Level : Radiation Mean Upper Bound on Mean Maximum N Alpha 10 12 52 98 4 File Name for this graph: ROATOA .EPS t i 1 l
'l l
Figure A-31 ' Direct Alpha Survey Results of Airlock Two O , l 1
" * * " " " " Page 33 of 163 REVISION e j l
i
APPENDIX A - O Bldg 100, Equipment Hatch Direct Alpha Survey 300 KXXXXX] Abhocbm/ 200 e g 100 1 0
--n-
""~
u u-- " " n"u- - u - - - u--
- - u"
-100 i ...u i . .....i ... u.i........i. .. . .i,o....ii. . ...
0021EH1C01 0021EH1F01 0021EH1WO3 ' 0021EH1WOS 0021EH1F01 - 0021EH1WO2 0021EH1WO4 Surwy Memtrernent LocxfJon Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary i i 10:06 am for Bldg 100, Equipment Hatch .. dpm/100 sq. cm. 95% Confidence Level ' Radiation Mean - Upper Bound on Mean Maximum' N Alpha 4 7 46 63 j File Name for this graph: ROEHOA .EPS l i 1 Figure A . Direct Alpha Survey Results of Equipment Hatch O > axm93-runwnencaonois.no Page 34 of 163 REVISION 8 ; i
APPENDIX A O Bldg 100, Operating Deck Wall to 2M Direct Alpha Survey
' XXX)OOG Atte cbm/
200 a g 100 m . l* j I W g 0 - i - -
-100 r - - - i -' r 'i -'i i 'r-0011000WO1 0011000WD1 0011000WD1 0011000WO1 0011000WO1 0011000WO1 0011000WO1 0011000WD1 Stney Manrement Locatbn Codes O 3/24/93 Alpha-Radiation Measurement Statistical Summary 10:11 am for Bldg 100, Operating Deck Wall to 2M !
dpm/100 sq. cm. , 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 20 22 64 150 File Name for this graph: RO2MWA .EPS l 4 Figure A-33 i Direct Alpha Survey Results of Operating Deck Wall to 2 Meters l
"*5" ****"" Page 35 of 163 REVISION 8 l
APPENDIX A n U Bldg 100, Operating Deck, Wall > 2M Direct Alpha Survey KXXXXX] Abho ctm/ 200 b a g 100 R , i O pa N E %J , a B L. N 8 h h,i G up - -
-100 i n n u . . . . iu . . n i n i n i . i n . i i n i . i nin in . . . . . iiiii n o . . sii . i n ii n ii n 0011000Wo1 OO1100CWO1 0011000WO1 001100CyWD1 0011000W01 0011000WO1 0011000V01 0011000WO1 Survey Memunerrmt Locatm Ccas O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:12 am for Bldg 100, Operating Deck, Wall > 2M dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 24 28 76 81 File Name for this graph: ROA2WA .EPS 9 1 Figure A-34 f Direct Alpha Survey Results of Operating Deck Wall > 2 Meters ,
""*""*"" Page 36 of 163 REVISION 9
o -g n m m :: .4,.La aa" 2 e,4,du ~M APPENDIX A i O Bldg 100, Remains of Platforms 1&2 Direct Alpha Survey : KXXXXX] ; Abha dpm/
]
200 l g ! sr 8 1T ; l g 0 - - 8 8 8 "" 8 O-l
-100 i . . . . .
i . . , ,, ,,..i. 0011000 FOS OO11000FO5 OO11000F06 OO11000F06 , 0011000F05 0011000F05 0011000F06 Suney Meauwnent LocdJrn Codes , O 3/24/93 Alpha Radiation Measurement Statistical Summary l 10:10 am for i Bldg 100, Remains of Platforms-1&2 : dpm/100 sq. cm. 95% Confidence Level i Radiation Mean Upper Bound on Mean Maximum N { Alpha 24 30 59 20 i File Name for this graph: RO56FA .EPS t Figure A-35 Direct Alpha Survey Results of Remains of Platforms 1 and 2 O , o
"""*""*"8" Page 37 of 163 REVISION 8
APPENDIX A. i o Bldg.100, Crane i Direct Alpha Survey j F 300 Abha ctm/ l b i a : 8 100 ; o L a LG e,., ,_2h3h_!asas d.. 4 I
-100 i......i.. ...i., ...;.... ii. . . i......i...
0012000501 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 .i Sure/ Mazuremmt Locat'm Codes t O 3/24/93 Alpha Radiation Measurement Statistical Summary , 10:04 am 'for , Bldg 100, Crane i n dpm/100 sq. cm. . 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 21 26 65 46 File Name for this graph: RDCROA .EPS Figure A-36 Direct Alpha Survey Results of Crane O mn - reamus Page 38 of 163 REVISION 6
APPENDIX A I f Bldg 100, Containment Dome Direct Alpha Survey
]
3* oxom : Abha dpm/. 200 b sr 8 1% . q
,I J .t Ill.11..I,Ill_. .. . '
i l masi.h a [L 0 '. up l g p g rjs g p i = -= -
-100 r --- ' '*i- --- - r - - - - 1'- - -- 4 -' - --- '= s' -- - : ' -, ;
0012000CD1 0012000C01 0012000C01 0012000C01 0012000CA1 0012000C01 0012000CD1 0012000CB1 Surwy Memunement Locatbn Codes l O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:03 am for Bldg 100, Containment Dome dpm/100 sq. cm. ; 1 95% Confidence Level j Radiation Mean Upper Bound on Mean Maximum N j i Alpha 9 12 89 170 File Name for this graph: RDCDOA .EPS Figure A-37 Direct Alpha Survey Results of Containment Dome j O . unenw m"" Page 39 of 163 REVISION 8 m
- w e w -lw -
-ww
APPENDIX A j O Bldg 100, Yard, Exhaust Stack Pad Direct Alpha Survey KKKKK)G A _ bho ctm/ 200 sr g 100 1 0 " "' Aaro% - - -, emsso" mu .o:na ro mon:mosa =
-100 i... .. i.... . .i.1 , .. .. ... i..... ..ii.. .i. iii...
0010P01F01 0010P01F01 0010P01WD1 0010P01WO4 0010P01F01 0010P01F01 0010P01WO2 Suney Measurement Locatbn Ccdes O 3/24/93 Alpha Radiation Measurement Statistical Summary 10:18 am for Bldg 100, Yard, Exhaust Stack Pad dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha -6 -5 10 60 File Name for this graph: RYSPOA .EPS l Figure A-38 Direct Alpha Survey Results of Exhaust Stack Pad 0* NB'"*"" " Page 40 of 163 REVISION 0
APPENDIX A O Bldg 100, Basement, NW Quad. Floor Direct Beta Survey 15 w00cm2 10 N g9 5 53 ILuniLLLtt,sia d kt me,hl ann ..dum. ,Lti 12d, O i m- ,-i-- i
, .hl.Li A.m,
-5, , , , , ,
0010000F01 OO10000F01 OO10000F01 OO1000CF01 OO10000F01 0010000F01 0010000FO1 OO10000F01 Stney Mestnment LocdJon Ccdes
;O Beta Radiation Statistical Summary 3/24/93 8:42 am for Bldg 100, Basement, IN Quad. Floor dpm/100 sq. cm. ,
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 316 340 1729 675 i File Name for this graph: RBINFB .EPS Figure A-39 Direct Beta Survey Results of Basement NW Quadrant Floor O exanrummrwuon." Page 41 of 163 REVISION 8 ,
APPENDIX A s Bldg 100, Basement, NE Quad. Floor Direct Beta Survey 15 Opm/100cm2 10 b sr8 8' 5 t .Aldlmidbljdhle1*
- L.um, ia .n mtt .116.La h uhuntNd O r . - r- or v-- v . . .-
-5 , , , , , , ,
002000CF01 00200uCF01 0020uuCF01 uuzuuuur 01 Ou2OuuuF01 0020000F01 Ou20000F01 0020000F01 Suney Memurement Locatbn Cocks 3/24/93 Beta Radiation Statistical Summary 8:38 am for i Bldg 100, Basement, NE Quad. Floor dpm/100 sq. cm. , 95% Confidence Level ' Radiation Mean Upper Bound on Mean Maximum N Beta 295 320 1771 630 4 File Name for this graph: RBNEFB .EPS i l Figure A-40 l Direct Beta Survey Results of Basement NE Quadrant Floor l l l 1
" " * " " " " Page 42 of 163 REVISION 9 l
.. I
APPENDIX A , O Bldg 100, Basement, SW Quad. Floor Direct Beta Survey
- 15 ,
Dpm/100cm2 10 N 9 8 5 t a rialtlha,dt!).dt.wilddllM1LAdaldt}IJ1LIkSLJ O rrr , s u ,r .c r w r -, , r, - r--
-5, , , , , ,
b Suney Memurement Lomibn Co&s 01 3/24/93 Beta Radiation Statistical Summary 8:46 am for Bldg 100, Basement, SW Quad. Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N , Beta 296 324 1747 675 File Name for this graph: RBSWFB .EPS Figure A-41 Direct Beta Survey Results of Basement SW Quadrant Floor
""""*""2" Page 43 of 163 REVISION 9
APPENDIX A Bldg 100, Basement, SE Quad. Floor Direct Beta Survey . 15 ; Dpm/100cm2 10 N 8 5
# d, b l .h tu k hiltl ei m't lddW J ] An tilail O e. ,. i -
ii ggQ
-5 , , , , , ,
O 3OOOOF 1 N M rT 3OOOOF01 Suney Mecruwrunt Locatin Cochs t O 3/24/93 Beta Radiation Statistical Summary 8:44 am for Bldg 100, Basement, SE Quad. Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N l Beta , 517 544 1802 651 File Name for this graph: RBSEFB .EPS Figure A-42 Direct Beta Survey Results of Basement SE Quadrant Floor O i omnunnwemim Page 44 of 163 REVISION 8 l 7
i APPENDIX A , O' Bldg 100, Basement, Gamma Well ; 1 Direct Beta Survey 15 Dpm/100cm2 f 10 - b o ' ,^iI" " '? L = gy i._ h u p _lg p 2 77 J 7 9 u.9; ya ip i
-5, , , ,-- ,-- ,- , ,
0060000W 00w000W 0060000WO1 easwy Meamsument Locat'm Co&s O 3/24/93 Beta Radiation Statistical Summary 8:35 am for Bldg 100, Basement, Gamma Well dpm/100 sq. cm. 95% Confidence Level - Radiation Mean Upper Bound on Mean Maximum N Beta 229 265 1255 270 F File Name for this graph: RBGWOB .EPS 1 Figure A-43 Direct Beta Survey Results of Basement Gamma Well
""""2"" Page 45 of 163 REVISION 8
APPENDIX A r Bldg 100, Basement, Sump Direct Beta Survey 15 [ Dpm/1CXkm2 10
.g f "i
g 5 t '#)'4's - I
"' ^
0 .'" 4' r - -
-5, , , , , , , ,
N 01 0$30000S01 h30000S01 N1 Suncy Memurement Lordicn Codes O 3/24/93 Beta Radiation Statistical Summary 8:50 am for Bldg 100, Basement, Sump dpm/100 sq. cm. _ 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N > Beta 399 448 1368 200 File Name for this graph: RBSUOB .EPS Figure A-44 Direct Beta Survey Results of Basement Sump i
" " " " * " " Page 46 of 163 REVISION 9 ,
APPENDIX A j l O' Bldg 100, Basement, Drains l Direct Beta Survey i l i l 15 Dpm/100cn2 1 10 b sr! i gZ 5 I o uaLk M dhial b ULil,& W e,JJuhiditbtb r .. 2e.ul..la..U w
-5 , , , , , , ,
rnymnnnAO OrmmnAO OCFA000DHD ND nncmnnnAO 0050000000 N 0010000D01 : Suney Memurement Locat'on Codes O 3/24/93 Beta Radiation Statistical Summary 8:41 am for Bldg 100, Basement, Drains l l dpm/100 sq. cm. -l l 95% Confidence Level l Radiation Mean Upper Bound on Mean Maximum N l Beta 424 459 1650 355 i I File Name for this graph: RB00DB .EPS I j l Figure A-45 l Direct Beta Survey Results of Basement Drains l O . ammurmsmm Page 47 of 163 REVISION 8 ;
APPENDIX A O Bldg 100, Basement, Trenches ; Direct Beta Survey .- 15 Dom /100cm2 10 g$ 5 ' t t II A1. k M,talhi M 4.iJLr.l.,1 il dh!JaifJJiuhId.]d1tb .2ie ,uj D ,, , l I
-5, , , , , ,.
O Suney Memunement Locatbn Codes O 3/24/93 Beta Radiation Statistical Summary i 8:51 am for , Bldg 100, Basement, Trenches { l dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N , Beta 444 481 1650 310 t File Name for this graph: RBTROB .EPS i I J l Figure A-46 l Direct Beta Survey Results of Basement Trenches
.i
" " " " " " " * " Page 48 of 163 REVISION 6 j
APPENDIX A O Bldg 100, Basement, Structures ' Direct Beta Survey. 15 Dpm/100cm2 10 sr! 81 5 t Ji IE 1l_lll] l i Id l bd -t idNI.Ld. a. kill O ri i i -- i i o g y i gi l [iggagg gg ij g- j j si pg
--5 , ,- , , , , ,- ,
10000b 0000b h10000S 10000S15 Surwy Memurement Locatbn Codes O 3/24/93 Beta Radiation Statistical Summary 8:40 am for Bldg 100, Basement, Structures dpm/100 sq. cm. 95% Confidence Level ) Radiation Mean Upper Bound on Mean Maximum N Beta 522 632 3590 239 i File Name for this graph: RB00SB .EPS 1 Figure A-47 Direct Beta Survey Results of Basement Structures m ar e rn m u on.no Page 49 of 163 REVISION 8
APPENDIX A O Bldg 100, Basement, NW Quad. Wall Direct Beta Survey
. 15 Dpm/100cm2 -
10 b ' g-3 0 kudLabia.J1l.r
.- y v. v .2 LR&1Lu.om.d a
. . , , , La d vu l,r ,o a
, v. . . , v 1,
-5 , , , , ,
0010000WO1 0010000WO1 001000Chvo5 0010000wC4 OO10000WO1 0010000WO1 0010000NO2 0010000WO3 Sumey Meceumment Locatbn Ccriss O 3/24/93 Beta Radiation Statistical Summary 8:43 am for Bldg 100, Basement, NW Quad. Wall i dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 189 209 1619 948 File Name for this graph: RBNWWB .EPS h Figure A-48 Direct Beta Survey Results of Basement NW Quadrant Wall ; m')-runwrimewaanori.mo Page 50 of 163 REVISION 9
APPENDIX A O Bldg 100, Basement, NE Quad. Wall - A Direct Beta Survey 15 Dpm/100cm2 10 N 8 5 h.lYlb'hk?; YQY N!\???kY^'P$?'.lb:-i l, O
-5 .
, , , l 1
u020000WD1 uu2u000WO1 002t x Q)WO3 0020000WO2 0020000WD1 0020000WO1 0020000WO3 0020000WOS ; Suney Measurrmmt Locatin Codes l O Summary Table on following page. l l l l 1 l Figure A-49a Direct Beta Survey Results of Basement NE Quadrant Wall O
" " " " * " " " Page 51 of 163 REVISION 8
f APPENDIX A Bldg 100, Basement, NE Quad. Wall - B Direct Beta Survey 15 Opn/100cm2 5 F 10 b 9 g 5 t bijiainubbt&d'In.llua a A&MCab Lle.hkiL101._all O orp4 rr- . r > -- ,r- 1- 4 >+- - er - ' '
-5 ,
OuzuuuOWO3 D 72uuuuw03 0020000WOB uu2000CiWO7 00Zu000WO3 0020000WO5 UTEuX6WO6 0020000WO1 Surwy Measurement Lxcat'cn Codes i O 3/24/93 Beta Radiation Statistical Summary 9:17 am for Bldg 100, Basement, NE Quad. Wall dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 189 206 2291 1422 File Name for this graph: .EPS Figure A-49b Direct Beta Survey Results of Basement NE Quadrant Wall, continued
" " " " * " " " Page 52 of 163 REVISION 0-
APPENDIX A-O Bldg 100, Basement, SW Quad. Wall Direct Beta Survey 15 Opm/100cm2 10 g6 kmbud,%...h ,J ML.dtkLah.L ik n Jia L.I.au ~ d m,db-0 -, .. ,4 -
.cn . ,v, , . w r. . , , , ,, - -m i
-5 -
OO40000WO1 0040000WO1 0040000WO1 0040000WO2 0040000WO1 0040000WO1 0040000WO5 0040000WO3 Suney Memurement Locat'on Codes O 3/24/93 Beta Radiation Statistical Summary - 8:47 am for ; Bldg 100, Basement, SW Quad. Wall dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 228 250 1736 961 File Name for this graph: RBSWWB .EPS 1 Figure A-50 - Direct Beta Survey Results of Basement SW Quadrant Wall t mannesmmmamm Page 53 of 163 REVISION 8 h
- k. - , +e
APPENDIX A , r} Bldg 100, Basement, SE Quad. Wall - A Direct Beta Survey 15 Dgm/loocm2 10
$ ~
9 8 5 t c 1,.a so4ia(n numhbua dLuuklh dihuAdamlI.aulu ui ,i > u -o>-- ,ii," < "w.
-5; , , , , , ,
M 00}ooocMos En3oooow bw Survey Memurement Locat'en Codes O Summary Table on following page. l l Figure A-Sla Direct Beta Survey Results of Basement SE Quadrant Wall
""" ""**"" Page 54 of 163 REVISION 8 I
l i 1
APPENDIX A Or Bldg 100, Basement, SE Quad. Wall - B Direct Beta Survey 15 Dpm/100cm2 10 6 yg n.g11in ,. mmy..- -.d i. ala J IIk t...Llgt y slth .b4.6f JidteW o n . . , , - .- . , , . . . .
-5 , , , , ,
M 0 30000W 30000WD2 Suney Masurement Lccatkn Codes O 3/24/93 Beta Radiation Statistical Summary 9:35 am for Bldg 100, Basement, SE Quad. Wall dpm/100 sq. cm. 95% Confidence Level , Radiation Mean Upper Bound on Mean Maximum N Beta 395 415 1903 1310 File Name for this graph: .EPS t Figare A-51b Direct Beta Survey Resu!!< of Basement SE Quadrant Wall, continued
%d
""5""2"" '" Page 55 of 163 REVISION 9
APPENDIX - A O U Bldg 100, Basement, Electrical Pen. Direct Beta Survey 15 - mm 10 g sr3 8 5 o -- = r="r- w"s= - =g r='=u=s="g =~ <
-5 3...i...i. i ..i...i.. ; .i ..i..
"' 1ELH"o"s wPwsMinsan#Fi!L&"
- Scway Measunement Lccatbn Codes O 3/24/93 Beta Radiation Statistical Summary 8:37 am for Bldg 100, Basement, Electrical Pen.
dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta -463 -309 579 35 File Name for this graph: RBEPPB .EPS Figure A-52 Direct Beta Survey Results of Basement Electrical Penetrations
%/
" " "*** Page 56 of 163 REVISION 8
APPENDIX A (.
's~' /
Bldg 100, Basement, Piping Penet Direct Beta Survey 15 Dpm/100cm2 10 b sre E 5 S Y O IPjf" dI7 r r7 avl ll1Un
, i r y. JiN
= ~ ralsir,.lall .. I.,6 I.
m vi l
-5 r -'- " r ' - ' T'-' r'- r ' " '' r' > ' 'r ' ' '" i 0010000PO5 OO2OOOOP16 OO3OOOOP16 OO40000PO9 0020000P06 CO2OOOOP23 OO40000PO1 OO10000PO3 Surwy Measurement Loccibn Codes 1
0 L) Beta Radiation Statistical Summary 3/24/93 8:39 am for Bldg 100, Basement, Piping Penet. dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N-Beta 73 189 3364 148 File Name for this graph: RBPPPB .EPS I l Figure A-53 Direct Beta Survey Results of Basement Piping Penetrations g T .
""*""#" Page 57 of 163 REVISION 0 k.
APPENDIX A Bldg 100, Basement, Ceiling Direct Beta Survey 15 Dpm/100cm2 10 sr3
'Ahuh &
1 N'8 L# ?ftJNdi d 0 'DI11'dI M8 g
-5 , , , , , , ]
Oromnrm 0030000Cn1 j 0070SW1C01 0040000C01 0010000C01 0040000CD1 OCr200u0CH3 0030000CO3 l Surwy Measurement Locat'cn Cochs ) i O 3/24/93 Beta Radiation Statistical Summary 1 ' 8:36 am for Bldg 100, Basement, Ceiling dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 323 361 1427 341 File Name for this graph: RB00CB .EPS l
.. i l
i Figure A-54 Direct Beta Survey Results of Basement Ceiling O ,
""*"" """ Page 58 of 163 REVISION 8
s APPENDIX A O Bldg' 100, Operating Deck, NW Floor ; Direct Beta Survey 15 j Dpm/100cm2 10 sr! 4 g2 5 j t dit kn olll14fi1JJud.hlddannib Lui>- > lia.
. dittuu O - - i -
r e. ;- i P
-5 .
b11000F 11000 11000F 11000F01 Suney Measurement in:cibn Codes O 3/24/93 Beta Radiation Statistical Summary 8:57 am for Bldg 100, Operating Deck, NW Floor , dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 468 498 1752 510 File Name for this graph: ROF1FB .EPS 1 I l Figure A-55 Direct Beta Survey Results of Operating Deck NW Quadrant Floor O i l on92-run.srnramonois.ao Page 59 of 163 REVISION 8 1
APPENDIX ~A O Bldg 100, Operating Deck, NE Floor , Direct Beta Survey 15 Opm/100cm2 to b 89 5 t o A.->.,Lii,Lld1AulJihd!,illlllad. c ,halbb3 tht&MIlm
-5 , , , , , ,
$100 b1000FN b1000F 1000F02 Suney Measuremmt Location Codes O 3/24/93 Beta Radiation Statistical Summary 8:58 am for e Bldg 100, Operating Deck, NE Floor dpm/100 sq. cm.
95% Confidence Level ,
~
Radiation Mean Upper Bound on Mean Maximum N Beta 389 419 1649 505 File Name for this graph: ROF?FB .EPS Figure A-56 Direct Beta Survey Results of Operating Deck NE Quadrant Floor ( mesm*" Page 60 of 163 REVISION 8
APPENDIX A Bldg 100, Operating Deck, SW Floor Direct Beta Survey 15 Opm/1CQm2 10 b srl 5 88 Y O i Y -N N
-5 OO11000FO4 OO11000F04 OO11000FO4 OO11000FO4 0011000F04 OO11000F04 OO11000F04 OO11000FB4 Strwy Mecnsement Locatbn Coms ,,_~ , ,J 3/24/93 Beta Radiation Statistical Summary 9:00 am for Bldg 100, Operating Deck, SW Floor dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 431 460 1819 612 File Name for this graph: ROF4FB .EPS Figure A-57 Direct Beta Survey Results of Operating Deck SW Quadrant Floor i m'trumsnvwmon.u Page 61 of 163 REVISION 0 W
APPENDIX A
~' l \
Bldg 100, Operating Deck, SE Floor Direct Beta Survey 15 . . Opm/100cm2 10 O J$IAhrdahthblM d&llhli NWi llubilLu.ua th'.
-5 --== , , ,
OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000F03 OO11000F03 Sarwy Memunrrwnt Loccfon Codec ( ) 3/24/93 Beta Radiation Statistical Summary 8:59 am for Bldg 100, Operating Deck, SE Floor dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 462 491 3857 515 File Name for this graph: ROF3FB .EPS Figure A-58 Direct Beta Survey Results of Operating Deck SE Quadrant Floor
" " " " " " " Page 62 of 163 REVISION 0
APPENDIX A O Bldg 100, Basement, Stairwell One , Direct Beta Survey-15 Dpm/100cm2 10 b 9 g 5 t 0 dL d w.mligg-
. ri -
kta.1d taJ LLNDA a dd dlfhd
- - r i. 4
..*i i
r i
-5 , , , , ,
0070SW1F01 0070SW1WO1 0070SW1WO1 0070SW1WO3 0070SW1F01 0070SW1WO1 0070SW1WO3 0010000P01 Suney Measurement Lmat'en Codes l O 3/24/93 Beta Radiation Statistical Summary- '
.8:48 am for Bldg 100, Basement, Stairwell-One dpm/100 sq. cm. ,
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 397 427 2039 542 File Name for this' graph: RBSOOB .EPS I l I Figure A-59 Direct Beta Survey Results of Stairwell One O
" " " " " " " Page 63 of 163 REVISION 8 1
i
APPENDIX A O Bldg 100, Basement, Stairwell Two Direct Beta Survey 15 Dpm/100cm2 10 b 0 -deua e n Lgg m JkiE 1!M
# 3 r i . ., m,L.1 sh iE. ad i , -
w.k.JdMhhin
-5 , , , ,
00OSW2 00OSW2b 00 OS 70SW2F01 Suney Memunement Locddan Codes O 3/24/93 Beta Radiation Statistical Summary i 8:49 am for . Bldg 100, Basement, Stairwell Two [ l dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 416 441 1760 759 File Name for this graph: RBSTOB .EPS Figure A-60 Direct Beta Survey Results of Stairwell Two O
**""" " 3$ Page 64 of 163 REVISION 8 '
APPENDIX A O' Bldg 100, Operating Deck, Airlock 1 Direct Beta Survey ' 15 Dcm/100cm2 10 N sr8 8 3 5 t ' 0 A ,lI",YSfk1hYJ,p/-$#, ifdfkyg'lY*EA'@b i
-5 . . . . . . .
0021AL1F01 0021AL1WO1 0021AL1WO4 0021AL1CD1 0021AL1F01 0021AL1WO2 0021AL1WO6 0021AL1CD1 Suney Mecsurerre.t Lccaton Codes O 3/24/93 Beta Radiation Statistical Summary 8:54 am for Bldg 100, Operating Deck, Airlock 1 dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta -8 20 1268 535 File Name for this graph: ROA00B .EPS Figure A-61 Direct Beta Survey Results of Airlock One O
"""3" " "" Page 65 of 163 REVISION 9
APPENDIX A O Bldg 100, Operating Deck, Airlock 2 > Direct Beta Survey - 15 Dpm/100cm2 10 b sr! g2 5 i t O IVe"M dhdd dr!LNV "'- ^" ^ 'A O d b i 'J"^~ $
-5 , , , , , , ,
0021AL2F01 0021AL2WO2 0021AL2WO3 0021AL2CD1 0021AL2F01 0021AL2WO4 0021AL2WOS 0021 AL2CD1 Suney Mearsement Locat'en Codes , O 3/24/93 Beta Radiation Statistical Summary 8:54 am for Bldg 100, Operating Deck, Airlock 2 dpm/100.sq. cm. 95% Confidence Level Radiation Mean Upper Bound im Mean -Maximum N Beta 60 80 1078 490 i File Name for this graph: ROATOB .EPS 1 Figure A-62 Direct Beta Survey Results of Airlock Two on9ma m^"W* Page 66 of 163 REVISION 9 . p
APPENDIX A O- Bldg 100, Equipment Hatch Direct Beta Survey
's usamma opm/1oOma to N
g$ 5 t /N -N" 1,".ffp', EA'i'8o4't'1'r';i.'MrNIvIEI 0 i l
-5 , . . . . . . .
0011EH1F01 0011EH1WO1 0011EH1WO3 0011EH1WO2 0011EH1F01 0011EH1WO5 0011EH1WO4 0011EH1CD2 Survey Memurement Lrmiian Ccdes O 3/24/93 Beta Radiation Statistical Summary 8:56 am for Bldg 100, Equipment Hatch dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta -55 -18 1384 345 File Name for this graph: ROEHOB .EPS Figure A-63 l Direct Beta Survey Results of Equipment Hatch , O I 1
"'"t**""""" Page 67 of 163 REVISION 6 l
i
APPENDIX A
-Q Bldg 100, Operating Deck Elec. Pen. !
Direct Beta Survey 15 Dom /100cm2 10 b g 5 t , .. e _........ L.___,____
-5 ii .i.. i... ...i ..i...i. .i>>.i.
0011000E01 0011000E09 0011000E17 0011000E25 0011000E39 0011000E05 0011000E13 0011000E21 0011000E29 i Suncy Manrement Locatbn Ccxhs O 3/24/93 Beta Radiation Statistical Summary 8:55 am for Bldg 100, Operating Deck Elec. Pen. dpm/100 sq. cm. 95% Confidence Level ' Radiation Mean Upper Bound on Mean Maximum N s Beta -17 174 2500 34 i File Name for this graph: ROEPPB .EPS e i Figure A-64 Direct Beta Survey Results of Operating Deck Electrical Penetrations -!
" " " " * " " * " Page 68 of 163 REVISION 9 ,
APPENDIX A Bldg 100, Operating Deck, Pipe Pen. '~' Direct Beta Survey 15 Dpm/100cm2 10 b sr5 gh 5 Y o - g- Y " J pgy@ S " " ,=+-
-5 i i i i i i i
i e i OO11000P15 0011000 0 0 0011000P29 OO11000P17 OO11000P27 0011000P32 Suney Mcmemt Locots Codrs A 3/24/93 Beta Radiation Statistical Summary 9:01 am for Bldg 100, Operating Deck, Pipe Pen. dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 149 593 1592 11 File Name for this graph: ROPPPB .EPS Figure A-65 l Direct Beta Survey Results of Operating Deck Piping Penetrations i
"*****""" Page 69 of 163 REVISION 0 C.
APPENDIX A O Bldg 100, Operating Deck Wall to 2M Direct Beta Survey 15 , Dom /100cm2 10 sr! g !2 5 d o .Jw1 nn
. r- . 11
. . y rLu.dL1a1.11.1A14
. .w - -
addhala LMl!ullb t 4 rc . ...,c
-5 , , ,
$11000WY 0011000W$ $11000N $1000WB1 Suney Mamsnment Loccfon Ccdes O 3/24/93 Beta Radiation Statistical Summary 9:03 am for Bldg 100, Operating Deck Wall to 2M dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N i i Beta 320 342 1870 900 l 1 File Name for this graph: RO2MWB .EPS )
)
Figure A-66 f Direct Beta Survey Results of Operating Deck Wall to 2 Meters l C
" " " * " " " Page 70 of 163 REVISION 8
APPENDIX A C' Bldg 100, Operating Deck, Wall > 2M Direct Beta Survey l 15 Dpm/100cm2 10 6 9 g- 5 t ildId tu tidi EIavLit,thk.se silit'b,,.alfid&k at.s d 21 k. d .. 0 2 e -> >< 1 '-- r 6 a
. 6 0011000wY $11000WY 0011000WO1 $11000WD1 Suncy Mecsurement Lccatbn Codes i O 3/24/93 Beta Radiation Statistical Summary l 9:04 am for Bldg 100, Operating Deck, Wall > 2M dpm/100 sq. cm. )
95% Confidence Level I Radiation Mean Upper Bound on Mean Maximum N l l Beta 388 416 1764 540 l l File Name for this graph: ROA2WB .EPS I i l l Figure A-67 Direct Beta Survey Results of Operating Deck Wall > 2 Meters. i
* * " " " " " " Page 71 of 163 REVISION 6
- _ _ _ _ _ __i
APPENDIX A O Bldg 100, Remains of Platforms 1&2 , Direct Beta Survey ; I 15 .! w mcm2 10 g sr! g2. 5 t O o L.. .. = .:_ L.-hlLu.a..n -- ,.m._m.
......i .. .i......i4... .i
-5 i. ....i...... .....
OO11000 FOS 0011000 FOS OO11000 FOS OO11000 FOS , OO11000F06 0011000F06 OO11000F06 OO11000F06 - Suney Measurement Locatbn Codes l O 3/24/93 Beta Radiation Statist._ cal Summary , 9:01 am for Bldg 100, Remains of Platforms 1&2 , dpm/100 sq. cm. l 95% Confidence Level ! Radiation Mean Upper Bound on Mean Maximum N Beta 388 479 1391 50 File Name for this graph: ROS6FB .EPS p Figure A-68 i Direct Beta Survey Results of Remains of Platforms 1 and 2 O t
" " * " " " Page 72 of 163 REVISION 9 .
i
?
APPENDIX A r^x ( Bldg 100, Crane Direct Beta Survey 15 Dpm/100cm2 10 N 5 9 5 L.. ..linkl t n , i me. n lt mlf f 1 fl . . it) 2 . ,la . u . g . . .
-5 ,- - r-2- -
r- F""- i . ""P 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 Surwy Mecxxnment Urcibn Cods
/'~~
(' ' 3/24/93 Beta Radiation Statistical Summary 8:53 am for Bldg 100, Crane dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 83 119 1029 230 File Name for this graph: RDCROB .EPS Figure A-69 gs Direct Beta Survey Results of Crane i O l m esunm en.u Page 73 of 163 REVISION 9
APPENDIX A i Bldg 100, Containment Dome , Direct Beta Survey . 15 Dpm/100cm2 10 b g 5 r 0 ? Y N,W. :-l !A r' ??
?,.Ylh.'..kh, 1
i
-5 .
0012000CD1 0012000CD1 0012000CD1 0012000C01 l 0012000C01 0012000C01 0012000C01 0012000C01 l Surwy Mecourement LocatM Cochs , O 3/24/93 Beta Radiation Statistical Summary j 8:52 am for i Bldg 100, Containment Dome dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 162 182 1618 755 File Name for this graph: RDCDOB .EPS l l Figure A-70 Direct Beta Survey Results of Containment Dome 0
" ' " * * * * * " " Page 74 of 163 REVISION 9 l
4
APPENDIX A l O Bldg 100, Yard, Exhaust Stack Pad Direct Beta Survey 15 Opm/100cm2 10 b sr3 g' 5 --
@ d(d L.id b'i ll ektjnJ M d gl1][jk h g 4 lyp1 J
-5, , , ,
10P01f 1 10PO1F 0 OP01WO2 OPO1WO4 Suney Memurement Lccat'e n Cccm O 3/2 4/ ' + 3 Beta Radiation Statistical Summary 9:12 m for Bldg 100, Yard, Exhaust Stack Pad dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 658 706 2734 300 File Name for this graph: RYSPOB .EPS Figure A-71 Direct Beta Survey Results of Exhaust Stack Pad O 0N*"""" " Page 75 of 163 REVISION 0
--e.- - - . - -
s
)
APPENDIX A l I O Bldg 100 Basement NW Quad. Floor ; Alpha Removable Contamination 20 Abhacbm/ 15 6 to g 8 5 i I II I l 11 I I I I o
-5
-10,.............3.................r''''i"'"""'>"i'""'"r""i""'"""""'
i 7021 7021 7022 7022 7021 7021 7022 Suncy Locatkr) Fh tirr6er 3/24/93 Alpha Radiation Statistical Summary 11:25 am for-Bldg 100 Basement IN Quad. Floor dpm/100 sq. cm. Radiation Mean Maximum N , Alpha -0 4 125 File name for this graph: RBlWFSA .EPS l i i Figure A-72 Removable Alpha Survey Results of Basement NW Quadrant Floor O
"**""#""" Page 76 of 163 REVISION 0
APPENDIX A O Bldg 100 Basement NE . Quad. Floor Alpha Removable Contamination , 20 Abha dpm/ . 15 10 g 8 q 5 b II lIl1 1 11 1111 11 1 11 1 II II I i
-5
-10 r " "-"""" m r '~"m *" ~r 'm" " * '"=r"- " '- "~r ="m "" ~ '"r'- """' ""' r"' "" "
3854 3854 3854 3855 3854 3854 .3855 Suney Locatbn Fh Number Alpha Radiation Statistical Summary 3/24/93 11:26 am for Bldg 100 Basement NE Quad. Floor dpm/100 sq. cm. I I Radiation Mean Maximum- N Alpha 0 4 135 File name for this graph: RBNEFSA .EPS Figure A-73 Removable Alpha Survey Results of Basement NE Quadrant Floor O
"""""""#" Page 77 of 163 REVISION 9
1 I APPENDIX A i Bldg 100 Basement SW Quad. Floor Alpha Removable Contamination 20 Abha dpm/ 15 li to g 8 5 0 l I I!!I E I I Il lli II g
-5
-10 p.u.. .. .." o.. r m.o. ... .o ou.p.o a.u no.ui".. .o " o u. co."."."" o .e ..o"o " no r u o ". oon 7413 7413 7413 7414 7413 7413 7414 Suney Lomron Fle Number 3/24/93 Alpha Radiation Statistical Summary 11:27 am for '
Bldg 100 Basement SW Quad. Floor dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 4 129 File name for this graph: RBSWFSA .EPS 9 Figure A-74 Removable Alpha Survey Results of Basement SW Quadrant Floor O
** """ """ Page 78 of 163 REVISION 8
APPENDIX A ; 1 O -Bldg 100 Basement SE Quad. Floor i Alpha Removable Contamination I 20 Ahho cim/ 15 6 10 sr 8 5 o i I ll ll Illi ll Il l I I I I I
-5 ;
-10,,,,................,,,,,,,,,.........,..........,,,,,,,,,,........,,,,,,,,,,,,m...........,.. .,,,,,,,,,,,,,,,,,,,,,,,,,,,,
7025 7025 7026 7026 7025 7025 7026 Suney Lccatin Fle Number ; 3/24/93 Alpha Radiation Statistical Summary 11:26 am for 3 Bldg 100 Basement SE Quad. Floor ! dpm/100 sq. cm.
-{
l Radiation Mean Maximum N Alpha -0 4 135 File name for this graph: RBSEFSA .EPS l i 1 i Figure A-75 Removable Alpha Survey Results of Basement SE Quadrant Floor i
" " " * " "*" Page 79 of 163 REVISION 9 l 4.,.- , ,,. .- __
APPENDIX A O Bldg 100 Basement Gamma Well Alpha Removable Contamination 20 Abho ctrn/ 15 6 10 8 q 5 4 .I J_ ___ I._____ __LII_____ __
, o x
-5
-10 si.. .i.. . ..i . ...i... ...ii .....ii .....i.....
7121 71 21 7121 7121 7121 7121 7121 Sur.cy LoccWen Fh Number O 3/24/93 11:33 am Alpha Radiation Statistical Summary for Bldg 100 Basement Gamma Well dpm/100 sq. cm. Radiation Mean Maximum N
-0 2 54 !
Alpha i File name for this graph: RBGWOSA .EPS l 1 i l i Figure A-76
- Removable Alpha Survey Results of Basement Gamma Well
\
" " " * * * " * " Page 80 of 163 REVISION 0 i
APPENDIX A l (3 Bldg 100 Basement Sump Alpha Removable Contamination 20 Abha dpm/ 15 10 8 q 5 4 E*****--************ O
-5
-10 i
, . , , , , , , . , i 7271 7271 7271 7271 Surwy Locotbn Fh Number (9j
/
3/24/93 Alpha Radiation Statistical Summary 11:32 am for Bldg 100 Basement Sump dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 7 20 File name for this graph: RBSU0SA .EPS Figure A-77 Removable Alpha Survey Results of Basement Sump
" " ""##"" Page 81 of 163 REVISION 8 L_
APPENDIX A
,c ,x J Bldg 100 Basement Drains Alpha Removable Contamination 20 g Abha ctm/
15 b 10 - 8 5 e O .h .
. . . .h --. .
-5
-10 i i
i i i i i i i 7015 7015 7016 Surey Lccat'm Fh Number 3/24/93 Alpha Radiation Statistical Summary 11:23 am for Bldg 100 Basement Drains dpm/100 sq. cm. Radiation Mean Maximum N l Alpha 0 2 10 File name for this graph: RB00DSA .EPS l Figure A-78 Removable Alpha Survey Results of Basement Drains
"*"'" "*"" Page 82 of 163 REVISION 0
APPENDIX A i O Bldg 100 Basement Trenches-Alpha Removable Contamination . 20 Abha dpm/ 15 > N sr g 1 q 5
.J..l. - U l. .l f -5 o . ..l.II
-10 iiiiii iipii iiiieiiii.
i iiiiiieiii iiiiiiiiipiiiiii ; 5925 5925 5925 5925 , Suncy Location Fh Numtur 3/24/93 Alpha Radiation Statistical Summary 11:32 am for .i; Bldg 100 Basement Trenches dpm/100 sq. cm. Radiation ! Mean Maximum N Alpha -0 2 62 File name for this graph: RBTROSA .EPS r Figure A-79 Removable Alpha Survey Results of Basement Trenches
""*"* ""#" Page 83 of 163 REVISION 9
APPENDIX A O Bldg 100 Basement Structures Alpha Removable Contamination 20 A W ttm/ 15 b 10 g 8 q 5 0 --
*- * -*- aa"* -
w'* -
-5
-10 . . . . . . . . . .
i i i i i 7051 7051 7051 Suncy Lcastcn Fh Numter 3/24/93 Alpha Radiation Statistical Summary 11:28 am for Bldg 100 Basement Structures dpm/100 sq. cm. Radiation Mean Maximum N Alpha 1 2 15 File name for this graph: RBOOSSA .EPS Figure A-80 Removable Alpha Survey Results of Basement Structures
"""*3"""" Page 84 of 163 REVISION 9
l APPENDIX A O Bldg 100 Basement NW Quad. Walls Alpha Removable Contamination ! 20 ,,,,, j Abha cbm/ 15 , li ' sr i 5 ll 11 Ill ll Il ll ll l lllll 11lll El l Ill I _5 -
-10, , , -- , , , ,
5849 5849 5899 7 011 Surwy Lccatim Fh Numtw 3/24/93 Alpha Radiation Statistical Summary 11:29 am for Bldg 100 Basement NW Quad. Walls
-I dpm/100 sq. cm.
Radiation Mean Maximum N ; Alpha 0 4 254 File name for this graph:. RBNWWSA .EPS i i 4 Figure A-81 i Removable Alpha Survey Results of Basement NW Quadrant Wall l O
" " " " " " " Page 85 of 163 REVISION 9
APPENDIX A O Bldg 100 Basement NE Quad. Walls l Alpha Removable Contamination 20 , Abha dpm/ 15 d sr : 8 q 5 . I lllili II I I II I I I ll Ill11 l
-5
- L
-10,- , ,e , , ,
3856 3857 5983 i Surwy Locatbn Fh Nurrtxr , O 3/24/93 11:29 am Alpha Radiation Statistical Summary for Bldg 100 Basement NE Quad. Walls dpm/100 sq. cm. Radiation Mean Maximum N l Alpha -0 4 192- l File name for this graph: RLNEWSA .EPS - l i i Figure A-82 Removable Alpha Survey Results of Basement NE Quadrant Wall
" " " " * * " * " Page 86 of 163 REVISION 9 _
f k APPENDIX A l O Bldg 100 Basement SW Quad. Walls - Alpha Removable Contamination ; F 20 Abha dpm/ 15 N 10 g 8 5 ll l5 llllllllll l- llll ! I IIIIIll ll l lll llll 4
-5 i
-10 p== - , , . 3 ;
7048 7282 7283 l Suney Lccaron Fb Number 3/24/93 Alpha Radiation Statistical Summary 11:31 am for . Bldg 100 Basement SW Quad. Walls dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 9 262 File name for this graph: RBSWWSA .EPS i Figure A-83 Removable Alpha Survey Results of Basement SW Quadrant Wall
""* """"" Page 87 of 163 REVISION 8
APPENDIX A . O Bldg 100 Basement SE Quad. Walls ! Alpha Removable Contamination l 20 , 15 10 g 5 , I l ll lll l lli 11 I lll i Il l ll ll l
-5 l
-10, , , , , , ,
5828 5828 5845 5901 l 58 2 gg Suney Location Fh timts 3/24/93 Alpha Radiation Statistical Summary 11:30 am for Bldg 100 Basement SE Quad. Walls , dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 4 190 File name for this graph: RBSEWSA .EPS _; I Figure A-84 Removable Alpha Survey Results of Basement SE Quadrant Wall O
" " " " " "
- Page 88 of 163 REVISION 8
APPENDIX A O' Bldg 100 Basement Electrical Pen. Alpha Removable Contamination . 20 Atto ctm/ 15 b 10 g 8 5 q
........E.) E .... ... ..).E ..E . .....
f -5 0
-10 iiiiiiiiiii iiiis iiiiiiiiii iii.
7097 7097 7097 7097 Stney LcccfJcn Fh Number C/ 3/24/93 Alpha Radiation Statistical Summary 11:24 am for Bldg 100 Basement Electrical Pen. dpm/100 sq. cm. Radiation Mean Maximum N Alpha -0 2 35 File name for this graph: RBEPPSA .EPS Figure A-85 Removable Alpha Survey Results of Basement Electrical Penetrations
- 4.
""* "*""*" Page 89 of 163 REVISION 9 W-
APPENDIX A . Bldg 100 Basement Piping Penet Alpha Removable Contamination m 15 N 10 g 8 5
- Il l I I Il I I 1 1 1
-5
-10ru...........r"""'"'"r""'"'"'"r'""""'""'r""""'r""""""t""""'"'*
7371 7381 7388 7387 . 7371 7381 7387 ! Suney Locotbn Fh Numbw 3/24/93 Alpha Radiation Statistical Summary 11:24 am for Bldg 100 Basement Piping Penet. dpm/100 sq. cm. Radiation Mean Maximum N Alpha -0 4 119 File name for this graph: RBPPPSA .EPS Figure A-86 Removable Alpha Survey Results of Basement Piping Penetrations O.
" " " * " Page 90 of 163 REVISION 8 -
- . y
APPENDIX A O Bldg 100 Basement Ceiling Alpha Removable Contamination 20 Abha dpm/ 15 g to g 8 q 5 4 _.l.l _ _ . l.i.. l__U _ 1.1 . _ f o . g
-5
-10 pTmtrrtini,o.oi.onnoi.onin.p.nonp.onnp.n, 7C64 7095 7382 7383 7084 7095 7382 Surwy Locatbn Fh Number 3/24/93 Alpha Radiation Statistical Summary ,
11:22 am for Bldg 100 Basement Ceiling dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 7 67 File name for this graph: RB00CSA .EPS Figure A-87 Removable Alpha Survey Results of Basement Ceiling
""8""""" Page 91 of 163 REVISION 9
APPENDIX A s O Bldg 100 Operating Deck Floor ;
. Alpha Removable Contamination , . 20 Abha ctrn/
15 6 to g 5 0 O 1111 I IINIIll IR l l l l ll l Il 111ll IllII I ll ll - 4 t
-10 , , , , , ,
7405 7408 7410 , Suney Locatbn Fb Nurnber 3/24/93 Alpha Radiation Statistical Summary 11:37 am for ; Bldg 100 Operating Deck Floor ! dpm/100 sq. cm. > 4 Radiation Mean Maximum N ! Alpha 0 7 432 File name for this graph: ROF0FSA .EPS l t Figure A-88 'l Removable Alpha Survey Results of Operating Deck Floor
""" """"" Page 92 of 163 REVISION 8 l i
APPENDIX A - O Bldg 100 Basement Stairwell One i Alpha Removable Contamination j 20 f Abha dpm/ 15
$ .0 g 4 8 5 )
III I II I I I I I l I II a ;
-5
-10 p u o m o u , m y.m ..o o , o.,p o n, , u n. ni. .n ou. ..o. y.o o. n..o.m io n m..n u ,mp n o in n 7070 '7071 7072 7072 7070 7071 7072 Suney Locatkn Fle Nrnber ,
3/24/93 Alpha Radiation Statistical Summary 11:34 am for Bldg 100 Basement Stairwell One . dpm/100 sq. cm. 'I 1 I Radiation Mean Maximum N j l Alpha 0 ' 7 107 l 1 File name for this graph: RBSOOSA .EPS - 1 l
\
Figure A-89 p Removable Alpha Survey Results of Stairwell One l
" " * " " " '8 " Page 93 of 163 REVISION 9
APPENDIX A O Bldg 100 Basernent Stairwell'Two Alpha Removable Contamination I 20 Abha dpm/ 15 6 g ' 8 3
?
- I Il lli Ill E lll111 Iil 1I I :
e f '
-5 143315iJBBIE33I i 4 3 5 3II B BI4 3 I'Ig'313 IIiIIIIa 8 e F g B 6 II f 5Ila 4 5I 51gis niIIII s a a t si s g 3 s i s allIa iIin s igi16 5II4 44 IIII 7218 7219 7220 7221 ;
7218 7219 7221
- Suncy Locat'en Fh Nurrtxr CJ 3,2 ,,, A1pha Rae1ae1.. Seae1.,1.a1 Smmmar, ,
11:34 am for > Bldg 100 Basement Stairwell _Two dpm,100 sq. cm. Radiation Mean Maximum N , Alpha 0 7 110 File name for this graph: RBSTOSA .EPS i Figure A-90 Removable Alpha Survey Results of Stairwell Two
, 0 i on92.runsirvacaonois.mo Page 94 of 163 REVISION 8
APPENDIX A O Bldg 100 Operating Deck Airlock 1 Alpha Removable Contamination 20 Ahha ctm/ 15 {l 10 g 8
- 5 1 1
- I I I IIII IB U 11 11 I I I II
-5
-10 p io u. u oap ..o uo m op o o u . ". .p omo o o o p .o .o o " .io ooio o opio o o.u a 7424 7424 7425 7425 7424 7425 7425 Surwy Lecotbn Fh Number 3/24/93 Alpha Radiation Statistical Summary 11:41 am for Bldg 100 Operating Deck Airlock 1 dpm/100 sq. cm.
Radiation Mean Maximum N ! Alpha 1 7 105 File name for this graph: ROAOOSA .EPS l Figure A-91 I Removable Alpha Survey Results of Airlock One 1
" " " " " " Page 95 of 163 REVISION 0
4 APPENDIX A ,
?
~
Bldg 100 Operating Deck- Airlock 2 Alpha Removable Contamination . 20 ; Abha ctrn/ 15 N 10 5 3 i Il iII I III I II I I JJ_,J_l_ o < l
-5
-10 p u .o . " . .op " .o u u n. y n oi u o. .o .p. ". u ." u u p. u ni u u u po o. u oin e.u n . u ;
7423 7423 7423 7423 l 7423 7423 7423 Smey Locatbn Fh Number l 3/24/93 Alpha Radiation Statistical Summary 11:42 am for Bldg 100 Operating Deck Airlock 2 dpm/100 sq. cm. l Radiation Mean Maximum N Alpha 0 4 100 I File name for this graph: ROATOSA .EPS l l l l Figure A-92 j Removable Alpha Survey Results of Airlock Two O
"" " "***"" Page 96 of 163 REVISION 9 l l
'1
APPENDIX A O Bldg 100 Equipment Hatch Alpha Removable Contamination 20 - Atho dpm/ 15 ,
$ 10 g
8 q 5 0 -- -- --
-5 l
-10 ........ ........,........ ................. ........ ........
7426 7426 742S 7428 Suney Locatkn Fle Number 3/24/93 Alpha Radiation Statistical Summary 11:42 am for , Bldg 100 Equipment Hatch dpm/100 sq. cm. Radiation Mean Maximum N , I Alpha 0 4- 63 .l File name for this graph: ROEHOSA .EPS Figure A-93 Removable Alpha Survey Results of Equipment Hatch O
' " "-" " " " " " " Page 97 of 163 REVISION 0 1
- -- - - .,. _ _ _ ]
- APPENDIX A O Bldg 100 Operating Deck Elec. Pen. 3 Alpha Removable Contamination x
Abha ctm/ ; 15
$ t 10 g
k 5 4 g o .....................s..... l
-5 l
- -10 3 .
...i....i. ..i... i....i.... ;
7096 7096 7096 ; Survey Lccaton Fle Number 3/24/93 Alpha Radiation Statistical Summary . 11:37 am for Bldg 100 Operating Deck'Elec.-Pen. l dpm/100 sq. cm. ; Radiation Mean Maximum N Alpha -0 4 30
-]
File name for this graph: ROEPPSA .EPS i l Figure A-94 , Removable Alpha Survey Results of Operating Deck Electrical Penetrations l l l
" " " " " " " " Page 98 of 163 REVISION 6 ' i i
APPENDIX A
,7m '~ ';
Bldg 100 Operating Deck Piping Pen. Alpha Removable Contamination 20 ,,,,,, AW @m/ 15 N 10
~
5 - jW o n ___ _ __ _ ___ _ __ _ _in _ ___ __i n ___ _ __ _ __L
-5
-10 iii iiii=1 >>l ie i i' i'iiT~
7415 7415 7415 7415 l 7415 7415 7415 Suney Locatbn Fb Number i
/~
- (/ 3/24/93 Alpha Radiation Statistical Summary 11
- 38 am for Bldg 100 Operating Deck Piping Pen.
dpm/100 sq. cm. Radiation Mean Maximum N 1 Alpha 0 7 37 File name for this graph: ROPPPSA .EPS Figure A-95 Removable Alpha Survey Results of Operating Deck Piping Penetrations
" " " " " " Page 99 of IC3 REVISION 0
p m A 19E 4 . ,3 4 4 -..*A4-# A J 4 % m APPENDIX A O Bldg 100 Operating Deck Walls to 2M Alpha Removable Contamination 20 Abho ctm/ 15 { 10 g -i 8 q 5 E l lill I I il l II I I II 11 4
-5
" pI V lui IHilli 14(ll5'54HEltil ""'If 1914I5 6 3 f 15 6 85165 5513 514 G Bl4 IIS Illi lIIII NgFTilHIGHE 7007 7007 7008 7008 7007 7007 7005 Suney Locat'm Fh Numtw 'i 3/24/93 Alpha Radiation Statistical Summary 11:40 am for Bldg 100 Operating Deck Walls to 2M dpm/100 sq. cm.
Radiation Mean Maximum N Alpha -0 4 150 File name for this graph: RO2MWSA .EPS Figure A-96 Removable Alpha Survey Results of Operating Deck Wall to 2 Meters O
"""" "'" Page 100 of 163 REVISION 8
- a e .
.a., 6 APPENDIX A O Bldg 100 Operating Deck Wall >2M Alpha Removable Contamination 20 -
Ahha ctrn/ 15 g 10 8 q 5 4 .JLbJ.ILI I EJ U..L U UJL o
-5
-10 pu.au m.o ip ..uu uu. u p u iou ..uipuuu". .u .p u ....u u u u p u. u u u u u i" u .u n u 5905 5906 5906 ,
S969 Sursey i.ocatkn Fh Number 3/24/93 Alpha Radiation Statistical Summary 11:39 am for Bldg 100 Operating Deck Wall >2M dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 4 108 File name for this graph: ROA2WSA .EPS Figure A-97 Removable Alpha Survey Results of Operating Deck Wall > 2 Meters O
"""*#""" Page 101 of 163 REVISION 9
APPENDIX A () Bldg 100 Platforms Alpha Removable Contarnination i m - Abha cbm/ 15 10 g 8 q 5 - 0 -wwwww
-5 i i
-10 i i i
i i i i i i i i i i i i i 5968 5968 59G8 5968 59G8 5968 5968 Surwy Locat'en Fb Mirter r sj 3/24/93 Alpha Radiation Statistical Summary 11:39 am for Bldg 100 Platforms dpm/100 sq. cm. Radiation Mean Maximum N Alpha 0 4 20 File name for this graph: ROS60SA .EPS l l l l Figure A-98
,r T Removable Alpha Survey Results of Platforms is' l
l
" " " """" Page 102 of 163 REVISION 9 l
APPENDIX A \ Bldg 100 Crane Alpha Removable Contamination , 20 Abha dpm/ N 10 Illl 8 " 1 O i. ..i . ....u..i .i... ..a.11 l J .,
-5 -
-10 ;.ii...iii. ,,,ii. ,,....iii..,,..i ii,i,,i 7277 7277 7277 7277 Suney Lccatbn Fh Number V' 3/24/93 11:36 am Alpha Radiation Statistical Summary for Bldg 100 Crane dpm/100 sq. cm.
Radiation Mean Maximum N Alpha 1 7 46 File name for this graph: BDCROSA .EPS Figure A-99 Removable Alpha Survey Results of Crane
" " " * " " " Page 103 of 163 REVISION 9
APPENDIX A
,m
() Bldg 100 Containment Dome Alpha Removable Contamination 20 Abha @m/ 15 10 Ei 8 q 5 I I I I I I ll ll l l 11 E
-5
-10 r '" a m ' " '" = f""' > = " i '"' ' a "< ' "' "i - -r"'"I"'"'""'"'"i-'-'"""
7064 7065 7093 711 5 7064 7093 7115 Surwy Locat'en Fh Number ,7~~] 'Ns' 3/24/93 Alpha Radiation Statistical Summary 11:35 am for Bldg 100 Containment Dome dpm/100 sq. cm. Radiation Mean Maximum N Alpha -0 2 152 File name for this graph: RDCDOSA .EPS Figure A-100 Removable Alpha Survey Results of Containment Dome (-)g L.. m e urm**"" Page 104 of 163 REVISION 0
1 APPENDIX A Bldg 100 Yard Exhaust Stack Pad-Alpha Removable Contamination 20 Abha ctm/ 15 g . 10 g 8 q 3 -- E y 0 JJ.L.- . 3.3 3.)Jl3..-. .J ..
-5
-10 a... iiiiiiiiiiii.i .
- i. . .... .. .. ..i.i.iiiiii>>. .
7561 7561 ~ 7561 7561 7561 7561 7561 Surg Lccatbn Fb tArnber O 3/24/93 11:46 am Alpha Radiation Statistical Summary for Bldg 100 Yard Exhaust Stack Pad dpm/100 sq. cm. 1 I Radiation Mean Maximum N j l Alpha 0 7 60 i l File name for this graph: RYSPOSA .EPS Figure A-101 Removable Alpha Survey Results of Exhaust Stack Pad
*8""" " Page 105 of 163 REVISION 9
{ 1
APPENDIX A s) Bldg 100 Basement NW Quad. Floor Beta Removable Contamination 1000 Beto dpm/ B00
$ 600 BT k 400 4
200
=
^
0
--200ii...........r'"'''>r"'''''i'""'i'"'""i"'"'"'"i""""""r'="
i 7021 7021 7022 7022 7021 7021 7022 7022 Sun.ey Locatbn Fh Numbcr 3/24/93 Beta Radiation Statistical Summary 11:00 am for Bldg 100 Basement NW Quad. Floor dpm/100 sq. cm. Radiation Mean Maximum N Beta -1 15 125 File name for this graph: RPNWFSB .EPS Figure A-102 Removable Beta Survey Results of Basement NW Quadrant Floor a
" " * " * " " " Page 106 of 163 REVISION 0
?
APPENDIX A .; t O Bldg 100 Basement NE Quad. Floor l . Beta Removable Contamination .
)
f 1000 Beto ctm/ 'f 800
$ em :
sr 8 4m m I h 2m : g
~
I 0
.. .. .' r
-200v.............i..................c................i....................................r..............i.......
3854 3854 3854 3855 3854 3854 3854 3855 , Suney Locatbn Fle Number r i 3/24/93 Beta Radiation Statistical Summary 11:01 am for-Bldg 100 Basement-NE Quad. Floor ; i dpm/100 sq. cm. .; Radiation Mean Maximum N Beta 1 11 135 ! a File name for this graph: RBNEFSB .EPS , i i Figure A-103 ! Removable Beta Survey Results of Basement NE Quadrant Floor
- - - - Fa,eio, erie 3 xevisios . ;
i
APPENDIX A- -, O Bldg 100 Basement SW Quad. Floor Beta Removable Contamination : 1000 Beta dom / - 800
$ 600 N i k
400 4 200 a -- - " - - - ~ 0
-200......m.......................i...............'r'i'">i"'-""r'""i
i 7413 7413 7413 7414 7413 7413 7414 7414 Suney Location Fle tArnber O 3/24/93 11:02 am Beta Radiation Statistical Summary for Bldg 100 Basement SW Quad. Floor dpm/100 sq. cm. Radiation Mean Maximum N-Beta 2 20 129 File name for this graph: RBSWFSB .EPS 1 1 i Figure A-104 Removable Beta Survey Results of Basement SW Quadrant Floor
" * * * " " " Page 108 of 163 REVISION 8
APPENDIX A
/O 'J Bldg 100 Basement SE Quad. Floor Beta RemoT7able Contamination 1000 Beto dpm/
800 N Sr bi k 400 4 200 a D - -
-200p..........p...........u.p.............;..... ........p............p,............'r""""l' 7025 7025 7025 7028 7025 7025 7026 702S Suney Locatkn Fle Ntmber ' Beta Radiation Statistical Summary 3/24/93 11:01 am for Bldg 100 Basement SE Quad. Floor dpm/100 sq. cm.
Radiation Mean Maximum N Beta -0 13 135 File name for this graph: RBSEFSB .EPS Figure A-105 . Removable Beta Survey Results of Basement SE Quadrant Floor I 1 mm e m ir m e n2e Page 109 of 163 REVISION 0 l
- APPENDIX A~
O Bldg 100 Basement Gamma Well , Beta Removable Contamination 1000 Beto cbm/ 800 ., b
- sr 4
= --
O
-200 ;i ..i i>iiii iii >>iiii>>i iiiiiiiii4 iiii. iiiiiiiii 7121 7121 71 21 7121 71 21 71 21 71 21 71 21 Surwy Locatin Fb Number ,
3/24/93 Beta Radiation Statistical Summary. 11:08 am for Bldg 100 Basement Gamma Well dpm/100 sq. cm. Radiation Mean Maximum N Beta -1 10 54 i File name for this graph: RBGWOSB .EPS Figure A-106 l Removable Beta Survey Results of Basement Gamma Well l
"'***""#*"" Page 110 of 163 REVISION 6 j
APPENDIX A > i O Bldg 100 Basement Sump Beta Removable Contamination : ,, 1000 Beta cbm/ , b b "" e k 400 4 - 200 o _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-200 i i i i i , i i i i i i i i i i i i i i 7271 7271 7271 7271 7271 Suney ucatbn Fle Number 3/24/93 Beta Radiation Statistical Summary .
11:06 am for Bldg 100 Basement Sump dpm/100 sq. cm. Radiation Mean Maximum N Beta 1 8 20 File name for this graph: RBSU0SB .EPS Figure A-107 Removable Beta Survey Results of Basement Sump
"""""""""" Page 111 of 163 REVISION 9 f
' APPENDIX A -
Bld.g 100 Basement Drains Beta Removable Contamination 1000 Deto cbm/ - .: 800
$ S a
k 400 -; 4 - 200 g
~~~~~~'~~~~
0
-200 i i i ; i i i i i 3 7015 7015 7015 ' 7016 7016 7015 7015 7016 7016 7016 Surwy Locatbn Fle NLnber i
3/24/93 Beta Radiation Statistical Summary 10:58 am for Bldg 100 Basement Drains dpm/100 sq. cm. Radiation Mean Maximum N , Beta -1 5 10 File name for this graph: RB00DSB .EPS l i 1 Figure A-108 Removable Beta Survey Results of Basement Drains
" " * " " " " " Page 112 of 163 REVISION 8 , . . . . , . -. ..g
APPENDIX A O Bldg 100 Basement Trenches Beta Removable Contamination
'om Beto ctm/
800 a 8 4T m h 2m g ; 0 - -- --
-- - ~ -
-200 pi....pi...p.....p....p.....pi.... p... .p...
5925 5925 5925 5925 5925 5925 5925 5925 St.ney Lracot'm Fh Number 3/24/93 Beta Radiation Statistical Summary l 11:07 am for Bldg 100 Basement Trenches , dpm/100 sq. cm. Radiation Mean Maximum N Beta -1 13 62 File name for this graph: RBTROSB .EPS , r Figure A-109 Removable Beta Survey Results of Basement Trenches O
" " " " * " "" Page 113 of 163 REVISION 9
, .,,c -. ., - - -, , ,
i
- APPENDIX A .,
i O Bldg 100 Basement Structures ! 1 Beta Removable Contamination 1000 i Beto @m/ B00 ; e - 1 1 4 2e : g O " - -^= = = =---^^ ~ - - ^ ~ ~
-200 i .
i . i . i i i . i i i 7051 7051 7051 7051 , sunw uceron Fh Nunter O 3/24/93 11:03 am Beta Radiation Statistical Summary. for ' Bldg.100 Basement Structures dpm/100 sq. cm. Radiation Mean Maximum N i Beta -3 11 15 File name for this graph: RBOOSSB .EPS I Figure A-110 Removable Beta Survey Results of Basement Structures 0
""""#*" *8 Page 114 of 163 REVISION 8 1
i i
.. .~.
/
APPENDIX A P O V Bldg 100 Basement NW -Quad. Walls , Beta Removable Contamination i 1000 Beta cbm/ 800 i 400 5 f 0 - - '
.i
-200, ,- , , ,- ,- _ , ,
M M M - D1 y ggg gg 7013 Surwy Locatbn Fh Number 3/24/93 Beta Radiation Statistical Summary 11:04 am for Bldg 100 Basement NW Quad. Walls dpm/100 sq. cm. i Radiation Mean Maximum N Beta 0 13 254 i File name for this graph: RBNWWSB .EPS I i Figure A-111 Removable Beta Survey Results of Basement NW Quadrant Wall O
""" "* """ Page 115 of 163 REVISION 6
APPENDIX A () f- s Bldg 100 Basement NE Quad. Walls Beta Removable Contamination 1000 Beto dpm/ 800 e R
? -
4 200 a 0 '- --
- -- = -^ ^ - :-
-200, , , ., , c- , ,--
3856 3857 5983 7001 Surwy Lo:dJcn Fh it.smber O Beta Radiation Statistical Summary C/ 3/24/93 for 11:04 am Bldg 100 Basement NE Quad. Walls dpm/100 sq. cm. Radiation Mean Maximum N Beta -1 17 192 File name for this graph: RBNEWSB .EPS Figure A-112 Removable Beta Survey Results of Basement NE Quadrant Wall s)
""""""#" Page 116 of 163 REVISION 0
APPENDIX A . t O Bldg 100 Basement SW Quad. Walls i Beta Removable Contamination : P 1000 Beto ctm/ 800 000 8 - ' 1 t 1
- ^^ -- - '
0 e-
-200, , - - - - , , , , , ,
7048 7281 7283 7404 , Suney Locaticn Fb Number i 3/24/93 Beta Radiatien Statistical Summary 11:06 am for Bldg 100 Basement SW Quad. Walls dpm/100 sq. cm. Radiation Mean Maximum N , Beta 1 20 262 File name for this graph: RBSWWSB .EPS . i Figure A-113 Removable Beta Surcey Results of Basement SW Quadrant Wall O l
" " " " * ** "3* Page 117 of 163 REVISION 0 .
t APPENDIX A l
' Bldg 100 Basement SE Quad. Walls Beta Removable Contamination- i 1000 Beb dpm/
800 { g 600 5 , O 400 3 s ; o
-200, , , , , , , ,
5828 5828 5845 5859 , 5828 5828 5846 5901 - Suney Ln:ctbn Fh Number e O 3/24/93 11:05 am Beta Radiation Statistical Summary for i Bldg 100 Basement SE Quad. Walls { j e dpm/100 sq. cm. i I Radiation Mean Maximum N Beta -1 13 190 File name for this graph: RBSEWSB .EPS i i
?
I Figure A-114 i Removable Beta Survey Results of Basement SE Quadrant Wall { O ,
" " " "*"" Page 118 of 163 REVISION 9 '
APPENDIX A 1 O Bldg 100 Basement Electrical Pen. Beta Removable Contamination 1000 Beta ctm/ 800 i b ECO bl i O 400 3 E - o _ _ _ _ _ _ _ _ - - - - -_______ __ _________ I
~
-200 iiiiiiiiiiiiiiiiiiiiiiiiiiiii iiiii 7097 7097 7097 7097 7097 ,
7097 7097 7097 7097 i Suney Locatbn Fle Number O 3/24/93 10:59 am Beta Radiation Statistical Summary for . Bldg 100 Basement Electrical Pen. i dpm/100 sq. cm. Radiation Mean Maximum N [ Beta -1 11 35 ' File name for this graph: RBEPPSB .EPS 3 i Figure A-115 Removable Beta Survey Results of Basement Electrical Penetrations , i
"**"" """ Page 119 of 163 REVISION 8 t - , -r -- . _
APPENDIX A. ! a O Bldg 100 Basement Piping Penet ; Beta Removable Contamination 1000 E , Beta ctrn/ i 800 6 000 t ST 8 400 m 200 ; f e
--~~- ' -
0
-200 i .uuu. u . .u i .u ..u .u .. u i u m iu uu .a . iu .. u .u .. . .ui o u. . u. . .u ui u. . u u uu . i. u. u .. uu .u i u . ."
7371 7381 7386 7387 . 7371 7381 7387 7388 Surey Lccatkn Fle Number 3/24/93 Beta Radiation Statistical Summary for '! 10:59 am Bldg 100 Basement Piping Penet. , dpm/100 sq. cm. Radiation Mean Maximum N Beta -0 20 119 File name for this graph: RBPPPSB .EPS i i 1 l Figure A-ll6 l Removable Beta Survey Results of Basement Piping Penetrations l O l
\
" " " " # " '#8 Page 120 of 163 REVISION 9 P - - - -
APPENDIX A O Bldg 100 Basement Ceiling Beta Removable Contamination ' . 1000 Beto ct:m/ - b 600 400 1 200 h 0
-200 p > > . . y . . . . . . p . . r ! r . . . . . . q i . . . . . . p i r i s i i p . . . p . .
7064 7095 7382 7383 7084 7vad 7382 7383 Surwy Locatbn Fh Number , 3/24/93 Beta Radiation Statistical Summary 10:57 am for ! Bldg 100 Basement Ceiling dpm/100 sq. cm. l Radiation Mean Maximum N Beta 0 15 67 .,
'l i
File name for this graph: RB00CSB .EPS l I l Figure A-117 Removable Beta Survey Results of Basement Ceiling O
" " " * * * " " Page 121 of 163 REVISION 8
o APPENDIX A ' 4 O Bldg 100 Operating Deck Floor l Beta Removable Contamination 1000 Beta ctm/ 800 4 a 400 1 ,
=
s 0
- ~ ~ - --
- s s &
4 i 7405 7407 7410 7421 Surwy Locat'on Fh tirrber ; M 3/24/93 Beta Radiation Statistical Summary 11:11 am for Bldg 100 Operating Deck Floor dpm/100 sq. cm. Radiation Mean Maximum N Lata 0 16 432 , File name for this graph: ROF0FSB .EPS 5 Figure A-118 Removable Beta Survey Results of Operating Deck Floor i
" " " " " " " " Page 122 of 163 REVISION 8
APPENDIX A ,~ v~ Bldg 100 Basement Stairwell One Beta Removable Contamination 1000 Beto ctm/ 800 b 600 bi kE 400 e
- ^= --
0
~ ~
-200 p n.o u n ou suo uo nn u pi ou uo oopuuniun o pi" .oinio r" u u . o ipi no"" .cp 7070 7071 7071 7072 7070 7071 7072 7072 Suney Locatm Fle Number
- 3/24/93 Beta Radiation Statistical Summary 11:09 am for Bldg 100 Basement Stairwell One dpm/100 sq. cm.
Radiation Mean Maximum N Beta -0 13 107 File name for this graph: RBSOOSB .EPS Figure A-119 e Removable Beta Survey Results of Stairwell One
"*"""* """ Page 123 of 163 REVISION 8
l APPENDIX A l l O Bldg 100 Basement Stairwell Two j Beta Removable Contamination . g Beta ctm/ 800
$ 600 5T O 400 I
s 0 - - - - -
-200 . . oi .. o i o oi.. o o o. omgmnn. . . .. .i. . . o .o .o .. .i . .o u . o . . oi. . " . . . ..o oj u . o u. oi . . ..
7218 7219 7219 7221 7218 7219 7220 7221 Surwy Lrrot'on Fh tA.mber 3/24/93 Beta Radiation Statistical Summary 11:09 am for Bldg 100 Basement Stairwell Two dpm/100 sq. cm. Radiation Mean Maximum N Beta 1 18 110 File name for this graph: RBSTOSB .EPS Figure A-120 q Removable Beta Survey Results of Stairwell Two V
" " *""""" Page 124 of 163 REVISION 8
APPENDIX A I l O Bldg 100 Operating Deck Airlock 1 -l l Beta Removable Contamination l l 1000 ( Beta @m/ ! 800 i
$ 600 :
i 5T 8
- 400
- j. 200 l i
0
-200 p o . . . . . . . m p o . . u. . . . . p o . u i u . . . . p . .. n . . n . . r i . . . . . . " .p i . . " . . " . c o . . o n n i p i n o 7424 7424 7425 7425 7424 7425 7425 7425 ;
Strwy Locatkn Fle Number 3/24/93 Beta Radiation Statistical Summary f 11:16 am for : Bldg 100 Operating Deck Airlock i dpm/100 sq. cm. , Radiation Mean Maximum N : Beta 1 18 105 , t I File name for this graph: ROAOOSB .EPS-l r i Figure A-121 Removable Beta Survey Results of Airlock One . O
" " " " " Page 125 of 163 REVISION 8 I
APPENDIX A c id Bldg 100 Operating Deck Airlock 2 Beta Removable Contamination . uxo Beta ctm/ 800 000 g k 400 4 8 9
-200 p " " i " " " . p i " " i " " " p i i n " " . " > p i " " . . " q " i n i" " ' p o s "" " " 'p " " " " " > p 7423 7423 7423 7423 7423 7423 7423 7423 Suney Locat'en Fh Numbcr r'
(
\ 3/24/93 Beta Radiation Statistical Summary 11:16 am for Bldg 100 Operating Deck Airlock 2 dpm/100 sq. cm.
Radiation Mean Maximum N Beta 1 18 100 File name for this graph: ROATOSB .EPS l l Figure A-122 Removable Beta Survey Results of Airlock Two l
'V l l
1
" " * * * * " " Page 126 of 163 REVISION 9
APPENDIX A O v Bldg 100 Equipment Hatch Beta Removable Contamination 1000 Beto ctrn/ 830 N soo 5I k 400 4 2 a 0 -----
-200 p i . . . . i i i i i , . i i i i . . . p . . . . . . . . . . . . . m . i . . . . . . . , , , , , , ,
7426 7428 7426 7426 7426 7426 7426 747B Suney Lcr:crJon Fle limber 1 ( 3/24/93 Beta Radiation Statistical Summary 11:17 am for Bldg 100 Equipment Hatch . l dpm/100 sq. cm. j 1 Radiation Mean Maximum N Beta -0 16 63 ! l File name for this graph: ROEHOSB .EPS l Figure A-123 Removable Beta Survey Results of Equipment Hatch
" " * **"" Page 127 of 163 REVISION 0
APPENDIX A 1 O Bldg 100 Operating Deck Elec. Pen. ; Beta Removable Contamination l 1000 M Beto ctm/ 800
$ om ET 400 4 :
2m g O ___- -
-200 i...i...,...,. .;.. i.. ,.. ,,
7096 7096 7096 7096 7096 709S 7096 7096 Suney Locatin Fh Numba ; 3/24/93 Beta Radiation Statistical Summary 11:12 am for l Bldg 100 Operating Deck Elec. Pen. 2 dpm/100 sq. cm. .'; Radiation Mean Maximum N Beta -0 9 30 File name for this graph: ROEPPSB .EPS I Figure A-124 i Removable Beta Survey Results of Operating Deck Electrical Penetrations
" " " * " " Page 128 of 163 REVISION 9 i
APPENDIX A
~
O Bldg 100 Operating Deck Piping Pen. Beta Removable Contamination . 1000 Beta cbm/ 800 N S a , 400 1 s o _
-200 i ...i...ii.. .i i .i .. i....i...
7415 7415 7415 7415 Suney Lccatbn Fle timber 3/24/93 Beta Radiation Statistical Summary 11:13 am for Bldg 100 Operating Deck Piping Pen. l dpm/100 sq. cm. Radiation Mean Maximum N
-1 Beta 1 10 37 File name for this graph: ROPPPSB .EPS l
4 Figure A-125 Removable Beta Survey Results of Operating Deck Piping Penetrations O
""""""""8 Page 129 of 163 REVISION 9
APPENDIX A (D v Bldg 100 Operating Deck Walls to 2M Beta Removable Contamination 1000 Beto dpm/ 800 g k 400 E e
^
0
-200 r "'"'"'I"
'""r " " '"'l'""mu nmpanm ,3.,,,.. ...,... ....'r' 7007 7007 7008 7008 Surey Locatin Fb Numtw f~
r' 3/24/93 Beta Radiation Statistical Summary 11:15 am for Bldg 100 Operating Deck Walls to 2M dpm/100 sq. cm. Radiation Mean Maximum N Beta -2 9 150 File name for this graph: RO2MWSB .EPS Figure A-126 Removable Beta Survey Results of Operating Deck Wall to 2 Meters onmeN= m Page 130 of 163 REVISION 0
k APPENDIX A E O Bldg 100 Operating Deck Wall >2M - Beta Removable Contamination , 1000 g , Beta ctrn/ 800
$ 600 k 400 5 .
2 2 0 " -
-200 grie: .......i..........i',"'..iiii..i'>ii'i"i>'il'"."i'>i'i'i.i""'i's.'
5905 5906 5906 5909 5905 5906 5906 5969 ; Suney Lccatlm Fb Numtxr O 3/24/93 11:14 am Beta Radiation Statistical Summary for l i, Bldg 100 Operating Deck Wall >2M dpm/100 sq. cm. , i Radiation Mean Maximum N ; Beta -0 13 108 File name for this graph: ROA2WSB .EPS i Figure A-127 Removable Beta Survey Results of Operating Deck Wall > 2 Meters -l t
""*" ""'" Page 131 of 163 REVISION 8 , , , , . , _- - - _. . . _ _ . I
APPENDIX A O Bldg 100 Platforms Beta Removable Contamination - 1000 Beta ctm/ 800 g 400 1 s o_ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _
-200 i i iiiii i i i i i i i i i i .
5968 5968 5968 5968 5968 Suney Locatbn Fh FAmtxr (~ k 3/24/93 Beta Radiation Statistical Summary 11:14 am for Bldg 100 Platforms dpm/100 sq. cm. Radiation Mean Maximum N Beta -0 9 20 ; l Filo name for this graph: ROS60SB .EPS j Figure A-128 Removable Beta Survey Results of Platforms (
" " " * " " " Page 132 of 163 REVISION 0
APPENDIX A [ Bldg 100 Crane Beta Removable Contamination
= sumus, Beta opm/
800
$ reo GT kE 400 11 200 0 ~~~~--~-~~~~--~~~-~~~~~---~~~~~~~~~~~
-200 Tr m . i . . . . i . , , , , , , , , , , , , , , , , i . . . . i . . . . . i . . ,
7277 7277 7277 7277 7277 7277 7277 7277 Strwy Locat'm Fb Number 3/24/93 Beta Radiation Statistical Summary 11:11 am for Bldg 100 Crane dpm/100 sq. cm. Radiation Mean Maximum N Beta 3 18 46 File name for this graph: BDCROSB .EPS Figure A-129 Removable Beta Survey Results of Crane
" " " " " ' * * " " Page 133 of 163 REVISION 0
APPENDIX A Bldg 100 Contninment Dome Beta Removable Contamination l 1000 ; Beto @m/ , 800 , t
$ mo ,
5f 8 e h j
-p 200 c5
=
0 -
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7064 7065 7093 711 5 , 7064 7065 711 5 711 5 Suncy Locatkn Fle Number O 3/24/93 11:10 am Beta Radiation Statistical Summary for Bldg 100 Containment Dome j i dpm/100 sq. cm.
}
Radiation Mean Maximum N Beta -1 12 152 , File name for this graph: RDCDOSB .EPS
.i L
Figure A-130 : Removable Beta Survey Results of Containment Dome :
" " ****"" Page 134 of 163 REVISION 6 - , -. - , - . . - , , - . . - , . , , r.o-- .
APPENDIX A; ; O Bldg 100 Yard Exhaust Stack Pad Beta Removable Contamination. 1000 Beto cbm/ 800 i 600 a b 400 3 200 - f , o - -__ - - ~ = _ _.
~2 giIa I i3giiII BtI ga4ieieIl>3iE III l1 43 IIItgI 11 IIIeg34 I3 Ii ajisa 7561 7561 7561 7561 7561 7581 7561 7561 Suney Locat'on Fh Number n
O 3/24/93 11:18 am Beta Radiation Statistical Summary for i Bldg 100 Yard Exhaust Stack Pad dpm/100 sq. cm. ; Radiation Mean Maximum N Beta -1 11 60 File name for this graph: RYSPOSB .EPS I i b Figure A-131 Removable Beta Survey Results of Exhaust Stack Pad ;
* * * " " " " Page 135 of 163 REVISION 0 ;
i r
APPENDIX A i O Bldg 100, Basement, NW Quad. Floor ; l Gamma Radiation at 1 Meter 35 rmm ; uR/hr ; 30 25 i
)
20 ! 2
~
15
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$100 $100 b10000F Surwy Mecanment Lecat'en Ccrias 1 l
O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:28 am for Bldg 100, Basement, NW Quad. Floor uR/hr 99% Confidence Level Observed Background Max Value Maximum N Radiation Mean Gamma 13.6 14.9 14.5 135 i File Name for this graph: RBNWFG .EPS Figure A-132 Gamma Radiation Results of Basement NW Quadrant Floor O
"" " ""*"" Page 136 of 163 REVISION 8
i APPENDIX A i Bld.g 100, Basement, NE Quad. Floor Gamma Radiation at 1 Meter V/////J uR N g 25 20 15 - t 10 5 l l 0 .. L e m ; s i n f.- l . L.1 i, . u
. .j '
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OO20000F01 0020000F01 wztuu 01 wzuuutt 01 vv20000F01 N 01 OtT20uuTO1 Surwy Memunement LeedJen Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:24 am for Bldg 100, Basement, NE Quad. Floor uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 13.5 15.6 16.1 129 File Name for this graph: RBNEFG .EPS Figure A-133 Gamma Radiation Results of Basement NE Quadrant Floor
""* ** """ Page 137 of 163 REVISION 8
APPENDIX A O Bldg 100, Basement, SW Quad. Floor Gamma Radiation at 1 Meter V/////1 uR/hr 30 25 20 4
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Surwy Memurernent trcaikn Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:31 am for Bldg 100, Basement, SW Quad. Floor uR/hr 99% Confidence Level Observed Background Max Value Maximum N Radiation Mean 16.2 17.5 135 Gamma 13.9 File Name for this graph: RBSWFG .EPS i Figure A-134 i Gamma Radiation Results of Basement SW Quadrant Floor j
***""**"#" Page 138 of 163 REVISION 9 i
APPENDIX A O Bldg 100, Basement, SE Quad. Floor Gamma Radiation at 1 Meter f V/////1 uR/hr 30 25 - 20 l
' 71
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003OOOOF01 M N O1 003OOOOF01 OCL'OOOOF01 0030000F01 OCL N O1 003OOOOF01 Suney Mecanment Locatbn Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:30 am for Bldg 100, Basement, SE Quad. Floor uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.8 17.5 17.5 129 File Name for this graph: RBSEFG .EPS 4 Figure A-135 Gamma Radiation Results of Basement SE Quadrant Floor 1 O
"**"""* Page 139 of 163 REVISION 8
APPENDIX A Bldg 100, Basement, Gamma Well t Gamma Radiation at 1 Meter , V/////l ' BM 30 25 t 20 s 15 - - . , t 39 _ s
~
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., i rrerON02 00eru XaV02 Surey Mecourement Locatbn Codes L O 3/24/93 Gamma uR/hr Measurement Statistical Summary + 10:22 am for Bldg 100, Basement,_ Gamma Well uR/hr 99% Confidence Level ' Observed Radiation Mean Background Max Value . Maximum N , t 13.5 15.9 14.6 8 Gamma File Name for this graph: RBGWOG .EPS , I Figure A-136 Gamma Radiation Results of Basement Gamma Well O
" *
- 8 " 883* Page 140 of 163 REVISION 8
APPENDIX A O Bldg 100, Basement, Sump Gamma Radiation at 1 Meter V/////1 WM 25 w 20 0 30000S 30000S 1 0030000S01 Suncy Masurement La:ctbn Code O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:34 am for Bldg 100, Basement, Sump uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 15.2 17.3 16.0 6 File Name for this graph: RBSUOG .EPS Figure A-137 Gamma Radiation Results of Basement Sump b a a30 93-runerivwatxwis.an Page 141 of 163 REVISION 9
4 APPENDIX A O Bldg 100, Basernent, Drains Gamrna Radiation at 1 Meter 35 V/////1 g 25 20 4 Edr: .;p;,r[ y .'7 ;
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o . o r. O p i i . o ..< i p o n i o i r o l o n i p . n o o i j i n . l o . q u o . < o q l 0050000DAO 00500300A0 0050000DHO 005000000 pmemAO 00500000D0 fYNO Surwy Memumment Locat'en Ccdes i' 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:27 am for Bldg 100, Basement, Drains uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum .N 13.3 16.6 15.8 68 Gamma File Name for this graph: RB00DG .EPS Figure A-138 Gamma Radiation Results of Basement Drains O
" ' " " " " "" Page 142 of 163 REVISION 9
APPENDIX A O Bldg 100, Basement, Trenches Gamma Radiation at 1 Meter . 35 V/////J uR/hr 30 25 20 ---
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0050000DAO 00500000A0 0050000DFO 00500000HO 0050000DAO 00500000C0 N Surwy Meaurment Loccikn Ccdes n 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:35 am for Bldg 100, Basement, Trenches . uR/hr 99% Confidence Level Observed 1 Background Max Value Maximum N Radiation Mean l 13.6 15.9 15.8 63 l Gamma ; File Name for this graph: RBTROG .EPS 1 l l l Figure A-139 Gamma Radiation Results of Basement Trenches x OM293-PUB'4MRXWii.RD Page 143 of 163 REVISION 8 l
APPENDIX A s~ Bldg 100, Basement, Structures t 1 Gamma Radiation at 1 Meter 35 V////A ' w BM 25 20 P 15 ed n e :',' ' '
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0010000S01 0010000SC6 0010000S11 Ou2000050i ! 0010000S03 0010000S08 00100COS13 Surwy Mem.rement Locaron Ccris i 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:26 am for Bldg 100, Basement, Structures uR/hr ; 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N i Gamma 14.3 16.5 18.4 70 File Name for this graph: RB00SG .EPS Figure A-140 Gamma Radiation Results of Basement Structures
"*3"*""" Page 144 of 163 REVISION 8 ;
i APPENDIX A O Bldg 100, Basement, NW Quad. Wall Gamma Radiation at 1 Meter V/////1 30l' 25 l' ! 20 15 10 5 -
.. : ; " al O ;
0010000WO1 0010CDOWO1 0010000WO2 0010000WO4 l
~
0010000WO1 0010000VO 001000CWO3 o n Co&s Suney Mecsurement Locat' O 3/24/93 Gamma uR/hc Measurement Statistical Summary 10:29 am for Bldg 100, Basement, NW Quad. Wall uR/hr
- i 99% Confidence Level Observed r Radiation Mean Background Max Value Maximum N Gamma 13.3 15.8 15.1 192 File Name for this graph: RBNWWG .EPS i f
Figure A-141 l Gamma Radiation Results of Basement NW Quadrant Wall
"'*" " "'* Page 145 of 163 REVISION 6
l APPENDIX A lO Bldg 100, Basement, NE Quad. Wall Gamma Radiation at 1 Meter V////A l uR/hr g l
'"I 20 15 i.
e . l' 10 f.o i [. [ t o h h n I fd t'
/
i l 1 5 9[ h.. f h e b i-il L i 4 [ i O 00xwuwo4 002uc00wo3 0020000wo1 Our0000WOB rmerrrwo3 0020000WOS 0020000wo2 Survey Mecnranent LocdJrn Ccrbs l . O 3/24/93 Gamma uR/hr Measurement Statistical Summary f 10:26 am for Bldg 100, Basement, NE Quad. Wall i uR/hr i 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 13.6 16.1 16.0 286 4 J File Name for this graph: RBNEWG .EPS l 1 i Figure A-142 Gamma Radiation Results of Basement NE Quadrant Wall l i
"** "*""" Page 146 of 163 REVISION 0 1
a
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APPENDIX A O Bldg 100, Basement, SW Quad. Wall Gamma Radiation at 1 Meter l V/////J l g l i uR/hr 25 20 t 15 - - '- # . I l 10 5.' O EU' ; ' l' - l' -
".~~
""eAmmet""e6% ,2yxx,g-nyo3 Sumey Memoriment tzcation Cochs O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:32 am for Bldg 100, Basement, SW Quad. Wall uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.0 16.6 16.5 191 File Name for this graph: RBSWWG .EPS Figure A-143 Gamma Radiation Results of Basement SW Quadrant Wall O .
""'3""*"" Page 147 of 163 REVISION 9
APPENDIX A l O Bldg 100, Basement, SE Quad. Wall G-amma Radiation at 1 Meter V/////1 l uR/hr 30 25 20 1 ' ' - - ' - - -' 15 er-10 l , fll (i!a' i l i : {fh1 ) i (!)Ijlll;iafLlllllI: 5 0 ii
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ob 00 6 09 Surwy Manurernent Loco' m Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:30 am for l Bldg 100, Basement, SE Quad. Wall I uR/hr 99% Confidence Level Observed , Radiation Mean Background Max Value Maximum N Gamma 14.4 18.2 18.7 263 File Name for this graph: RBSEWG .EPS i l 5 Figure A-144 Gamma Radiation Results of Basement SE Quadrant Wall i
""* """"" Page 148 of 163 REVISION 8 i
APPENDIX A O Bldg 100, Basement, Ceiling Gamma Radiation at 1 Meter V/////] y BN 25 20 15 m ' i,i
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" " " * * *
- Page 149 of 163 - REVISION 8 I
APPENDIX A n
\"J Bldg 100, Operating Deck, NW Floor Gamma Radiation at 1 Meter V/////]
BM y 25 20 4 15 10 ; "I 9 , S i l O po.uoo.o.JN! p u...ou..q.aoa o uip.o ou o iu nauar o...n o.u.r o o o . .. 0011000F01 0011000F01 0011000F01 OO11000F01 0011000F01 0011000F01 0011000F01 Suney Mecrurement Locatkn Codes 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:40 am for Bldg 100, Operating Deck, NW Floor uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 10.8 12.4 12.5 102 File Name for this graph: ROFIFG .EPS Figure A-146 Gamma Radiation Results of Operating Deck NW Quadrant Floor
" " " " " " Page 150 of 163 REVISION 9 i i
APPENDIX A O Bldg 100, Operating Deck, NE Floor Gamma Radiation at 1 Meter V/////1 BM y 25 20 4 15
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m OO11000F02 OO11000F02 00110 XF02 0011000F02 OO11000F02 OO11000F02 OO11000F02 Surwy Memuremmt Loxst'm Codes O 3/24/93 Gamma uR/hr Measurement. Statistical Summary 10:41 am for Bldg 100, Operating Deck, NE Floor uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 11.4 12.1 12.3 101 File Name for this graph: ROF2FG .EPS Figure A-147 Gamma Radiation Results of Operating Deck NE Quadrant Floor
" " "**"" Page 151 of 163 REVISION 8
APPENDIX A ('N r 4 Bldg 100, Operating Deck, SW Floor Gamma Radiation at 1 Meter s V/////1 g uR/hr 25 20 15
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" " " " * "
- Page 152 or 163 REVISION 8
APPENDIX A-O Bldg 100, Operating Deck, SE Floor Gamma Radiation at 1 Meter V/////l 1 i uR/hr 30 25 - 20 15 10 T 5 h i- im '. 0p A . .li j
'l at I .
.ll "o .li i-L
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4 0011000F03 ' 0011000F03 0011000F03 0011000F03 0011000F03 0011000F03 0011000F03 Suney Mensement LocdJon Ccdes l O 3/24/93 Gamma uR/hr Measurement Statistical' Summary i 10:42 am for j Bldg 100, Operating Deck, SE Floor uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N 11.0 12.7 12.6 103 Gamma File Name for this graph: ROF3FG .EPS Figure A-149 Gamma Radiation Results of Operating Deck SE Quadrant Floor
" " " " " " " Page 153 of 163 REVISION 9
APPENDIX A O' Bldg 100, Basement, Stairwell One Gamma Radiation at 1 Meter
- V/////J WM 25 15 ,r.i'.r, '
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0070SW1C01 0070SW1WO1 0070SW1WO2 0070SW1WO3 0070SW1F01 0070SW1WO1 0070SW1WO3 Suney Metrurement Locat'on Cc&s O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:33 am for Bldg 100, Basement, Stairwell One uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 13.1 14.3 14.5 107 File Name for this graph: RBSOOG .EPS Figure A-150 J Gamma Radiation Results of Stairwell One l
" * " " " " " Page 154 of 163 REVISION 9
APPENDIX A i O ' Bldg 100, Basement, Stairwell Two 1 Gamma Radiation at 1 Meter i V/////]
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l 25 23 j
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0070SW2F01 0070SW2WO1 0070SW2WO2 0070SW"2WO3 0070SW2f'01 0070SW2WD1 0070SW2WO3 Sursey Memurement LocatJcn Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:34 am for Bldg 100, Basement, Stairwell Two uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N ., 1 l Gamma 13.4 16.0 16.3 111 ! l File Name for this graph: RBSTOG .EPS ; l l l I Figure A-151 Gamma Radiation Results of Stairwell Two
-.O-
""-""""*""" Page 155 of 163 REVISION 8 l
APPENDIX A O" Bldg 100, Operating Deck, Airlock 1 Gamma Radiation at 1 Meter 25 V/////l y SN 25 20 - 15 10 l: ' r
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I,.yi.,. "p,j.[,,,, ,.4. i,a,5' i " 5( f: ' , , , , O F.o.uounop ioonoom p Loouuo...p..".u o.u.p.io'o. ".uv o ...u o.. .p o o o o.: OO21AL1CL1 OO21AL1F01 OO21AL1WD1 OO21AL1VC5 OO21AL1C01 OO21AL1F01 OO21AL1WO4 Suney Meraservet Locatin Codes (N \ 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:37 am for Bldg 100, Operating Deck, Airlock 1 uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 7.3 10.0 12.1 108 File Name for this graph: ROAOOG .EPS Figure A-152 Gamma Radiation Results of Airlock One w MB MMMM.R0 Page 156 of 163 IEVISION 0
APPENDIX A ' O Bldg 100, Operating Deck, Airlock 2 Gamma Radiation at 1 Meter ; i V/////1 y @M 25 20 4 15 10
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""""""* Page 157 of 163 REVISION 9
APPENDIX A O Bldg 100, Equipment Hatch Gamma Radiation at 1 Meter 3s V/////] uR & g 25 20
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" " " " " " " " Page 158 of 163 REVISION 8 1
l
APPENDIX A - Bldg 100, Operating Deck Wall to 2M Gamma Radiation at 1 Meter V/////J uR/hr 30 - ,, 25 20 15 5 I l l l lII _ I l I i l 0v . . , , . - i - l Wil.lhlI!uII 11000WO1 0011000WO 0011000Wg 1000Wg Suney Memunement Lccatbn Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary . 10:43 am for Bldg 100, Operating Deck Wall to 2M uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 11.0 12.6 12.7 150 File Name for this graph: RO2MWG .EPS Figure A-155 g Gamma Radiation Results of Operating Deck Wall to 2 Meters
%)
" " " ' * * * " " Page 159 of 163 REVISION 8
APPENDIX A O Bldg 100, Operating Deck, Wall > 2M 1 Gamma Radiation at 1 Meter i l V/////] ea ~ l m 1 20 15 ; 10
-l l" 5 g ; ; j s I .........,....i..........,e.......,....,...E...
Oc.m,m......,...............,..............,. . 0011000WO1 0011000WO1 0011000WO1 0011000WA1 0011000WO1 0011000WO1 OO11000WAl Suney Memurement Lccat'on Codes O 3/24/93 Gamma uR/hr Measurement Statistical Summary i 10:44 am for Bldg 100, Operating Deck, Wall > 2M uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 11.0 12.5 12.7 114 File Name for this graph: ROA2WG .EPS Figure A-156 Gamma Radiation Results of Operating Deck Wall > 2 Meters O
" " """"" Page 160 of 163 REVISION 9
APPENDIX A-3 Bldg 100, Crane Gamma Radiation at 1 Meter 35 V/////1 uR/hr 30 20 8 15 10 0 ii...i.i',i..i..iiq.i'iii,,i...i,c.3.i.,i i [ - b l - 0012000501 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 0012000S01 Surwy Memurement Location Codes 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:37 am for Bldg 100, Crane 1 uR/hr 99% Confidence Level Observed Background Max Value Maximum N Radiation Mean 4.9 6.7 6.3 46 Gamma , 1 File Name for this graph: RDCROG .EPS , i i Figure A-157 Gamma Radiation Results of Crane , O. e
" " ' " " " " " Page 161 of 163 REVISION 8
. . . , , . _ _ . . . . _ , - - . , .-em , m ,e-. -
p
APPENDIX A bw Bldg 100, Containment Dome Gamma Radiation at 1 Meter V/////l
@N y
25 20 4 15 10 5
- h , ; m.
. I~ d" . ,. ..~..r . . .I. .-l . .
0 . - Oh2000CD1 0012000h 12000 Surwy Memurement Locaibn Corts b v Gamma uR/hr Measurement Statistical Summary 3/24/93 for 10:36 am Bldg 100, Containment Dome uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 4.1 5.3 5.1 151 File Name for this graph: RDCDOG .EPS l Figure A-158 1 Gamma Radiation Results of Containment Dome O
" ' " " " " " " " Page 162 of 163 REVISION 8'
- . = l l APPENDIX A l i
~I
.i l
O I l G Bldg 100, Yard, Exhaust Stack Pad ; Gamma Radiation at 1 Meter V/////J m l 25 w 20 Lr, r, 15 7;=if
.. Pr,f. r o
g, t;fr ;r.;':r, fip, lF,%J; p L;F,, [M;'
' E fCy* v *;Il L
.;r;;7[L rf[. [r,p ;L(( Lrp ,;r;r ,r;t r *' a ;" r[ELTE
.r ;rp; p[ -
.['r r ;;riF f
." ^
10 fr![-[rpiff:'ri lU:r!L -@L r; -er ritL. " .r r r -7;~ lti EI r :!It - FL O 3r b[ rL ,
;r-r
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p prLe r
- , r , r ');L plt r .H -
-;r srL r -[ -!! r ;-r*
e 5 Er.
- L ;;i; r ;r Yr.
-'p tr LtL LT n LtL r " r c .-t' LI
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- L rl;h[ L l [r L -[p[ Ib y [h[r I[
F 0 i .. .. i3 p . . . . . p ;. . o i i . f.......iii.....i.o. 0010PO1F01 0010PO1F01 0010PO1WD1 0010PO1WO4 0010P01F01 0010P01F01 0010PO1WO2 Surwy Measurement i enCcn Codes 3/24/93 Gamma uR/hr Measurement Statistical Summary [ 10:51 am for Bldg 100, Yard, Exhaust Stack Pad uR/hr I 99% Confidence-Level Observed Radiation Mean Background Max Value Maximum N Gamma 15.4 18.1 18.0 60 File Name for this graph: RYSP0G .EPS r Figure A-159 Gamma Radiation Results of Exhaust Stack Pad \
""""" ## REVISION 9 Page 163 of 163
1 7 O A.PPENDIX B REACTOR YARD SOIL SAMPLES O
I
- APPENDIX B
-)
O l
'J 1
APPENDIX B O REACTOR YARD SOIL SAMPLES- . I l l l l 1 O d 03089xrtra'smrmaxso25.no REVISION 0
=i i
APPENDIX B APPENDIX B Reactor Yard Soil Samples There were three pits or trenches and five mounds of excavated soil in the reactor yard. A rundom 50% of the 1 x 1 meter grids of these eight areas were sampled. Direct alpha and beta radiation measurements and gamma radiation at one meter were taken prior to sampling. Surface samples were taken in the pits, and subsurface samples at l' and 3' were taken from the mounds. The samples were ar.alyzed for gross alpha and beta activity, and gamma spectroscopy was performed for nuclide identification and activity in pCi/g. 14 ucliddlMI5KsTs^rsy55enI&ll ifihb~61hf[formj fdimfs(s5Eidsdjamiisi ipscIfoshohy)1DX75@H2 This table also lists all nuslides in'thsLH20/Siudgslibrary;used for all[s~oiljsamplesi Graphs like those in Appendix A present the direct radiation results. Gross alpha and beta, and gamma isotopic results are in tables. Samples are identified by their unique 4-digit number and their location code. The location code was determined as follows:
- type of sample (OD = subsurface, OU = surface)
- depth (1 = 1', 2 = surface, 3 = 3')
- survey area (000 = area 0,001 = area 1,002 = area 2)
O, a survey unit (0 = pipechase, A = hole or mound A, B = hole or mound B)
- grid location (e.g., A01 = grid A1) mmrumstrentuwaraurwnso37 Page 1 of 48 REVISION 1
APPENDIX B l A ~'** V vosat un
~
tycn;D met Anauga arTTrar ar.4 TRtts pf R U CToa l . TARa wirs r w :c AREA 0 ~~~
..=,.,,,%
ncavATED c:ar uma m It71 8 l tremten tem FJ 7 :=a "
- n= = m
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AREA 1
.ana un
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m _ . , _
.e W ~
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- N
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'N0ftTH BEACON STPECT
~%
AREA MAP OF REACTOR YARD
, ,,,. e - SHOWING EXCAVATED TRENCHES AND DIRT PILES Figure B-1 Reactor Yard O
s_/ on92 nnnsmrxrmm5n Page 2 of 4g REVISION 0
APPENDIX B D d Bldg 100, Yard Area 0, Dirt Mound A Gamma Radiation at 1 Meter 35 V/////J uR/hr 3g 1 25 20 75 ~' n,? _i ' m r:
~
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ODOOOOAF01 ODOOOOAF01 ODOOOOAF01 CDOOOOAF01 CDOOOOAF01 CDOOOOAF01 COOOOOAF01 Surwy M&surement LocdJtn Codes p 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:46 am for Bldg 100, Yard Area 0, Dirt Mound A uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 12.9 14.6 14.1 28 File Name for this graph: RYOARG .EPS , Figure B-2 Area 0 Mound A Gamma Radiation Results O 030993-PUB'. SIT'JW,RX\025." Page 3 of 48 REVISION 0
l APPENDIX B i,
)
Bldg 100, . Yard, Pipe Chase Trench . a i Gamrna Radiation at 1 Meter l 1 i i 35 V/////J -1 I uR M - 30 4 25 ~ i 20 I 7 b '? , -[ 15
- 'r V
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D uiniiiiniaisiitu. COOPCHOF01 DOOPCHOF01 OOOPCHOF01 OOOPCHOF01 OOOPCHOF01 OOOPCHOF01 OOOPCHOF01 Suney Measurement Locatbn h
.r 3/24/93 Gamma uR/hr Measurement Statistical Summary for :
10:50 am 1 2 Eldg 100, Yard, Pipe Chase Trench , 5 uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.0 16.8 16.5 64 File Name for this graph: RYPCRG .EPS Figure B-3 Area O Pipechase Gamma Radiation Results :
'"3""""2* Page 4 of 48 REVISION 0 t
-w- , ,--- -, . - , - - y
APPENDIX B
.i ' Bldg 100, Yard Area 1, Dirt Mound A Gamma Radiation at 1 Meter l
V/////l uR/hr 3g . 25 , 1
> 20 h 15 -- ,
eglql '- f:
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e OD0001AF OD0001 AF 1 001AFA1 1AFg Suney Measurement Locatbn Ccdes 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:47 am for Bldg 100, Yard Area 1, Dirt Mound A uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.1 16.6 16.4 165 File Name for this graph: RY1ARG .EPS i Figure B-4 . Area 1 Mound A Gamma Radiation Results , f
" " " " * " " Page 5 of 48 REVISION 0
APPENDIX B O e1ag 100, vara Area 1, oirt uouna e Gamma Radiation at 1 Meter 35 V/////1. uR/hr 30 25 g O d$ . r . i..,l ' > r... i .!
- rrrre H j pl 15 ;-) rF
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t [ 10 [ 4 r , i 5 l I O pn u .uio n.p..i n a. o n.c o.un o n op oc n u o uo p in o oi.n o p un. nu n p u.iin.i u'. ODOOO1BF01 ODOOO1BF01 ODOOO18F01 ODOOO18F01 ODOOO18F01 ODOC018F01 ODOOO18F01 Sursey Mecsurement Lecctbn Ccdrs s- 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:47 am for Bldg 100, Yard Area 1, Dirt Mound B uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximam N Gamma 14.7 18.0 18.0 104 File Name for this graph: RY1BRG .EPS Figure B-5 Area 1 Mound B Gamma Radiation Results O ~ ocertansmrue.xxw25 "" Page 6 of 48 REVISION 0 l l
)
APPENDIX B O Bldg 100, Yard Area 2, Dirt Mound A Gamrna Radiation at 1 Meter 35 V/////) uR/hr 30 25 20 s ?. w 15 . ?? .
?)27 / i- -- 7?
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O ;,,;,.,,l*u ; , ,,;I -**<,;,,,;.& ' s s a ; ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 Suney Mecnnment Locat'rn Ccdes ; s 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:48 am for Bldg 100, Yard Area 2, Dirt Mound A uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 13.8 15.7 15.3 31 i File Name for this graph: RY2ARG .EPS Figure B-6 i Area 2 Mound A Gamma Radiation Results i 1 cun-nnrstraumca" Page 7 of 48 REVISION 0 i j
APPENDIX B n Bldg 100, -Yard Area 2, Dirt Mound B Gamma Radiation at 1 Meter 35 V/////J uR/hr 30 25 20 - 15
- r. - .3'
~r' "
,. r:p-' .'~'," ff' '
- rr 10 ,
;s 5 '
Oiiiioomipi n n n o gi . i i n a i n i o 'u . . o p'o'. dn n ibuiniopou ODOOO2BF01 ODOOO2BF01 ODOOO2BF01 ODOOO2BF01 COOOO2BF01 OOOOO2BF01 CDOOO2BF01 Suney Memuremmt Lccatin r* O 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:49 am for Bldg 100, Yard Area 2, Dirt Mound B uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 11.5 14.6 14.0 72 File Name for this graph: RY2BRG .EPS Figure B-7 l Area 2 Mound B Gamma Radiation Results ! C) \/ l an9nw.struwams.n Page 8 of 48 REVISION 0
APPENDIX B ( r
'- Bldg 100, Yard, Cistern 242 Trench Gamma Radiation at 1 Meter V/////1 1
uR/hr 3g 25 20
' ,h-t f y, 15 'O : ..p f ,,
r
.y r f 10 L
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OUOOO2AF01 OUOOO2AF01 OUOOO2AF01 OUOOO2AF01 OUOOO2AF01 OUOOO2AF01 0U00601 Suney Mecsurement Locat'm Cochs
'~
3/24/93 Gamma uR/hr Measurement Statistical Summary 10:45 am for Bldg 100, Yard, Cistern 242 Trench uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.2 16.5 16.4 90 File Name for this graph: RYCIRG .EPS Figure B-8 Area 2 Cistern 242 Trench Gamma Radiation Results O
'*" " * "
- Page 9 of 48 REVISION 0
APPENDIX B (3 v' Bldg 100 Yard Secondary Sump Trench Gamma Radiation at 1 Meter V/////] uR/hr 30 25 20 15 - - - [ ; ';':l $k;.k [ 5 h f,, ;' .c . '[' , h, .hgl , t'k , ff
- 'h..t _
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F1 OOO2BF F Suney Memurrment Locat'en Ccuts i k 3/24/93 Gamma uR/hr Measurement Statistical Summary 10:50 am for Bldg 100 Yard Secondary Sump Trench uR/hr 99% Confidence Level Observed Radiation Mean Background Max Value Maximum N Gamma 14.2 17.4 17.2 160 File Name for this graph: RYSSRG .EPS Figure B-9 Area 2 Secondary Sump Trench Gamma Radiation Results onn-nsstrm.xxvc3.e# Page 10 of 48 REVISION 0
A.PPENDIX B - TABLE B-1 V REACTOR YARD SOIL SAMPLES AREA 0 MOUND A INST: LB5100#1352 &1362 l K PHA ANALYSESBETA ANALYSES CAL.DUE: 08/18/93 09/23/93 SAMPLE FAASS MDA Activity MDA ACTIVITY NUMBER LOCATION (g) (pCl/g) (pCl/g) (pCilg) (pC1/g) 1423 OD1000AA01 0.103 5.70 8.49 22.70 26.55 1774 OD3000AA01 0.082 13.01 9.07 29.86 67.58 1380 OD1000AA02 0.045 13.05 6.32 51.95 11.92 1777 OD3000AA02 0.086 12.41 3.56 28.47 11.02 1550 OD1000AA03 0.104 0.26 6.13 19.75 30.42 1775 OD3000AA03 0.336 3.18 2.21 7.29 3.56 1424 OD1000AA04 0.076 7.73 12.37 30.76 17.88 1585 OD3000AA04 0.084 12.70 9.63 29.15 21.28 1780 OD1000AA06 0.034 31.38 6.43 72.01 42.06 1428 OD3000AA06 0.245 2.40 6.52 9.54 33.56 1779 OD1000AB01 0.105 10.16 1.46 23.32 -5.11 1382 OD1000AB01(OC) 0.049 16.95 8.93 49.00 -6.20 1770 OD3000AB01 0.028 38.11 81.22 87.44 185.13 1425 OD1000AB04 0.266 2.21 4.69 8.79 31.58 1426 OD3000AB04 0.115 5.11 5.70 20.33 24.87 1381 OD1000AB06 0.063 9.32 6.94 37.10 -2.84 15S4 OD3000AB06 0.159 6.71 8.25 15.40 42.38 1588 OD1000AB07 0.039 27.36 24.67 62.78 85.71 1586 OD3000AB07 0.057 18.72 28.39 42.95 49.23 1553 001000AC01 0.145 7.36 6.64 16.89 39.45 1773 OD3000AC01 0.126 8.47 3.47 19.43 31.21 1551 OD1000AC03 0.027 24.10 11.02 .76.08 19.86 1771 OD3000AC03 0.155 6.88 4.23 15.80 30.33 1552 OD1000AC06 0.090 7.23 8.74 22.82 43.10 1555 OD3000AC06 0.118 9.04 5.56 20.75 46.96 1481 OD1000AC07 0.086 7.57 9.14 23.88 45.73 1427 OD3000AC07 0.207 2.84 4.54 11.29 40.84 1587 OD1000AD01 0.043 24.82 25.43 56.94 80.23 1776 OD3000AD01 0.151 7.07 0.58 16.21 22.85 1484 OD1000AD03 0.069 9.43 9.24 29.77 36.27 1772 OD3000AD03 0.147 7.26 5.50 16.66 75.76 1778 OD1000AD06 0.142 7.51 4.62 17.24 25.55 1554 OD3000AD06 0.049 21.78 19.64 49.97 14.59 O MEAN: 10.89 MEAN: STD.DEV: 37.07 34.85 STD.DEV. 14.26 mwrmnsmurrv.rwmunno35 11 of 48 REVISION 1
' APPENDIX B i TABLE B-2 REACTOR YARD SOIL SAMPLES AREA 0 PIPECHASE INST: LBS100#1352 &1362 ALPHA ANALYSES BETA ANALYSES CAL.DUE: 08/18/93 09/23/93 SAFAPLE FAASS FADA Activity FADA Activity NUfABER LOCATION (g) (pCl/g) (pCl/g) (pCl/g) (pCl/g) 1477 OU20000A01 0.074 10.35 6.80 32.25 72.47 1489 OU20000A02 0.056 11.62 9.11 36.68 27.77 1491 OU20000A04 0.030 21.69 21.25 68.47 17.88-1488 OU20000A05 0.062 10.50 6.85 33.13 30.85 1383 OU20000A07 0.070 7.02 7.18 33.61 19.66 1389 OU20000A08 0.116 5.06 9.43 20.15 42.53 OU20000A09 0.113 5.76 3.20 18.18 34.80 1480 1385 0U20000B01 0.033 17.80 4.64 70.84 -43.33 OU20000B02 0.088 12.13 5.96 27.82 22.34 1781 1387 OU20000807 0.102 5.76 7.93 22.92 41.36 OU20000B09 0.089 6.60 15.48 26.27 25.31 1422 OU20000C01 0.046 14.15 11.09 44.65 14.38 1548 1492 OU20000C04 0.093 7.00 3.88 22.09 34.02 1475 0U20000C05 0.127 6.03 7.92 18.79 14.92 , 1479 OU20000C07 0.233 3.29 2.82 10.24 26.08 1388 OU20000C08 0.033 17.80 4.64 70.84 -3.79 OU20000D03 0,051 20.92 12.86 48.01 1.05 1583 OU20000D04 0.240 3.19 6.65 9.94 41.41 1473 OU20000D05 0.095 11.23 3.22 25.77 33.87 1782 OU20000D07 0.100 6.51 9.99 20.54 32.18 1549 OU20000E02 0.018 59.28 0.00 136.02 -32.77 1581 1582 OU20000F01 0.081 13.17 11.88 30.23 28.03 0U20000F02 0.041 15.87 12.44 50.10 27.90 1546 OU20000F03 0.078 9.82 5.61 30.00 24.29 1474 OU20000F05 0.088 7.40 10.62 23.34 27.22 1547 OU20000F06 0.106 5.54 8.87 22.05 30.33 1421 1545 0U20000F07 0.055 11.83 13.13 37.35 29.?" . 1476 0U20000G01 0.130 5.89 5.55 18.36 26.9:> OU20000H02 0.097 6.71 0.88 21.18 20.27 1486 OU20000G03 0.072 9.04 6.85 28.53 29.05 1487 OU20000G04 0.151 4.31 6.19 13.60 20.12 1490 OU20000G05 0.061 10.67 16.37 33.67 29.30 1543 0U20000G06 0.043 15.13 9.88 47.77 22.45 1485 OU20000H04 0.070 10.94 11.25 34.09 11.75 l 1478 OU20000H05 0.120 5.42 7.79 17.12 26.81 1544 1384 OU20000H06 l O f/EAN: 8.29 FAEAN: 23.05 l STD. DEV: 4 45 STD.DEV: 19.83
~
- cmir:
l 1 oomwmsmwremmamcmes 12 of 48 REVISION 1 j
APPENDIX B TABLE B-3 ACACTOR YARD SOIL SAMPLES AREA 1 MOUND A LhS 100a 1352 und e AFM5 641 A M At M5 l P40 CALDUE D6/1853
#D l5AMPLC MASS MCA Activity MDA ACT1VITY
'N'JM BE R LOCATION (g) (pCit'g) (pCFg) (pCitg) (pCl!g)
Y 5643 CD1001 AA01 0.376 1 77 4 45 4 87 34.38 5662 DD1001 AA32 0.077 7.63 12 31 31 A0 10.06 Sa55 OD1001 AA04 C.212 1 52 6.22 11.77 22 20 5378 OD1001 AB01 0.259 2A3 2.s1 6.70 30.50 5669 OD1001 AB02 0.140 4.20 5.21 17.49 2Bh4 4635 DD1001 AB05 0 166 5.00 3.95 15 11 43.50 4s45 DD1001AC01 0 132 8.29 3.31 19.01 49 70 4803 CD1001 AC02 0.371 1.50 1 63 6.74 29 20 5647 OD100 TACO 3 0 133 242 6 58 18 1s 37.23 1445 DD1001 AC04 0.218 1 48 2.71 11.45 33.04 5211 DD100 TAC 45 0 429 1.73 3 94 5 66 31A7 5645 CD1001 A006 0 475 1.41 2.03 3A5 33 49 45c4 DD1031 AD02 0 457 1.22 1 96 5 47 29 96 4936 OD1001 AD04 C.250 3 32 262 10.04 35.32 5212 DD1001 AE01 0.319 2.33 4 62 722 34.76 4931 DD1001 AE43 0.354 2.35 4.14 7.00 32.32 5115 OD t00t AF03 0220 2 67 6.29 12.07 30.93 5014 OD1001AFD4 2430 0 24 1 46 1.09 20.29 5213 DD1001 AfD5 0525 1 42 2 67 4.63 34.75 5379 OD1001 AG01 0.182 559 2 80 12.37 30.12 5179 DD1001 AG02 0.270 2 48 3.54 4.89 45 90 46>4 ODt001AG03 0.323 1.73 4 13 7.74 34 42 er447 CD1001 AG07 0 221 3,76 4.65 11.35 39.63 4649 OD1001 AH01 0.376 2.21 3 49 6 67 32 04 4874 OD1001AHD4 0.314 1.77 6.82 726 3541 5376 001001 A101 0.159 6 40 3 67 14 16 4272 4607 OD1001A803 0 546 1.02 1.35 4 55 21.40 4802 DD100 t Al07 0.334 1.67 4.65 7 48 34.73 4871 001001 A!!0 0 153 3 64 11.5A 16.34 32.25 5650 DD1001A111 0.205 157 7 15 12 17 29 30 5381 CD1001 Al14 0.201 5 06 5 44 11.21 32.31 5636 OD1001 AJ01 0.388 133 3h4 4.84 stA7 4872 CD1001 AI2 0.148 3.77 9 01 16.89 39.74 5377 001001M06 0.227 4 46 5.78 9 92 41.21 5646 OD1001 AJ10 0.143 2 25 6 72 17 45 2230 5218 OD1001 AJ14 0 461 1.61 1.77 5.27 34 68 f466 035001 AK01 0.105 5 59 8 94 23.32 13.62 g\ 5667 OD1001 AK02 0.123 4.78 10.07 19 91 23.25 4s34 CD1001 AK04 0.192 4.33 4 90 13.07 3947 g
% 5639 CDWtAK06 0.36 1 1 80 2 85 5.20 36.82 5640 001001 AK12 0384 1.15 2 51 3.22 31 53 5145 001001 AK15 0 431 1.36 3 21 6 16 28 92 4&C7 OD1001 ALD1 0.3a7 1.44 1 58 6 46 21.99 5670 DD1001 ALO7 0 110 2.60 5 55 11 86 31 49 5162 001001 ALC0 0.391 131 3 93 6 14 27.58 5065 00 toc 1 AL10 0 182 3 06 5 29 1314 26.29 5208 OD1001 AL12 0.265 2.60 3.08 0 17 3132 5206 OD1001 AL13 0.173 4.29 3 45 14 04 32.10 5654 00100 t AL14 0 186 1.73 8.66 13.41 21.46 5 t50 DD1001 AM01 0 483 1.22 5.13 5 50 34.81 5114 CD1001 AM03 C.131 4 48 12.24 20 28 29.20 5144 DD100 TAM 06 0.231 2.54 2 52 1130 31.00 4o68 OD1001 AM07 0,354 147 5 51 7.06 26.36 5178 OD1001 AM10 0.237 2.63 6 B0 to 13 31.93 5172 DD1001 AM12 0 447 1.50 3 60 6.37 30.68 5169 OD1001 AM13 0.327 2.05 339 7.34 3243 5012 DD1001 AN06 1 535 0.36 0.90 1.70 25.23 4870 DD1001 AN08 0.350 1.59 1.31 7.14 35.55 4943 DD t00l AN10 0$97 1.39 231 4.20 22 56 5149 OD1001 AN12 0.392 1.50 2 96 6.76 3130 5007 OD1001 A001 1.124 0 52 1 61 2.32 30 44 5146 CD1001 AOD3 0.383 133 4.19 6 94 39.39 5143 OD1001 A004 0.257 1 96 9.D8 8 44 38.36 5064 CD100i AOC7 0.237 2 35 6 27 10.82 39.09 5362 0010ct A000 0 164 3 40 5 07 15.35 23.76 5011 OD 1001 AP03 0 962 0 60 2 38 2 60 33.03 5175 OD1001APO4 0 207 3 24 5.32 11 60 3454 5178 OD1001 AP05 0.252 2 66 5.24 0 53 33 10 4910 DD1001 AP06 0.371 1 58 3 54 7h4 39.70 4573 DD1001AP00 0.364 1.53 4 ET 6 87 38 11 1K47 OD1001 ACE 3 0.240 2.25 5.38 10 15 35 17 5015 OD1001 AQ05 1.206 0 49 1.50 2 17 27.03 5177 OD1001 AOO7 0 250 2 68 6 86 9 a0 33.61 5116 OD1001 ACD8 0.267 2.20 6 55 6 95 31.06 MEAN: 4A1 MEAN: 31.20
_ STD DFV: 3 09 $YD DE'V: 7 25 mwnmsmwrwunwumes 13 of 48 REVISION 1 E. _
- - _ .~ .-
- . = . -
APPENDIX B TABLEB3 REACTOR YARD Soll SAMPLES AREA 1 MOUND A (continued) aN51; LB51%e 1352 AJwA AarAL?sE4 MI4 Au.r ais CAL.DUE: 06/18 S 3 a SAMPLE MASS MDA Activity MDA AC71VITY NUMBER LOCATION (g) (pC1/g) (pCl/g) (pcilg) (PCl/g) 5382 033001AA01 0.234 4.25 2.13 e 42 38 65 . k 5181 DD3001AA02 0.361 1A0 4 46 8AS 29.05 5182 CD3301 AA04 0.258 2 A0 - 5.11 0.31 31 87 5663 OD3001 A801 0.096 6.12 9 87 2530 9.17 5651 OD3001AB02 0149 1.29 4.13 10.02 28 A3 4939 OD3001AB05 0.256 3.24 2.56 8 80 33.10 5661 CD3001AC01 0.130 4.52 7.85 16.83 15.71 4912 CD3001ACO2 0.376 4 D4 4 58 S AS 30.01 5214 033001 AC03 0.264 2 62 3.39 6.55 31A3 566L OD33 MAD 04 0.089 6.60 9.10 27.51 4.02 4601 DD3331 AC05 0.340 1A4 5.21 - 7.35 40.59 4913 003001AC06 0.268 2 19 7.07 8.75 35.39 4648 033001AD02 0.304 2.73 2.16 8.25 29.53 Sc37 OD3001AD04 0 450 1 49 4.08 4.17 34.84 5638 OD3001AE01 0.673 0 77 1 86 2.15 27.03 5380 DD3001AE03 0.325 3 13 2 02 033 23.27 4649 OD3001AF03 0.146 5.69 4D4 17.18 33.06 4936 OD3001AF04 0.815 1.02 1.26 3.06 23 12 5634 OD3001AF05 0375 1 18 1.52 3.27 31.21 5652 003001AG01 0.119 230 12.31 20.97 25D9 4805 OD3001 AG02 0.146 3.82 4.10 17.12 41.14 4600 OD3001AG03 0.24 1 2.31 4.36 10.37 27.37 5013 DD3001AG07 1.683 0.31 1.30 1.30 24.34 4933 CD3001AH01 0.193 4.30 2.27 13.00 29.0'1 5650 003 Col AH04 0.076 7J3 13 43 32 22 3.14 5166 OD3301A101 0.302 2.22 3.64 7A5 40 45 Se53 DDxotAm3 0.265 1.21 4.70 8 42 30.35 5649 OD3001A307 0 145 2.22 14 18 17.21 2926 5668 OD3001A310 0 134 4.38 5 44 18 27 32.01 4640 DD3001 A111 0.577 1.44 1 89 4.35 26.24 5170 DD3001A114 0.305 2 20 3 61 7A7 34.97 5010 CD3001 A.8)1 1.264 0 46 1 44 247 29.71 5644 OD3001AJ02 0 413 1.62 4 98 4.b5 34.49 5641 DD3001 A.06 0.563 1.15 2A9 3.22 30.35 5209 OD3001M10 0452 1 44 121 6.37 33.90 5665 OD3001 AJ14 0.134 4 32 8 65 18.00 27.60 5228 003001AK01 0 189 3 93 7 40 12A5 34 11 4915 OD3301 AK02 0454 1 68 4.32 7.3a 37.57 5657 OD3001AK04 0 117 5 02 9.34 20 93 14 77 5658 OD3001AK06 0 110 4 96 6.03 20J5 32 82 5656 OD3001AK12 0 064 9.18 11.39 36.26 4 65 5642 DD3001 AK15 0.764 0.85 1.23 2 40 25.08 5149 OD3001ALC1 0.198 2.97 5 52 1342 34 06 5664 CD3301ALO7 0.157 3.14 5 85 1349 29.31 5210 CD1001ALOG 0.294 2 53 SJ7 8.26 30.24 4041 CD3001AL10 0.091 0 13 15.14 27.57 24 95 5225 CD3301 AL12 0.347 2.14 3 41 7.00 25.37 5171 OD3001 AL13 0,207 3.24 4 96 11.60 3434 5635 DD3001AL14 0 428 136 3.27 4.30 42 60 5061 DD3001AM01 0.340 118 3 97 7.61 3716 5363 DD3001AM03 0.336 1 66 6.12 7.48 3873 5000 OD3001AM36 1.164 0 50 1.89 2.24 27.09 5215 OD3301 AM07 0 301 1 90 2A3 8.21 35.38 5147 OD3001AM10 0.156 377 10J5 17.03 1735 lite CD3001 AM12 0.240 2 43 6.07 11.67 31.58 5140 OD3001AM13 0.166. 3.50 16 40 15A1 34 47 5173 DD3001 AN06 0.330 2.03 3.11 7.29 30 66 5167 OD3001AN06 0.397 1.69 3 69 6 05 31A2 4D42 DD3301AN10 0.2n8 4.03 7.43 12 18 28 63 5180 003001 AN12 0.156 4.29 5.19 15.30 29 03 5174 DD3001AD01 0 470 1.42 3 43 5.11 at38 5141 DD3301 A003 0.359 1.64 5 08 7 40 40 20 5066 OD3001AO)4 0.103 5 41 6 58 24 45 28.11 5183 003301 AOO7 0.344 1DS 4.05 6.98 37.07 542 OD3301 A000 0.209 2 81 5 58 12.71 36.83 5118 OD3001 APC3 0.264 2 22 4 69 10.06 34 60 5006 OD3301APO4 0.737 0 60 - 1.78 an. 3252 4908 OD3001APc5 0.194 3.03 8.27 1347 31.06 4000 CD3001 AP06 0.266 2,05 3 06 9.13 40.04 4914 CD3301 AP09 0.340 173 2.36 7 48 35 96 5117 OD3001AOD3 0.303 1 D4 3.85 8.77 34.28 4669 OD3001A005 0.568 0.96 1.58 4.39 20 b4 5207 OD300tAQ07 0.327 2.27 3.83 7 43 32 47 4911 OD3001ACKA 0.205 2.87 8 96 12.74 41.62 s MEAN. 4.91 MEAN: 31 20 ST . DEV:_ 3 09 STD.DEV- 72s a erumsrrurunmuwmm'" 14 of 48 REVISION 1 ~ l
APPENDIX B i TABLE B-4 REACTOR YARD SOIL SAMPLES AREA 1 MOUND B INST: LB5100#1352 ALPHA ANALYSES BETA ANALYSES CALDUE: 08/18/93 SAMPLE MASS MDA Activity MDA ACTIVITY , NUMBER LOCATION (g) (pC1/g) ' (pCl/g) (pCl/g) (pCI/g) 5748 OD1001BA06 0.043 11.43 8.31 54.71 -5.54 5750 OD1001BA07 0.046 12.77 15.85 54.24 6.48 5575 OD1001BB01 0.029 20.25 17.59 86.04 -10.27 5752 OD1001BB04 0.085 5.78 9.35 27.67 14.72 5576 OD1001BB05 0.039 15.06 7.48 63.98 -22.92 5753 0010018808 0.047 12.50 12.41 53.09 -12.68 5573 0D1001B809 0.053 11.08 9.63 47.08 0.00' 5755 OD1001BCO3 0.041 11.99 1.60 57.37 -20.35 5757 OD1001BC04 0.043 17.81 1.53 60.13 -27.71 5759 OD1001BC05 0.203 3.77 3.91 11.34 34.34 5761 OD1001BC07 0.130 5.89 1.63 17.71 17.88 5763 OD1001BC08 0.094 8.15 13.10 24.50 ' 27.89- , 5765 OD1001BC09 0.056 13.68 3.77 41.12 7.45 'i 5767 OD1001BC10 0.042 18.23 11.97 54.83 *2.77 5769 OD1001BD03 0.023 33.30 2.85 100.12 -33.68 5771 OD1001BD05 0.043 17.81 23.56 53.55 16.63 5773 OD1001BD06 0.087 8.80 6.62 29.72 10.96 5B41 OD1001BD08 0.027 28.37 10.53 95.77 -57.38 5775 OD1001BD08 0.035 25.45 -3.96 72.60 -52.77 5777 OD1001BE05 0.049 10.03 10.26 48.01 7.30 5779 OD1001BE07 0.041 11.99 10.49 57.37 -B.72 5781 OD1001BE08 0.057 14.57 10.23 46.37 13.48 I 5783 OD1001BE09 0.023 38.73 6.66 110.47 -88.08 5785 OD1001BF01 0.028 27.35 23.17 92.35 -57.46 5787 OD1001BF04. 0.023 38.73 -12.36 110.47 -121.76 5789 OD1001BF07 0.032 27.84 0.23 70.40 -37.24 5791 OD1001BF09 0.072 11.54 8.10 36.71 7.53 7002 OD1001BF11 0.070 11.87 6.25 37.76 2.64 5793 OD1001BG06 0.061 14.60 4.90 41.65 16.61 5795 OD1001BG08 0.058 15.36 13.95 ~ 43.81 1.03 5955 OD1001BG11 0.067 13.30 2.07 37.92 23.12 5797 OD1001BH01 0.023 38.73 -2.85 110.47 -28.50-5799 OD1001BH02 0.015 59.39 24.78 169.39 -75.47 5801 OD1001BH05 0.028 27.35 -0.26 92.35 72.35 5803 OD1001BH06 0.035 25.45 -6.04 72.60 20.43 5805 0D1001BH08 0.102 7.51 5.65 22.58 17.52 5807 OD1001BH10 0.045 18.46 11.34 58.74 -13.11 5809 OD1001B102 0.172 4.45 4.62 13.39 29.10 5811 001001B105 0.023 38.73' -9.19 110.47 -85.49 5813 0D1001B106 - 0.034 26.20 4.50 74.73 -61.34 5815 OD1001Bl08 0.030 27.69 2.43 88.10 -37.54 5817 0D1001B109 0.078 11.42 1.03 32.57 -6.11 5914 OD1001Bl10 0.049 18.18 15.02 51.85 12.16 , OD1001BJ02 0.043 17.81 -3.56 53.55 -19.4G 5819 OD1001BJ05 0.034 - 22.53 -4.50 67.73 -1.75 5821 5823 OD1001BJ07 0.037 20.73 9.65 62.24 40.26 ' 5825 OD1001BK04 0.044 20.25 1.82 57.75 -21.67 MEAN: 7.16 MEAN: .-17.13 STD. DEV: 8.30 STD.DEV: 46.28 V murunnmmannwnnms 15 of 48 REVISION 1
APPENDIX B' TABLE B-4 ., REACTOR YARD SO'L SAMPLES AREA 1 MOUND B (continued) LB5100#1352 ALPHA ANALYSES BETA ANALYSES l lNST: CALDUE: 08/18/93 SAMPLE MASS MDA- Activlty MDA ACTIVITY NUMBER LOCATION (g) (PCl/g) (pCl/g) (pCl/g) (pCl/g) 5749 OD3001BA06 0.022 26.70 13.25 113.41 -37.92 5572 OD3001BA07 0.042 13.99 24.30 59.41 -25.54 5751 OL3001BB01 0.046 10.68 3.01 51.14 1.30 5578 OD3001BB04 0.037 15.88 11.82 67A3 -17.71 ; 5574 0030018B05 0.031 18.95 7.05 BOA 9 -53.82 5579 OD3001BB08 0.033 17.80 28.71 75.61 -21.67 l 5754 OD3001BB09 0.068 7.23 17.04 34.59 -0.88 i 5756 0D3001BC03 0.048 12.24 19.74 51.98 -3.72 5577 OD3001BC04 0.025 23.50 5.83 99.80 -33.37 5760 OD3001BC05 0.223 3A3 2.91 10.33 26.18 5762 OD3001BC07 0.033 26.99 15 68 76.99 -54.17 , 5764 OD3001BCOB 0.051 15.02 2.72 45.15 2.34 5766 OD3001BC09 0.026 29A6 -0.69 88.57 -48.13 5768 OD3001BC10 0.041 18.68 6.93 56.17 15.99 ) 5770 OD3001 BD03 0.044 11.17 8.12 53A6 -23.02 5772 OD3001BD05 0.065 7.56 15.59 36.19 19.25 l 5774 OD3001BD06 0.043 11.43 15.09 54.71 -13.86 l 5776 OD3001BD08 0.064 11.97 7.86 35.98 39.10 5778 OD3001BE05 0.027 18.20 18.63 87.12 30.90 5780 OD3001BE07 0.032 15.36 6.61 73.51 1.86 5782 OD3001BE08 0.037 22.45 9.85 71.44 -64.25 5784 OD3001BE09 0.030 29.69 22.11 84.69 -45.68 5786 OD3001BF01 0.024 37.12 12.45 105.87 -74 A8 3 5788 OD3001BF04 0.025 35.63 11.95 101.63 -57.20 l 5790 OD3001BF07 0.072 11.54 7.09 36.71 -0.74 , 5792 0D30018:09 0.033 26.99 9.06 76.99 -45.14 5887 OD3001BF11 0.103 8.65 2.90 24.67 26.61 5794 OD3001BG06 0.032 27.84 0.23 79AO 0.00 5796 OD3001BG08 0.035 25.45 18.95 72.60 17.02 5956 OD3001BG11 0.075 11.88 7.87 33.88 20.66 5798 OD3001BH01 0.073 12.20 1.10 34.81 25.30 5000 OD3001BH02 0.037 24.08 3.74 68.67 -25.77 I 5802 OD3001BH05 0.051 17.47 1.57 49.82 8.18 l 5804 OD3001BH06 0.059 15.10 8.77 43.06 -3.03 l 5806 OD3001BH08 0.014 63.63 -9.89 181 A9 -174 A9 5808 OD3001BH10 0.162 4.73 4.45 14.21 39.72 5810 OD3001B102 0.058 13.20 3.64 39.70 0.00 - 5812 0D30018105 0.042 10.23 8.50 54.83 12.77 5814 OD3001B196 0.087 8.80 0.75 26A7 27.39 5816 OD3001Bl08 0.005 178.17 -13.12 508.17 -286.00 1 5818 0D30018109 0.027 32.99 8.37 94.10 44.14 l 5915 003001B110 0.043 20.72 8.64 59.09 0.00 l 5P20 OD3001BJ02 0.064 11.97 1.02 35.98 28.86 j 5822 OD3001BJ05 0.035 21.88 12.29 65.79 -23.83 - 5824 OD3001BJ07 0.039 19.64 14.76 59.05 1.53 581G OD3001BK04 0.073 12.20 2.10 34.81 16.32 MEAN: 7.16 MEAN: -17.13 STD.DEV: 8.30 STD.DEV: 46.28 l l mourumsnwnuwmurene 16 of 48 REVISION 1 i
-APPENDIX B TABLE B-5 O REACTOR YARD SOIL SAMPLES AREA 2 MOUND A INST: LB5100#1352 ALPHA ANALYSES BETA ANALYSES CAL.DUE: 08/18/93 SAMPLE TAASS TADA Activity FADA ACTIVITY NUTABER LOCATION (g) (pCl/g) (pCl/g) (pCl/g) (pCl/g) 7236 OD1002AA01 0.047 14.25 6.36 49.00 3.80 ,
7237 OD3002AA01 0.01 5 44.65 29.64 153.52 -3.97 7238 OD1002AA04 0.065 7.56 13.34 37.67 23.83 7239 OD3002AA04 0.019 35.25 27.24 121.20 -37.63 7240 OD1002AA05 0.075 6.55 5.73 32.65 1.59 7241 OD3002AA05 0.018 37.21 12.55 127.93 -82.75 l 7242 OD1002AA06 0.018 37.21 8.50 127.93 -26.48 7243 OD3002AA06 0.078 6.30 5.51 31.39 3.82 ; 7244 OD1002AB02 0.017 39.40 9.00 135.46 -98.14 7245 OD3002AB02 0.012 55.81 6.68 191.90 -104.27 7246 OD1002AB03 0.093 5.28 3.06 26.33 14.74 7247 OD3002AB03 0.140 3.51 5.67 17.49 22.13 7248 OD1002AB04 0.015 44.65 53.94 153.52 -67.53 4.55 5.33 22.67 14.34 0 7249 7250 7251 OD3002AB04 OD1002AB05 OD3002AB05 0.108 0.042 0.044 15.95 15.22 8.85 8.45 54.83 52.34
-4.26 10.83 1
7252 OD1002AC01 0.069 7.12 16.80 35.48 -0.86 i 7253 OD3002AC01 0.068 7.23 8.47 36.01 19.28 7254 OD1002ACO2 0.053 12.64 5.64 43.45 16.86 10.24 16.55 51.01 -8.69 ! 7255 OD3002AC02 0.048 7256 OD1002AC03 0.039 17.17 17.01 59.05 3.06 7257 OD3002AC03 0.072 6.83 11.03 34.01 3.31 7258 OD1002AC04 0.083 5.92 7.82 29.50 -4.31 7259 OD3002AC04 0.024 27.91 -2.73 95.95 -44.69 7260 OD1002AC05 0.040 16.74 3.83 57.57 10.43 7261 OD3002AC05 0.019 35.25 19.56 121.20 -53.31 7262 OD1002AD01 0.092 5.34 11.80 26.61 9.07 > 7263 OD3002AD01 0.097 5.07 10.44 25.24 9.83 7264 OD1002AE03 0.032 20.93 7.06 71.96 -20.48 l 7265 OD3002AE03 0.041 16.33 9.07 56.17 -18.89 ; 7266 OD1002AE05 0.059 11.35 5.07 39.03 3.03 7267 OD3002AE05 0.049 13.67 6.10 47.00 8.51 MEAN: 11.36 MEAN: -12.43 STD.DEV: 10.22 STD.DEV: 34.78 mwnw.smurrawnwitmm3 17 of 48 REVISION 1
APPENIEX B TABLEBG REACTOR YARD SOIL SAMPLES AREA 2 MOUND B O INST: CAL.DUE: LB5100#1352 08/18/93 ALPHA ANALYSES BETA ANALYSES SAMPLE MASS MDA Activity MDA ACTIVITY NUMBER LOCATION (g) (pCl/g) (pC1/g) (pCi/g) (pCl/g) 7132 OD1002BA06 0.026 25.76 16.02 94 71 -57.06 7134 OD1002BB04 0.022 22.34 2.98 118.14 -102.65 7136 OD1002BB05 0.018 37.21 0.36 133.38 -89.38
- 7138 OD1002BB06 0.035 16.78 12.50 71.68 -33.88 7140 0D1002B807 0.018 37.21 0.40 136.81 -26.15 7142 OD1002BC01 0.015 44.65 -18.95 160.06 -79.84 7144 OD1002BCO3 0.025 26.79 6.12 98.50 -52.20 7146 OD1002BC04 0.025 19.66 2.62 103.97 116.55 7148 OD1002BC06 0.018 37.21 20.65 133.38 -73.49 7150 0010028007 0.009 65.27 -16.20 278.76 -303.88 7152 OD1002BC08 0.020 24.57 14.21 129.96 -133.76 7154 0010028D02 0.015 44.65 14.58 160.06 -100.10 7156 OD1002BD03 0.033 17.80 4.42 76.58 -38.10 7158 OD1002BD04 0.012 55.81 -5.47 200.07 -159.39 71GO 001002BD06 0.020 33.49 0.00 120.04 -77.76 7162 OD1002BE01 0.019 30.92 0.00 133.01 -97.53 7164 OD1002BE02 0.035 19.14 -6.25 68.60 -30.64 7166 OD1002BE03 0.024 20.48 -0.30 108.30 -64.30 7168 OD1002BE04 0.017 28.91 21.01 152.89 -115.31 O 7170 7172 7174 OD1002BE05 DD1002BE07 OD1002BE08 0.027 0.030 0.023 18.20 19.58 29.12 10.53 17.01
-6.02 96.26 84.24 107.06
-90.26
-59.78
-98.18 7176 OD1002BF04 0.037 18.10 0.20 66.55 -20.77 7178 OD1002BF05 0.010 37.21 0.40 136.81 -142.01 7180 OD1002BF07 0.01 8 37.21 3.64 133.38 -79.44 7182 OD1002BG02 0.018 27.30 3.64 144.40 151,94 7184 OD1002BG03 0.022 26.70 13.25 114.87 -86.M 7186 OD1002BG05 0.013 45.18 5.61 192.99 -155.38 7188 OD1002BG06 0.017 39.40 0.43 144.85 -136.34 7190 OD1002BH02 0.016 36.71 18.22 156.80 -137.41 7192 OD1002BHM 0.024 27.91 6.38 100.04 -39.47 7194 OD1002BH05 0.021 31.89 10.76 117.26 -59.30 ;
7196 OD1002BH06 0.018 37.21 4.45 136.81 -115.53 7198 OD1002B102 0.016 41.86 17.77 150.05 -126.24 7200 OD1002B106 0.017 45.05 8.15 147.58 -125.83 7202 OD1002BJ02 0.031 18.95 9.40 81.52 -36.71 7204 001002BJ03 0.029 23.09 0.00 82.79 -28.97 7206 OD1002BJ06 0.025 26.79 26.53 98.50 -73.65 7208 OD1002BK02 0.025 23.50 8.75 101.09 -66.97 7210 OD1002BKO4 0.024 27.91 12.45 102.60 -49.40 7212 OD1002BK05 0.009 54.61 8.91 288.79 -270.77 7214 OD1002BLO2 06 35.10 20.30 185.65 -178.32 7216 OD1002BLO3 t,.wd 95.73 -19.13 313.61 -334.41 O MEAN: 5.51 MEAN: -95.19 STD.DEV: 10.12 STD.DEV: 72.14 mrwsmammmnwormm5 18 of 48 REVISION 1
APPENDIX B TABLE B-6 REACTOR YARD SOIL SAMPLES AREA 2 MOUND B (continued) INST: LB5100#1352 ALPHA ANALYSES BETA ANALYSES CAL.DUE: 08/18/93 SAMPLE MASS MDA Activity MDA ACTIVITY NUMBER LOCATION (g) (pCl/g) (pCl/g) (pCl/g) (pCl/g) 7133 OD3002BA06 0.026 22.59 2.80 96.49 77.69 7135 0D3002B804 0.030 19.58 7.29 84.24 -39.92 7137 OD3002BB05 0.013 51.52 6.06 184.68 -82.50 7139 OD3002BB06 0.056 11.96 1.17 42.87 -17.24 7141 OD3002BB07 0.013 45.18 11.21 194.40 -119.63 7143 OD3002BC01 0.024 27.91 -2.73 100.04 -67.03 7145 OD3002BC03 0.012 55.81 -12.76 200.07 -163.85 7147 OD3002BC04 0.013 51.52 -5.05 184.68 -74.25 7149 OD3002BC06 0.032 20.93 11.62 76.95 15.08 7151 OD3002BC07 0.013 45.18 0.00 192.99 -159.96 7153 0D3002B008 0.023 21.37 18.70 113.01 -77.46 7155 OD3002BD02 0.014 47.84 0.00 171.49 -127.68 7157 OD3002BD03 0.019 35.25 8.06 126.36 -97.84 7159 OD3002BD04 0.014 47.84 10.93 171.49 -131.51 7161 OD3002BDD6 0.044 13.35 12.92 52.68 -15.03 71S1 OD3002BE01 0.021 31.89 7.29 114.33 -65.54 7165 OD3002BE02 0.023 29.12 6.66 104.39 -36.53 7167 OD3002BE03 0.01 5 44.65 -10.20 160.06 -83.42 7169 OD3002BE04 0.043 15.58 8.64 57.27 19.26 7171 OD3002BE05 0.020 33.49 -10.57 123.12 -92.06 O 7173 7175 OD3002DE07 OD3002BE08 0.017 0.016 34.55 36.71
-4.29 0.00 147.58 156.80
-83.77
-141.14 7177 OD3002BF04 0.020 29.37 0.00 126.36 113.51 7179 OD3002BF05 0.021 31.89 21.17 117.26 5J.63 7181 OD3002BF07 0.014 41.96 15,62 179.20 161.30 7183 OD3002BG02 0.017 34.55 4.29 148A6 -151.06 7185 OD3002BG03 0.022 26.70 6.63 114.04 -80.98 7187 OD3002BG05 0.018 37.21 3.64 133.38 -52.63 7189 OD3002BG06 0.032 20.93 9.34 76.95 -50.09 7191 OD3002BH02. 0.017 3940 9.00 141.23 -84.12 7193 OD3002BH04 0.006 97.90 12.15 418.14 -426.02 7195 OD3002BH05 0.043 15.58 3.56 57.27 -19.26 7197 OD3002BH06 0.045 14.88 6.64 54.72 -6.49 7199 OD3002B!02 0.051 11.52 5.72 49.55 -28.16 7201 OD3002B106 0.016 41.86 -4.10 153.91 -74.11 ,
7203 OD3002BJ02 0.034 19.70 8.36 70.61 -33.12 7205 OD3002BJ03 0.046 10.68 4.60 56.50 -28.37 7207 OD3002BJ06 0.025 26.79 -2.62 98.50 -68.88 7209 OD3002BK02 0.028 20.98 13.02 90.26 -68.31 7211 OD3002BK04 0.026 29.46 13.74 96.49 -89.15 7213 OD3002BK05 0.036 18.60 4.25 68.40 -11.42 . OD3002BLO2 0.012 40.95 23.69 216,60 -232.87 7215 7217 OD3002BLO3 0.013 58.91 38.69 192.99 -178.29 MEAN: 5.51 MEAN: -95.19 f STD.DEV: 10.12 STD.DEV: 72.14 mmmansnuunwnuurmes 19 of 48 REVISION 1 I
h APPENDIX B - TABLE B-7 /" REACTOR YARD SOIL SAMPLES AREA 2 CISTERN INST: LS$100#1352 ALPHA ANALYSES BETA ANALYSES CALDUE: 08/18/93 ' SAMPLE MASS MDA Activity MDA ACTIVITY NUMBER LOCATION (g) (pC1/g) (pCl/g) (pC1/g) (pCl/g) 7487 OU2002AA01 0.032 15.36 2.05 76.51 -26.07 7468 CO2002AA02 0.042 11.70 17.18 58.30 11.35 7409 OU2002AA03 0.033 25.17 6.63 77.95 -38.10 7470 OU2002AA04 0.037 13.28 7.68 66.17 -17.71 7471 OU2002AA05 0.035 23.73 6.25 73 50 -44.43 7472 OU2002AB01 0.070 7.02 5.10 34.98 18.73 7473 OU2002AB03 0.032 15.38 22.55 76.51 -48.41 7474 OU2002AB04 0.024 34.61 12.15 107,18 -74.73 7475 OU2002AB07 0.131 6.34 5.01 19.64 25.43 7476 7U2002AB09 0,053 9.27 12.24 46.20 -11.24 7477 % 12002AC01 0.058 8.47 4 90 42.21 -1.03 7s n Co02ACO3 0.051 16.29 5.72 - 50.44 -23.48 7479 - J02AC04 0.044 11.17 13.09 55.65 0.00 7480 OU2002AC07 0.071 6.92 8.11 34.48 8.39 7481 OU2002AC08 0.118 4.16 6.12 20.75 34.34 7462 OU2002AC09 0.097 5.07 3.68 25.24 23.34 7483 OU2002AD01 0.107 4.59 7.43 22.88 33.41 7484 OU2002AD02 0.063 7.80 18.40 38.86 9.46 7485 0U2002AD04 0.058 14.32 5.03 44.35 0.92 7456 0U2002AD05 0.040 12.77 14.26 50.39 0.00 7487 OU2002AD07 0.073 6.73 8.89 33.54 15.51 7488 OU2002AD10 0.088 9.44 3.31 29.23 12.12 7489 OU2002AE03 0.095 5.17 9.13 25.77 33.24 7490 OU2002AE04 0.044 18.88 13 25 58.46 -6 91 7491 OU2002AE05 0 051 16.29 7.15 50.44 -12.97 7492 OU2002AE07 0.080 10.38 6.38 32.15 14.82 7493 OU2002AE09 0.086 5.71 9.24 28.47 24.25 7494 OU2002AE10 0.142 5.85 5.65 18.12 13.39 7495 OU2002AF03 0.027 1820 34.82 90.68 4 7.52 7496 0U2002AF04 0.040 12.29 21.68 61.21 -34.26 7497 OU2002AF05 0.083 10.01 5.27 30.99 12.13 7498 OU2002AF09 0.091 5.40 9.53 28.91 31.43 7499 OU2002AF10 0.074 11.23 5.91 34.76 3.14 7500 OU2002AG01 0.085 5.78 4.20 28.80 2.10 7501 OU2002AG02 0.064 12.98 10,25 40.19 -2.89 7502 OU2002AG03 0.062 7.93 13.99 39.49 8.65 7503 OU2002AG05 0 048 10.24 1655 51.01 12.41 7504 OU2002AG07 0.060 13.85 1.21 42.87 4.87 7505 0U2002AG08 0.351 2.37 1.04 7.33 4.40 7500 OU2002AH05 0.077 6.38 14.10 31.80 27.86 7".07 OU2002AH06 0.053 9.27 8.11 46.20 1.12 7508 OU2002AH07 0.108 4.55 10.06 22.67 22.62 7509 OU2002AH08 0.062 13.40 4.70 41.49 -6.82 7510 OU2002AH09 0.131 3.75 6.06 18.69 24.11 7511 OU2002AH10 0.063 13.19 5.78 40.83 8.42 7512 OU2002A102 0.073 6.73 15.88 33.54 20.41 7513 OU2002A!08 0.075 6.55 6.71 32.65 17.48 7514 OU2002A107 0.070 7.02 20.72 34.98 27.24 7515 0U2002A108 0.075 6.55 14.48 32.65 8.74 7518 OU2002A109 0.061 1362 5.97 42.17 -6.94 7517 OU2002 At10 0.063 7.80 9.14 36.86 -10.40 \ MEAN; 9.66 MEAN: 2.19 STD.DEV: 6.34 STD.DEV: 23.37 mourumsmmrurnarxmama3s 20 of 48 REVISION 1 l
_m ._. , I TABLE B-8 REACTOR YARD SotL SAMPLES AREA 2 SECONDARY SUMP j 1N57. Lb510001352 ALPHA ANALYSES BE7A 4NALYSE3 CALDUE; 08/14193 SAMPLE MASS MDA AeHvity MDA ACTWITV NUMBER LOCATION (3) (pCl!9) (pClfg) (pct!g) (pCDg) 7259 OU2002BA07 0 034 13.d5 3 84 sf. 34 -48.34 1 7290 OU2002BA08 0.025 23.50 17 49 92.71 -45.05 7291 OU2002BA15 0.034 17.28 17.15 68 17 4.58 f OU2002BB07 0 028 20.98 2 80 82.78 23 19 ! 7202 7293 OU2002BB08 CA23 36.12 -3.17 111.84 -75.39 72b4 0U20020B09 0.070 11.87 4.08 34.30 18.00 7295 OU20020812 0.071 6.27 13.35 32.64 22.74 , J 7290 OU20028814 0.000 9.79 8.50 3663 -12 41 7297 OU2002DC05 0467 1140 1ce 3629 10.76 7294 OU2002BC06 0.199 4.17 0.73 12 93 6.72 7299 OU2002BC00 0 041 14.33 8.33 6633 25 01 . 7300 OU2002BC10 0 044 10.24 12.00 40.01 4.87 7301 OU2003011 0.057 14.57 7 87 45.13 11.60 7302 OU2002BC12 0 058 10.13 1267 39.96 13.46 7303 OU2002BD11 0224 24 47 3.04 96 57 27.06 7304 OU2002BD12 0.050 8 19 20A3 39.21 4.L6 7305 OU2002D13 0.048 12.24 9.11 48 29 16.26 7306 OU2002BD14 0.0a2 to 13 6.33 3147 12.28 7307 0U20029D15 0.063 9.32 S.10 36.79 1941 7308 OU2002BD16 0.088 S.58 843 26.73 -4296 7309 OU2002BE12 0221 27.97 34.71 110.37 -te As 7310 OU2002BE13 0.050 11.75 13.12 4626 19.19 7311 OU2002Bf14 0.102 4 82 4A3 23.00 35.05 7312 OU2002BE18 0.040 10 03 1.34 48A: -17 A2 7313 CO2002BF04 0 078 0.30 4.4$ 30.16 25.21 7314 OU2002BF08 0.080 10.38 3.64 32.15 047 7315 OU20029507 0 076 6.30 7.38 30.15 12.15 7316 OU20028815 0.100 4 91 4 30 23.62 24.43 7317 CUW02BG01 0 086 6 83 10.17 26.95 34.71 7318 OU2002BG02 0.061 7.25 9.90 28.61 10.37 7319 OU2W12B005 0.0s9 11.99 11.90 47.30 3.77 7320 OU2002BG07 0110 5.34 5 63 21.07 31.47 7321 QU2002BG06 0.077 7.63 3.79 30.10 11.68 7322 0U20028000 0.087 5 75 5.66 26 64 26.09 7323 OU2002BG10 0.107 7.75 10.90 24 04 18.88 73N OU2002BG11 0.041 11.99 6.71 57.37 -7 ft 7325 OU2002BG12 0.088 9 44 2 48 29.23 3D9 7326 OU2002BG13 0.078 733 3 74 29.72 15.35 7327 0U2002SG14 0 092 6 38 10.30 25.10 27.27 7326 OU2002BG16 0.044 13.35 4.97 8268 -237 7329 OU2002BH33 0.045 13.06 22.68 61A1 2122 7330 OU200SH04 0.070 7.02 14 47 33 et 24.85 7331 OU2002DH05 0.061 SM 10.63 38.56 20.S1 r 7332 OU2002SH06 0.0A 17.26 0.00 48.17 0.18 7333 OU2002BH07 0 051 1152 10.00 45 45 6 De 7334 OU2002BH06 0 069 7.12 8.35 34.00 1295 7335 OU2002BH10 0.118 4.98 4 44 19.64 22.27 7336 OU2002DHt2 0 091 6 45 8 81 25 47 IS 40 7337 OU20c2BH13 0.097 6 DS 6.27 23 69 19 10 7338 0U2002B01 0435 23 73 0.03 7350 51.24 ) 0U2002B06 0 048 17.31 0.00 5359 31.16 7330 7340 OU20028107 0.136 4.32 4.82 17.04 26.33 7341 0U2002B100 0D62 7.93 5.76 37D4 12.49 7342 CU2002B111 0 047 12 SD 11.51 4931 0.13 7343 OU20020112 0 053 11.08 13.75 4373 19.22 7344 ' OU200$113 0.034 24 43 4.29 75.06 35.22 7345 OU2002Bt15 0.091 6.45 15.22 25 47 20.38 7348 0 020029118 - 0 082 7.16 7.11 2s 27 952 7347 OU2002EUD4 0 072 8.14 0.11 32.19 18.29 7348 OU200SJD5 0.084 5 99 8 $8 27.59 11.42 7349 OU2002EUO7 0 097 5.07 11.20 24.25 38.70 7350 OU2002S&S 4.055 8 B4 0 14 42.77 1.08 l 7351 CU2002BJ10 0.064 12 96 5.81 37 51 0.22 [ 7352 OU2003J12 0 093 6.26 8 54 25.29 26.19 , OU2002BJ13 0.063 13.19 8.94 40.83 15.04 7353 OU2002BJ15 0042 13.09 8 68 $5.19 8.37 7354 7355 OU2002DK04 0.105 $39 744 2227 22.19 , 7358 OU2002BK06 0.001 7.25 8.10 26 81 20.57 7357 OU2002BK00 0.117 5 02 4.98 19 81 20 42 7358 OU2002BKto 0.0a0 6.14 11.75 29 40 14 15 OUW02BK13 0.059 9 98 4 D4 39.26 4.14 7359 14.87 i 73a0 OU2002BK14 0.0a0 7.34 12.75 28.87 7361 CO2302BKt5 0.076 733 9.34 29.72 1745 7382 OU2002DK16 0.165 3 56 4 63 1446 31 61 OU2003LO4 0472 e 10 6.00 32.19 10 01 7363 7364 OU2002SLOS 0.056 14.83 8.11 45 94 4.11 7365 OU2002BLO7 0.129 4.55 7.91 17 s 7 8 97 7366 OU200$LOS 0.064 7.68 9 00 36.70 6 52 25.20 , 7367 OU200$L10 0 100 5.39 4.01 21.26 OU2003L11 0.071 8.02 6.06 33.13 15.11 7368 0.064 7.68 4.44 36.74 4.65 7369 OU2002BL12 OU2002 Bit $ 0 A71 11.70 6.21 36 23 4.11 7370 MEAN; 8 05 MEAN: 559 ., STD DEV: 6 64 STD DEY: 21 ea oomumsmAmunssnxsAutnoso35 21 of 48 REVISION 1
APPENDIX B Table B-9 Nuclide MDAs (pCilg) Nnclide MDA MG54 0.1 C658 03
~
1:6:59 0.2 Co40 0.1 Zn45 0.3 Mo-99 1.0 Cs:134 0.I Cs:137 0:1 Ce-141 0.1 Cell 44 0.1 Eu 152 0.01 Es:154 0.1 Th-234 1.4 The ll 0! 2 SLUDGE Fadionsclide liblaryjused during analyds also sontains the following nuclides: Be.7; ~ Pb-210 :: T Ra-223i ' Th 233 K 40 L Pb-211.l Ra 224 - Th-234 K-42 :- Pb-212 - Ra-225 ' Pa-231 Cr-51 ' i Pb-214 ' Ra-226 '.- ' Pa-233 Rb-83 i 2 Bi-211-' Af-225 ': Pa-234a Kr-85 : - / Bi-212 ::'Ac-228 1. Pa-234 ' Nb-94 . : Bi-213 - Th.227: ' U-231 11a 133 ' 111-214: Th-228 ' " U 232 T1-207 : Po-211 . Th' 229
':U-234 T1-208 :- 4 Rii-2'o i ' Th-230. . U.235 TJ-209 ;: Fr 1. . Th.231 sM aU-238 TI-210 L 2 Ft-22 Th-232 Am-241 _
~
Note: These Values ~are froin a stsnciaid soil analysisT : Ths 1.3g sample was analyzed for 500 secorids using a sand; rnarinelli' matrix. m m mr.strumw nummo" 21a of 48 REVISION 1
APPENDIX B r TABLE B-10 REACTOR YARD SO!L SAMPLES AREA 0 MOUND A n., e.=um. us. u, GAMMA SPECTRUM ANALYSES NUCLIDES pCilg
. Am.tf Ce ,3, h 30. .p t,3 Pb.3,3 .6.,4 Pb t.. 33. .e. 2,. h t,. Tb t3 M .* 1 3 b, muu r. LOCA ,,DN 84
.m ~ . . . , ., .. .n ..
im --- .. ., ..., .. . im ., .. ... . ..
,,,, . , - on ., .. . .. . . ,
.- - ., .. ., .n
.o,-, , , . .. . .,
... . 7, .
,m .o.-., .
,m -.
. .,-c. ... .., .,, .n ..
.. .,-c.
., on,-.c., .... .., .., ... .
., .~ .. .. .., .
,, .o,--. ... .,. . ..
. 1 4
L mennt.smamawawnwmo35 22 of 48 REVISION 1
. - . - - . .- . - .- . . ~-. . . ~
APPENDIX B TABLE B 11 REACTOR YARD SOIL SAMPLES AREA 0 PIPECHASE af tnuums uu es, GAMMA SPECTRUM ANALYSES NUCLIDES PClig sawns tsumeER LDC AYION E4e e* 137 D IOS D 213 96-813 Dfte 96914 he-274 he 32s Aet2e Tbt34 Co4e eate$ es1H tm euraxxam ese s er e s, en
.4m ar .n um en eM en om m, em sua, w em en en
,4m eue co.aB en on en i=3 suraxa.or is m em en om en im suramoane er 7 e te em s.n en
.4m m= e ar en e rs en im eurmxemn en .2e em en en 17e8 DJEN"an e21 e te eM 8 07 IN7 eU20000eDP eM 9 71 s ee e se 1422 eW'* em e 73 ott tSee outcomCet BeJ1 42e e.78 s ee em 30 tese eUtommCM te m e27 e ?B est s ei 147s eJNDOOCe5 em G Ps e e7 e7e 147e mnem2007 e 74 e 74 e es tMe suremmCc3 f f #T eB e13 e Fe em its3 cupm-m 94 7F e re e s' e 73 e ?R 94F3 e020000004 9e st e87 em of7 est 17mr sufstc00s e3 e s? 0 75 e se sMe avrarmour to ie en e 7e em e ve 49e e evitaand er le il B 3D e 90 e 83 e et ISEP DJNKE0Fei IT M e tt om e fe em 6 74 fees surexmPm 19 42 e 13 ez? e tt eM e7e les 4s74 m17 encore 3 M 5s eB e 77 e 7e e el 1947 sulcomPee IS ep e se e 33 en s el e fD 9370mNFee em e 7e 6 fe eel e se tat t.4e outcomref $7 50 e21 8 33 s e5 s e5 set un macamooi ese ea e se e es e er i4es an~-= n rr ea e en eer e se in? our - to ne 42s s e3 en err seso mammoued its? om e ra en en e en tM3 outexhxh0S face est s es e eS 6 87 8 87 sees auramcoas is s3 em em en ,
148e eutixrmede 47 et 6 74 ee 6 toes auNcDoHoe le e9 62e e es e 77 eM ime euneceMoe t$st een e e ra usw is se em em e ?: e.74 of se em em em ormece in e se eM em em em en
- Maan le of samples greater then MDA.
mmnwsnwcrmmxummms 23 of 48 REVISION 1
APPENDIX B TABLE B-12 REACTOR YARD SOIL MMPLES AREA 1 MOUND A OAMMA SPEC 1hJM AN As 75ES tJJCLDiS pCug tw caneveu uc.o ens SAMPLE Ce40 N 152 te154 NUMSER LDCATION K40 C e137 T1200 Bb212 Ptr212 Bb214 Pk214 Re224 Re-226 Ae228 Th234 0.31 0 66 0.65 0 64 0.75 2 43 DD1001 A A1 17.76 15.38 0.29 0 68 0 05 031 5662 DD t001AA02 14 45 0 17 0 66 0 55 0.68 5655 OD1001 AA04 001001 AB01 17.23 0 33 0 65 03e 0.71 5376 18 70 0.27 0 83 0.71 0.76 5869 OD1001 ABc2 043 0 76 0.76 0 60 4935 OD1001 A805 16.11 0.32 0.65 0 67 0.79 4p45 001001 AC01 16,77 0.32 0 63 0.66 0 67 4803 00100 t ACO2 17.63 0.29 0 00 0 75 0.74 5647 001001AC03 1842 0.26 0 66 0 63 0.76 5648 OD1001AC04 17,79 0.26 0 50 0 51 033 0 73 5211 CD1001AC05 0.26 0 se 0.58 0,75 0.79 5645 OD1001 ACD6 20.23 0 61 0 62 0 72 4606 OD1001 AD02 21.34 0.26 0 66 0.60 0.72 4938 001001 AD04 17 64 0.21 0 60 0 61 0.63 5212 DD1001 AE01 18.72 0.27 0 78 0.71 4937 OD1001 AE03 0.a0 0.74 OA3 1.00 5115 CD1001AF03 17.09 0.33 0.31 0.75 0.75 0.76 5014 OD1001 AF04 0 26 0 63 0.77 0.78 0.63 1213 001001 AF05 18 60 16.53 0 26 0.71 0 66 0.72 5370 CD1001 AGot 16 61 0.24 0.64 0.76 0.77 5179 OD1001AG02 17.77 0.66 0.72 0.71 4804 001001 AG03 0 27 0 60 0 90 0.00 4H7 DD t001 AG07 4946 0.37 0.70 0 60 0.65 OD1001 AH01 DD1001 AH04 0.30 0 63 0.85 4674 0.29 0 64 0 58 054 0.65 5376 OD1001 A101 1612 4607 001001AfC3 16.00 0.20 039 0.61 0.65 DD1001 Al07 18 47 0.31 0.75 0.77 0.64 4802 0.73 0.75 0 60 4a71 001001 A110 0.31 0.54 0 56 0 60 1.88 5650 001001 Al11 17.88 17.01 0.31 0 68 0.62 0.70 5381 DD t001 Al14 17.20 0 24 0.73 0 64 0 60 5a36 001001 AW1 0 25 0 60 0.60 0.76 4872 0D1001U32 18 56 0.21 0 68 0 67 0 67 5377 OD t@1 AJ06 0.71 0.75 0 66 ' 5646 001001 AJ10 16 07 0.22 0.74 0.68 0.74 0.8D 5218 OD t001 AJ14 17.08 0.25 5666 001001AK01 17 90 0.77 0.62 0.73 b667 001001 AK02 20.01 0.35 0 74 0.76 0 65 4G34 OD1001 AK04 0 28 0 57 0 66 OM 0.29 0 85 0 71 0.72 0 64 5639 OD1001 AK06 17 48 16 12 0 34 014 0 68 0.63 5640 OD100tAK12 16 17 0 25 0.61 0 55 0 58 5145 OD1001 AK15 4667 CD100 t AL01 0.27 0.76 0.53 0.51 18.21 0.34 0 66 0.66 0.78 5670 001001 ALD7 17.31 0.33 0 61 0 60 0 68 5162 CD 5001 ALOG 0,20 0 73 0 63 0 63 1 53 Sc45 CD1001AL10 17.46 16.60 0 29 0.63 0.52 0.71 5208 OD1001 AL12 0.24 0 63 0 65 0.56 13e
$206 DD1001 AL13 15 65 0.30 0 66 0.73 0.75 0.71 5854 CD t001 AL14 1875 17.13 0.28 0.70 0 62 0.54 5150 OD1001AM01 0.26 0 69 0.70 0 47 0.80 5114 DD1001 AM03 1632 0.65 0.74 0.64 0 66 5144 DD1001 AM00 17.02 0.26 4868 OD1001 AM07 0 26 0.70 0.02 0.72 17 66 0.33 0.70 0.70 0 67 5176 ODiOO1 AM10 0.75 0 46 0 67 2 46 5t72 DD1001AM12 16.87 16.11 0.24 0 66 0 55 0.74 5169 DD tll0 t AM t3 0.27 0.51 0 56 0.73 5012 CD1001 AN06 0 24 0 58 0.73 0 66 4670 001001 AN08 0.34 0 63 0.65 0.64 4643 001001AN10 17.37 0.31 0 64 0 53 0.76 5148 OD1001 AN12 0.33 0 60 0.57 0 51 5007 001001 AOO1 to42 0.33 0.71 0.68 0.79 5146 OD1001 AOO3 0.33 0 78 0.73 0 67 1.99 1.04 5143 OD1001 A004 16 98 0.75 0 66 0 49 0 85 SDf.4 001001 A007 17.06 0 26 17.14 - 0.35 0 64 C 66 0 64 ba62 001001 A030 0.33 0 68 0 65 0.78 5011 OD1001AP03 0.25 0.74 0.73 0 65 0.78 5175 ODiOO1 APO4 10 66 17.88 0.24 0 61 0 62 0.74 5176 001001AP05 0.26 0.75 0 62 0 67 4910 OD1001 AP06 0.25 0.77 0 62 0.00 4673 CD100t AP00 BM7 OD1001 ACX13 1342 0.24 0.73 0.66 038 0.30 0.72 0.77 0.75 5015 OD1001 AQ"5 17.37 0 30 0.70 0.70 0.74 5177 OD1001 AQG7
- f. 31 0.70 0 60 0 67 0.70 Site 001001 AOD6 15 99 0 28 0 67 0 68 0 68 0 67 0 67 1.82 0 60 MEAN* 1741 0 DS 0 06 0 08 0 00 0 17 0 37 0 15 F70 DE'W1A710N 1 29 0 05
. u.ac. 61 +, re..~ un ;
f 1 4 l 1 m runartwurm w n wurunes 24 of 48 REVISION 1 l l l 4 1 1 1
APPENDIX B I TABLE B-12 s l REACTOR YARD GOfL SAMPLES AREA 1 MOUND A (centinued) s1Laneemsu,odet 655hHXTisJM NAt[I5 hJGLWi$ pGety
- 5 AMPLE K40 Ce137 Tb2DR Bb212 PF212 Bb214 Per214 Ra-224 Re 226 As 228 Th-234 Ce40 Ew152 tw154 NUMTIER LOCA7 TON OD300 t AA01 16.55 022 0.64 0.70 0.70 5362 DD3001AA02 16.17 0 43 0.59 0 61 0.72 5161 5182 CD3001 AAD4 17.35 0.79 0 66 C 65 15 93 0.33 0.72 0.56 0,74 i Se43 00330 t ABC)
DD3001 AB02 15.90 0 06 0 23 0 56 0 53 0 82 07s 5651 4939 OD3001 AB05 0 22 0 54 0.81 0 47 i 003001 AC01 15 36 0 23 0.56 0.56 0 59 M61 CD300t ACC2 0.32 0.73 0.71 0.53 f 4s12 OD3001 ACO3 20 01 0 35 0 74 0.62 0 75 0 90 5214 17 76 0.30 0 64 0 70 0 66 1.24 6660 0D3001 AC04 4s01 DD3001 AC05 16 62 0.30 0 62 0.74 0 62 4913 DD3001 ACO6 0 77 0 63 0 60 0.60 4648 OD 21 AD02 0 25 0.72 0 $2 0 68 17 60 0.25 0.51 0 $2 0 56 0.91 5637 003001 ADO 4 19 10 0.28 0 57 0 63 0 66 1.27 M36 OD3001 ALO1 17.70 0.22 0 65 0.72 0 65 0 66 5360 OD3001AE03 4 b49 OD3301 AF 03 0 16 0 43 0.51 0.51 4916 OD3001 AF04 0 33 0.74 0 72 0 66 003001 AF05 16 27 0 28 0 60 0.61 0 63 0.21 i 5634 . DD3001AGot 21.34 0.36 0.76 0 69 0 65 i 5652 l 4 SOS 003001 AGD2 15 93 0.23 0 70 0 75 0 69 17.69 0.29 0 85 0 72 1.03 4600 00 m01 AGC3 5013 003001 AGC7 0 30 0.66 0 79 0 78 j 4933 0D3001 AH01 0.23 0 so 0 53 0 54 003001 AHG4 16 16 0.29 0 74 0.72 0.63 Se59 OD3001 A101 16 62 0 17 0 62 0 60 0.60 0 72 516e l DD3001403 17 65 0 25 0 74 0.81 0 76 l be53 5649 ODDOI A107 16 56 0.26 0 67 0 62 0 80 l OD3301 A!10 1s.33 0 26 0 B6 0 56 0 66 l 5668 4940 OD YJo t Af t1 17.93 0 29 0 73 C 63 0 67 5170 CD3001N14 16 43 0 28 0 76 0 60 0 66 ODE 01 AJ01 0 31 0 56 0 70 0 62 5010 ' ODE 01 AI2 16 06 C 26 0.70 0 66 0 64 M44 0 62 b641 0D3001M06 17.7D 0.30 0.70 0 72 to 00 0 33 0.71 0 76 0 76 0 G7 l 5209 OD300 t AJ10 17.36 0M 0.76 0 52 0 73 0 62 1 56c5 00)001 AJtd 5226 OD3001 AF01 17.75 0.24 0 54 0.70 0 67 i 0 32 0 63 0 63 0 63 0.74 4915 CD 3x1 AK32 17 27 0 30 0 50 0 79 0 76 0 66 b657 OD W1 AK34 Se%8 OD3301 AXO6 17 96 0 27 0 63 0.70 0.7h t 16.70 0 19 0 72 0 56 0 66 2 21 0 93 i 5656 CD3001 AM12 OD3001 AE15 to 50 0 26 e 66 0 70 0 70 5642 OD3001 ALD1 17 49 0.27 0.74 0 49 0 69 0 67 i 5149 CD3001 Aw? 15.36 0 26 0 71 0 61 0.73 j 5664 OD3001 ALD9 17 26 0 24 0 76 0.79 0 45 5210 494i OD3001 Alto 17 03 0.3 0 52 0 53 0 65 DD3001 AL12 1652 0 18 0 67 0 59 0 64 Sv5 13 93 0 24 0 60 0 52 0.57 1 96 0.81 5171 CD3001 AL13 5635 OD3001 AL14 16 66 0.26 0 66 Ot2 0.39 1 65 003001 AMo t 17.95 0 37 0 to e e5 0 78 5361 5063 CDXOtAMD3 17.39 0 24 0 69 0 67 0.72 ODM0 t AM36 0.27 0 72 0 62 0 57 50D0 17.39 0 26 0 69 0.70 0 55 0 73 5215 OD3001 AM07 OD 3001 AM10 16 50 0.16 0.73 0 59 0 67 0.72 2 03 5147 0 26 0 60 0 67 0 61 0.99 5119 OD 300 t AM12 18 06 0033CI AM13 17.06 0.27 0.75 0 70 0 06 2 05 5140 19 68 0.35 0 63 0 60 0 85 0 76 5173 CD300l AN36 5t67 OD3001 AN06 18 64 0.23 0.72 0.76 0 05 OD3001 AN io 0 30 0 70 0 60 0 47 4942 5160 CD D01 AN12 14 35 0 26 0.65 0 53 0 83 19 60 0.34 0 73 0 62 0.76 0 83 5174 003001 A001 18 67 0.26 0 64 0.76 0.77 0 77 5141 CD300 t A003 10 01 0.70 0f3 0 63 0 70 0.02 W6 0D3301 AOO4 OD3301 AO 7 16 20 0.28 0 63 0 66 0 67 5183 CD3301 ACxe 17 65 0J1 0 60 0.77 0.81 5142 0.31 0 77 0 75 0 50 0.64 511B OD3x1 APc3 17 40 DD E01 APG4 0 27 0 53 0.63 0 71 5006 4936 OD3001 APDS 0 41 0 65 0 66 0.55 4900 DD330 t Apoe 0 27 0 67 0 57 0 04 4s14 CD300 RP09 0 31 0.74 0 71 0.58 ODW1 AQO3 17 61 0.25 0.69 0 60 0.72 5117 OD3001 AM 0 32 0 60 0 67 4359 03 0 66 0 65 0.70 0.71 52c7 OD M 1 ACE 7 18.20 4911 DDM01 AQDB 0 28 0 66 062 0 52
~
l 17.41 0 06 0.26 0.67 0 06 0 66 0 67 0 67 1 62 0 60 MEAN' 0 05 0 De 0 08 0 09 0 12 0 37 0 15
. _ $TD DfM471/1N 1 29
. M... .. s ,#. 9.. 1 4., M a
% %mumstmax1Auimno35 25 of 48 REVISION 1
APPENDIX B , TABLE B-13 REACTOR YARD SO:L SAMPLES AREA 1 MOUND B av m uu .c GAMMK5FCCTiiUkTNiALY5E51WCDDES pGug
$ AMPLE K-40 C + 137 71-208 81212 Pb212 Bi-214 Pb214 Re.224 Me224 Ae.228 Th234 Ce40 t e152 te154 NUMBER LDCATION 16 94 0.29 0.70 0.75 0.77 1.13 5748 001001BA06 0.35 1.17 1 05 1.10 3.84 5750 CDt001BA07 23 21 14,37 0.31 0 90 0.75 0.88 0.53 5575 0D10018001 0010018b04 17.50 0.32 0 93 0.71 0.75 5752 OD10010005 14.73 0 29 0 BC 0.55 0.81 1.13 123 5578 0010018B08 16.70 0.26 0.79 0 68 0.81 5753 0.31 0 79 0.87 0 83 0.80 5573 0D10019809 17.10 15.33 0.31 0.68 0.70 0 to 0 se 5755 CD10019003 OD1001BC04 16 69 0 69 0.74 0 80 5757 0010019005 18.16 0.30 0 89 0.80 0.95 5750 001001BC07 19 14 0.33 0.81 0.73 0.87 5761 001001000a 19.75 0 37 0 64 0.93 0 43 5763 20.75 0.28 0 83 0.a3 0.s0 1 14 5765 001001BC00 001001BC10 to 90 0 35 0 77 0 07 0.86 5767 5759 001001BD03 17.70 0.35 0.81 0.70 0 65 0 40 0.87 0 89 1.00 1.16 5771 OD10c1BD05 21.06 001001BD06 21 44 0.31 0 65 0 88 0.s4 1.03 5773 CD100tBDos 16.24 0.28 0.88 0 65 0.83 5841 00100tBDo8 18 48 0 24 0.02 0.77 1.00 5775 16 15 0.30 0 96 0.68 1.05 1.05 5777 OD1001BE05 OD1001DE07 22 62 0 44 0 90 0 99 1.07 5779 14.is 0.22 0 55 0 52 0.57 0.se 5741 CD1001CE0s 17.78 0.25 0.74 0.82 0 88 0.79 57s3 001001BE09 OD1001BF01 is 88 0 31 0.72 0 80 0.6a 5785 0.32 0 84 0.82 0 97 0.77 5767 001001BF04 17 11 18.70 0 39 0.73 0.68 0.60 0.93 5?60 OD1001BFC7 OD1001BF00 14 47 0.20 0 68 0 67 0.57 2 so 5791 7002 CD t001BF11 5783 OD1001BG06 19 60 0.35 0 91 0 86 0.M 5795 OD100 tBG66 18.06 0 35 0 80 0.75 0.73 5955 00100180 t1 18.22 0.31 0.74 0.74 0.75 001001DH01 17.35 0 15 0 29 0.79 0.73 0.66 5767 19.23 0 23 0 68 0.71 0 64 0.98 579e 001001BH02 0.42 1.16 1.00 1.14 1 15 Es01 001001BH05 25.38 5803 001001BM06 20.33 0.35 0 80 0.79 0.71 5n05 DD1001BHoe 16 70 0.35 0 82 0.73 0.77 001001BH10 15 13 0.21 0 65 0 55 0.63 5607 5800 001001B22 16.50 0.25 0 71 0 85 0.96 15 70 0.30 0.56 0 56 D e0 1 s4 58 t1 0D1001B:05 5813 001001B106 16.00 0.21 0.73 0.70 0 91 Se15 OD1001Bl06 15 63 0 27 0 74 0.72 0.55 OD1001Bl09 14 00 0 30 0.74 0 66 0.64 5817 0D1001B110 17 05 0.32 0 50 0 58 0.00 5014 58 te 0D1001B42 16 38 0 27 0 63 0.67 0 62 0D1001B45 18.70 0.34 0.81 0 63 0.76 5821 0010018 4 7 17.55 0.23 0.73 0.74 0.75 5823 001001BK04 10 10 0.27 0.76 0.73 0 50 5825 17.53 0.14 0.31 0 85 0.76 0.73 0 79 1.13 1 63 0 82 MEAN*
0 07 0 D5 0 11 0 11 01e 0 91 0 13 STD DEMA7 TON 2.05
. u.., ,. a +. ... en ua muumstrarrwwnmum"* 26 of 48 REVISION 1
.- =
~ -. -- . .. APPENDIX B TABLE B 13 REACTOR YARD SOIL S AMPLES AREA 1 MOUND D (continued) nss s. man a enso en GAMMA SPICTiiUM AWiT5[5~NUl.T.lDES PGuig
$ AMPLE LOCATION K-40 C + 137 T1206 81-212 Pk212 Bb214 Pb214 Re-224 Re 226 Ae-220 Tk234 Ce40 Eir152 Ew154 NUMBER 5749 OD3001BA06 14 67 0 PS 0.79 0.75 0 63 5572 CD3001BA07 17.21 0.25 0.72 0.63 0.76 16 00 0.24 0.37 0 64 0.80 0 D6 0.99 5751 0030019B01 17 10 0.32 0 63 0.60 0 43 2.74 0.60 5576 OD3001BB04 CD3001FB05 17.25 0.31 0.79 0.72 0 69 5574 14 63 0.25 0.72 0.71 0.76 0 81
$57e 0D30010B06 5754 0030015809 14 76 0.:s 0.81 0 60 0.75 0.06 0.35 0.82 0.74 0.77 1.06 5756 003:019003 16 49 14 97 0.30 0.64 0.65 0.71 0.66 5577 0D30010004 0D3001B005 16.70 0.33 0.85 0 of 0.81 1.00 5760 1042 0 37 0 94 0.76 1,06 5762 CD3001BD07 0.33 0.85 0.79 0.82 1.13 5764 0030018006 17.66 20.76 0.29 0.67 0.82 0.76 0 85 5766 DD300tB009 5768 OD3001BC10 16 60 0.28 0.70 0.83 0 62 18.06 0 35 0.76 0 64 0.75 0.64 5770 0030010D03 CD3001BD05 18.72 0 28 0 60 0.76 0.80 5772 18 43 0 41 0.90 0 60 0.65 1.05 5774 0030018006 OD30010DD6 16.76 0.33 0.76 0.76 0.92 3.33 5776 OD3001BE05 16.50 0.33 0 33 0.93 1 19 0.96
$778 0030010E07 19.32 0.34 0.75 0.69 0 49 0 97 5760 CD30018E06 14 64 0 68 0.72 0.72 0.64 5762 DD3001BC09 to 62 0.36 0 60 0.79 0.72 0 63 5764 5786 CD3001BF01 17.19 0 34 0 62 0.79 0.71 5764 0030C 19804 16 49 0.27 0 67 0.70 0 94 .
15 64 0 23 0 67 DE3 0.70 0 87 5730 OD30NBF07 5702 OD3001BF09 18 90 0.26 0 68 0.57 0 73 00300IBF11 1940 0.26 0 67 0.70 0 75 0.65 5687 17.27 0 32 0 80 0 66 0 66 0 66 6794 CD30010000 5796 0033010G36 16 60 0.30 0 86 0A6 0.70 16 60 0.31 0 64 0.75 0.77 0.99 59$6 CD3001B311 5796 CD3001BH01 16,74 0.12 0.30 0 73 0.70 0 69 5600 OD3001PH02 15.70 0.22 0 64 0 60 0.13 5802 CD3001BH05 19 01 0.32 0.78 0.46 0.81 16 50 0.29 0 69 0.67 0.72 0.99 5604 OD3001BH06 5806 003001BH06 1049 0.27 0.61 0 48 0.74 5800 003001BH10 10.59 0 36 0.82 0.82 0.79 5810 0030010c2 15.70 0.35 0.70 0.56 0.76 0D3001B105 16 Ba 0 32 0.70 0.67 0.83 1.55 0.71 5812 0D30010106 15.44 0 24 0 58 0.71 0.72 0.74 5814 5818 003001Bi06 17.16 0.33 0.79 0.66 0.74 16.50 0.31 0.63 0.67 0.79 0 66 5816 0030010109 5915 0030010:10 15,17 0.34 0.72 0 45 0.59 0.32 0.70 0.75 0 69 0.64 58F) 00300t822 16.20 5622 OD2001BJD5 15.43 0.22 0.61 0.68 0.70 5824 CD3001BE7 1847 0.39 0.66 0 82 0 67 5626 OD3001BA04 14 57 0.32 0.67 0.66 0.71 MEAN* 17.53 0.14 0.31 0.65 0.76 0.73 0.79 1.13 2 83 0 82 0 07 0 05 0 11 0 11 0 is 0.91 0 13 570 DrvlATim 2 05 P
- Mean is of tempes gester than MDA.
merumsmomuwmuremms 27 of 48 REVISION 1
. - _m m.-_ .. ...-._ _ ._. _ .. _ _ _-..~...._m . _
APPENDIX B TABLE B.14 REACTOR YARD SOIL SAMPLES AREA 2 MOUND A
.ust t.aums ut,o en Q AMM A SPECTRUM MALYSE$ NUCUDES pCI!g SAMPLE K-60 Ce127 T120s BL212 Pk212 Bb214 Pk214 Re 224 Re22t Ae.226 Tk234 C+60 Ee152 Ew154 NUM8tR LOCA710N 7234 CD1002AAct 1732 0 20 031 O so 7237 OD3002AA01 17.07 0.23 0.72 0.60 0 66 7238 001002AA04 19 98 0 34 0 De 0.77 0 6a OD3002AA04 18.60 0 24 0.76 0.57 0.51 7239 7240 CD1002AA06 16.01 0 73 0.58 038 7241 CD3002AA05 15 47 0.61 0 40 031 7242 001002AAD6 15.33 0.17 0.64 7243 003002AA06 16 93 0 64 0 80 074 7244 DD1002AB02 15 64 0.62 0.54 7245 CD3002A902 14 A0 0 64 7244 DD1002A803 17.77 0 66 0 65 0.51 7247 003002AB03 16 30 0.77 0.52 0 48 7248 CD1002AB04 to11 0 63 7249 OD3002AB04 16 66 0.62 0 62 0.61 7250 CD1002AB05 14.71 03 0 60 0 49 037 7251 DD3002AB05 16 66 0.63 0 53 0.54 7252 001002AC01 17.08 0.7D 0 48 0.54 7253 OD3002AC01 17.24 0 82 0 57 7258 001000AC02 17.66 0.85 0 60 0 81 7255 CD3002ACc2 18.24 0.75 0.72 0 07 7256 001002AC03 15.80 0.30 0.50 7257 OD3002AC03 17.69 0.38 0.78 0.62 7258 OD1002AC04 17.4 e 0 24 0.75 0.51 7258 CD3002AC04 13.35 0.55 7250 CD1002AC05 15 is 0 58 7241 DDMc2AC05 15 41 037 0.32 7262 001002AD01 19.83 0 85 0 91 0 63 7263 DD3002AD01 19 34 0.31 0.75 0.72 7264 OD1002AE03 16 47 0 60 7265 CD3002ALO3 17.3e 0.32 0.75 7268 001002AE05 14 14 0 67 0 60 0 54 7267 OD3002AE05 15 41 0 65 0.71 0 46 MEAN' 16 81 0.28 0 69 0.61 C et
$YD DCVIATION 1.78 0.06 0 11 0.12 0 14
- Mean la of esmples amtet then MD A.
t l l I s comrwsmurrunmnummm 35 28 of 48 REVISION 1
APPENDIX B t TABLE B 15 REAOTOR YARD SOIL SAMPLES AREA 2 MOUND D nas tsuen mn eau any GAMMA SPECTRUM MALYSES NUCLIDES pCIlg S&Wf%E ' K-40 Ce137 TI-206 Bl.212 Pk212 Bi-214 Pb 214 Re 224 Re.226 An-228 T42M Ce40 E*112 Ew154 NUMBE R LOCATION > 7132 CD1002BA06 0.33 035 0.85 0 as 0.60 7134 001002DB04 0 13 0.32 0 se 0.8a 0 na 7136 CD1002BB05 14.94 0.43 1.12 OD1002BB06 12.67 0 43 0.30 0 58 0.88 0.66 7138 0.32 0.26 0 85 0.67 0.78 0.90 0.94 7140 0010028907 7142 CD t002BC01 14 47 0.26 0.01 7144 0010028C03 14.95 0.37 OJ1 1.09 0 85 0 64 0.26 0.65 0.68 0 67 0.89 7146 CD1002DC04 7144 001002BCc6 15 57 0 17 0.67 .t s 001002BC07 15 16 0.25 0 94 0.68 0 58 7150 i 7152 001002BCD8 0.31 0.23 0.67 0.80 0.77 7154 001002DD02 17.60 0.29 1.00 ? 7156 0010029003 15 47 0.20 0.28 0.76 0 64 0.78 0010028D04 17.27 0.96 7158 7160 DD1002BD06 16 De 0.25 0.74 0.70 7162 OD1002BE01 13 00 0.25 0.61 0 63 0.78 t 7184 001002DE02 16 63 0 40 0.95 0 64 0.74 7166 001002BF03 0.27 0.73 0.83 0.65 716e CD t002DE04 0.23 0.70 0.72 0 67 7170 0010c2DE05 0.26 0.28 0 87 0 71 0 82 7172 001002DE07 12.94 0 23 0.26 0 75 0.70 0.50 7174 CD t002BE0a 0.22 0 31 0 62 0 63 0.73 7176 0010020T04 15.28 011 0.70 0.58 0 43 OD10C2BF05 0.21 0.36 0.22 0.77 0.74 7178 7180 DD t002DF07 17.96 0.76 0.72 0 64 7162 001002BG02 0 63 0 67 0.55 7164 CD10c2BG03 14 52 0.26 0 66 0.67 '
- 7184 DDiOO2BG06 15 26 0.25 0 81 0 61 0.64 7188 001002BG06 0.37 0 77 0 61 0.76 7190 CD1002BH02 15 40 0 71 0 64 0 61
+
7192 001002SH04 17.77 0.30 0 99 0.60 0.73 7164 OD1002DH05 0.24 0.54 0.57 0.01 15 64 0 29 0 63 0.51 0 82 .; 7196 001002DH06 0010020102 20.27 0.77 0.71 7196 1835 0 32 0,73 0 67 7200 CD1002DL6 7202 OD1002BJ02 16 17 0 57 0 48 0.63 f 7204 OD1002BJ03 17.04 0.30 0.72 0.61 0 75 CD1002BJD6 10 40 0.31 0 90 0 $9 0.66 7206 7208 OD1002SK02 16 64 0.a6 0 46 0.25 0 60 0.52 0.61 2 61 7210 CD1002DK04 7212 OD1002DK05 0.27 0.76 0 60 0 67 7 21' OD1002BLD2 0 29 0.66 0 65 0 $4 7216 001002BLD3 10 43 0.27 0.66 0.46 0 61 , i 0.28 0 30 0.73 0.76 0.67 0.71 2.01 0 43 0.94 MEM* 15 65 0 08 0 07 0 De 0 15 0 14 0.15 0 11 STD.DEVIA70N 2 73
. u... ,. er ,1.. .. u. uDr meumsnwrrurmmurmm5 29 of 48 REVISION 1
ANENDIX B T ABLE D 15 REACTOR YARD SOI. SAMPLES AREA 2 MOUND B (continued) nss t.ueu ms stoe na OAMMA SPECTRUM ANALYSES NUCLIDEs pCilg 5 AMPLE NUMBER LOCATION K40 C + 137 TL206 Bi-212 Pk 212 St214 Pb214 Me224 Re-226 Ae-220 Th234 DD3002BA05 15.51 0 28 0 69 0 56 0 65 7133 7135 0D30028B04 14.77 0.21 0 27 0 60 0.76 0 64 003302n805 15 40 0 28 0.70 0.96 7137 DD3002DB36 16.30 0 22 0 34 0.79 0.78 0 68 7139 7141 0030020807 15 53 0.33 0.51 0 02 0.82 C 96 DD3002BC01 14 04 0.21 0 69 0.78 7143 7145 CD3002BC03 14.04 0.34 0.78 0.76 0 69 7147 OD3002BC04 15.57 0.96 0.77 7140 CD3002BCOS 14.10 0 30 0.29 0.75 0 66 0 66 DD3002BC07 14 A4 0.28 0 25 0 57 0 80 0.58 7151 1 003302BC06 0 20 0.33 0 61 0 71 0.63 i 7153 1 CD3002BD02 13.27 0 as 0.64 7155 0030020D03 15 42 1.00 l 7157 17.65 0.36 0 63 0.52 ] 7159 ODMC2BD04 I 003/J02SDD6 16 00 0.31 0.31 0 67 0.66 0 65 7161 7163 0D33020E01 17.34 0.64 0 83 0 91 OD3002DE02 13 47 0 70 0 85 0 99 7165 7167 ODM02BE03 16 45 0.37 0 83 0.86 0 80 OD3002DE04 0 44 1.04 0 73 0 69 7169 003002DE05 0 27 0 40 0 60 0 75 0.93 7171 7173 DD3002DE07 15 47 0 36 0 00 0 67 033 ) ODE 2DE08 13.70 0 67 0 e6 0 88 7175 OD3002BF04 1275 0.31 0.75 0 64 0.63 7177 0.31 0.71 0.66 0.58 0 70 - 7179 OD30020F 05 7161 OD3032DT07 15.07 0.:2 0 b6 0.63 0.73 0.71 0 92 7 t 83 CD3002BG02 14 12 0.76 0.71 0 82 ! 7185 CDEC2BD03 14 42 0.31 0.24 0 78 7187 OD3002BG05 15 63 0.37 0.9 ) 0 94 0 69 0 63 0 50 l 7189 DD3302BGM 15 02 0 to 0 27 12 60 l 7191 OC30020H02 0 65 0 76 ) 7193 OD300$H34 20.05 0.35 0 81 7195 OD3002DH05 to 14 0 24 0 83 0E O 58 1197 OD30020HUC 17.06 0 29 0 83 0 71 0.50 7106 0D3002B102 17.37 0 50 0 52 0.53 7201 ODM02B136 1761 0.37 0 77 0.63 0 63 7203 DD3002BJJ2 P0.19 0.74 0.75-7205 OD Mc2BJ03 0 23 0.59 0 52 0 59 7207 ODM0;tuD6 0.32 0 90 C.71 0 60 7200 003302DK02 15 90 0.61 0 43 ODM02004 14.95 0 35 0 60 0 66 0.71 7711 OD3002BK05 18 05 0.05 0.27 0 79 0 09 0.72 7213 DDD0?DLD2 0 29 0 74 0 63 0.63 7215 ODM02hLD3 19 60 0.31 0 65 0 61 0.77 7217 0.26 0 30 0 73 0 76 0 67 0.71 2 81 0.63 0 94 MEAv* 15 65 2.73 0 08 0 07 0 08 0 15 0 to 0 15 0 11 STD.DTVJ.477DN
- Mean is of samples greater than MDA.
l 1 murummunuruunuta"" 30 of 48 REVISION 1
i APPENDIX B TABLE B-16 REACTOR YARD SOIL SAMPLES AREA 2 CISTERN
.<s,wou w uc.4mr G AMMA SPECTRUM AWsLYSES NUCLIDES pCs!g f,&WPLE NJWBER LOC ATION K -4 3 C e 137 T1208 Bi212 Pk212 bi-214 Pt-214 R* 224 Fie 226 Ae.22 0 Th234 Cee0 Ew152 Ev.154 7467 OU7A2AA01 55 53 0 62 0 60 7468 0'Jac2AA02 16 22 0 67 74$9 DU2002AAC3 16 35 0 26 0 71 0 59 0 62 7470 DU2002AAS4 14 05 0 69 7471 QU20C2AAOS 15.8' 0 63 0.72 0.70 7472 flUM2AB01 18 74 7473 OU2tC2AB03 17 40 0.51 7474 OU742A%A4 19 91 0 25 0 65 0 Se 0 59 7475 DU2002AT307 16 49 C.72 0 62 0.70 7476 0U2032ANie to 77 C 29 0 81 0.57 7477 DU2CC2AC01 15 12 0 66 0.74 0 67 0 67 7478 OU?X ACO3 lt$81 0.25 7479 OU7X2A004 19 43 0 70 7480 OUT42AC07 15 LS 0 64 7451 00M2ACOs 18 17 7482 OV742AC09 19 53 C .72 ,
7483 OU?002AD01 22 G-t 1 00 1 10 7424 Dd7t2ADC2 18 D6 0 61 7485 OV ?X2 AD' 4 16 G7 0 I? O 75 0 76 0 77 7456 OU 7 CAD 05 15 59 0 25 0 67 0 67 C 72 7457 f'U2302ADfi7 19 27 0 66 0 80 0 72 7468 DJ2002AD10 17 97 0.:S 0 60 C SS 0 80 20 15 1 D4 0 89 0 93 7499 DU2000AE C.3 { 74in DU272Af04 18 34 0 to C.57 C 63 C 50 0 48 7491 DV742A[?5 25 16 0 Z3 Cia 0 94 0 69 74s2 OU?x2ALC1 17 as 0 30 0 67 0 C3 C 67 74a3 OJ742 AL 99 17 46 0 79 74e4 OU20C2 AE 10 21es 0 35 07 C ia 09. 74 a5 DU2T2 AF03 16 64 74 MI OU2002 AF D4 20 44 0 81 7407 OU2002AF 05 22 21 0 36 0.71 0 84 0 68 7488 OUTX2.AF D9 K b3 C S2 7499 DU20CIAT 10 17.25 0 43 0 98 0 77 0 75 75 1 OU2002AG01 It ti 0 52 1.04 7501 DU ?302AG02 is 35 0 33 0 80 0 83 C B6 7W2 OU2%2AGC3 to 78 0 19 0 52 0.67 7503 007A2A3c6 23 30 C 35 0 68 1.19 1 13 7504 OU7.02AGC7 22 M 0 45 I 06 1 D3 1C2 1.t2 7K5 OV2302AW 18 64 0 23 0 73 C 67 0.79 7%M OJ7X 24405 19 91 0 42 0 D5 0.60 1 01
?M7 OV?I2AHO6 20 77 0 64 0 80 0 90 750s DJ?)o24407 16 33 C 23 0 72 0 97 7539 OU2002 AH'>6 19 64 0.32 1 00 0 81 0 91 242 1.02
?$10 OU7X2AH09 19 75 0 45 1.00 0 90 7511 OU7X2AH to 17 83 0 33 0 94 0 E3 C D' O ES 7512 DJ20C2402 15 63 0 05 0.75 0 79 7513 OU2002M36 16 64 0 29 0 R2 0 74 0 60 7514 OU742A07 K 33 0 34 0 64 C 80 0 85 0 93 0 70 0 &4 i 7515 DJ7x2AG8 17 45 7516 00M2009 19 23 0 35 C 63 0 75 0 54 00MLA110 17 41 0 37 C 72 0 89 0 91 0 81 7517 i
MEAN* 1s.71 0.22 0.79 0 75 0 52 2 42 0.68
$70 Dn 347DN 2 35 0 DB C 14 0 14 0 14 0 25 u.. .. 1 #. . 1., uwat N
%' # %unnxmumms 31 M 48 IEVISION 1
APPENDIX B
\
TABLE B-16 REACTOR YARD SOIL SAMPLES AREA 2 CISTERN .
%.nuseama suor ao GAMMA SPECTRUM ANALYSES NUClJDES pCilg SAMPLE NUWSfR LOCATION K 40 C+137 TL204 8b212 Pk212 B0214 Pk214 M*224 Me-228 A -228 Th234 Co 60 Ew152 Ew154 7467 OU2002AA01 15 63 0A2 0 80 7468 OU2002AA02 16.22 0 67 7469 OU2002AA03 16 25 0.26 0.71 0.50 0.62 7470 OU2002AA04 14.05 0 69 7475 OU2002AA05 15.87 0 63 0.72 0.79 7472 DU2002AB01 16.74 7473 OU2002AB03 17 40 0 51 7474 002002AB04 19.91 0 25 0.65 0 56 0 50 7475 0U2002AB07 16 49 0.72 0 62 0.70 7476 0U2002AB09 16.77 C.29 0.81 0 57 7477 OU200 TAC 01 15.12 0.66 7475 0U2002AC03 16 et 0.25 0.74 0 57 0 67 7479 OU2002AC04 14.43 0 70 7480 CO2002AC07 15 55 0.84 7461 OU2002 Acon 18.17 7482 002002AC09 19.53 0.72 7463 CU2002 ADO) 22 98 1 00 1.10 7464 002002AD02 16.98 0 61 74a5 0U2002AD34 it at 0 77 0.75 0.76 0.77 fees 0U2002AD05 15 50 0 25 0.67 0 67 0.72 7437 OU2002AD07 19.27 0.66 0 no 0.72 7468 OU2002AD10 17 97 0.25 0.50 0.80 040 7469 OU2002AE03 20 15 1.D4 0 69 0.03 7deo OU2002AE04 18 34 0.19 037 0 63 0 59 0 48 7431 OU2002AE05 25.16 0 23 0 56 CD4 0 BG 7492 OU2002AE07 17.89 0.30 0 67 0 63 0.67 74B3 OU2000AC09 17 46 0.79 7434 OU2002AE10 21.85 0 35 0.97 0 62 DD8 7495 0U2002AF03 18 64 7496 0U2002AFD4 20 44 0.61 74s7 OU2002AF05 22.23 0 36 0 76 0 64 0.68 7496 0U2002AF09 20 03 032 7499 CU2002Af to 17.2s e 40 0 98 0.77 0.76 7500 OU2002AQo t 21.61 0 12 the 7501 OU2002AG02 19 35 0.33 0 80 0.63 0.88 7502 OU2002AG03 16.78 0 to 0.52 0 67 7503 OU2002AG05 23.30 0.35 0.86 1.19 1.13 7504 OU2002A007 22 90 0 45 1.06 1.00 1 02 1.12 7505 OUFJ02AGC6 19 64 0.23 0.73 0 67 0.79 7506 0U2002AH05 1e 91 0 42 0 95 0.80 1At 20.77 C 64 0 sp ODO 7507 - OU2002AH06 7508 OU2002AH07 16.33 0 83 0 72 0 97 7500 CO2002AH00 19 84 0.32 1 00 0 et 0 91 242 1 02 75 t0 OU2002AH00 19.75 0 45 1.00 0.90 7511 OU2002AH10 17.83 0.33 0 64 0 e3 0 91 0se 7512 OU2002A102 15 60 0.65 0.75 0.79 7513 DU20c2A106 18 49 0.29 0 82 0.74 0 80 7514 OU2002A107 to 33 0 34 0 64 0 as 0 a5 7515 0U2002Af06 1745 0.63 0.70 0 D4 7516 0U2002At06 to 03 0 35 0 80 0.75 0 84 71l1 7 CU2002N10 17 41 0.37 0.72 0 as 0 81 CJ1 MrAN* 18 71 0.12 0.79 0.75 0 82 2 42 08s .
2
$70 DEVl47CN 2 35 0.04 0 14 0 14 0.14 0.25 m.o. w . r.4. uwDu i
coerumsmuntumxuummes 31 of 48 REVISION 1
TABLE B-17 REACTOR YARD SOIL SAMPLES AREA 2 SECONDARY SUMP usssonerms anse err OAMMA SPECTRUM ANALYSES NUCUDES pCity SAMPLE K-40 Ce137 tb20s Bb212 Pk212 Bi214 P&214 Re 224 R* 226 As-228 Th234 C. 60 te152 t#154 NUMBER 1.OCA710N Q32002B4D7 14 JO 0.30 DA1 0 65 0.78 7289* 7290 Q1200251A06 1422 0 24 0 75 0.53 0.73 7291 OU1002BA15 12.77 0.57 0.30 0 se 0.7e 0.72 7292 OU2J02BB07 16.87 0.31 0 43 0 50 0 80 14 82 0.30 0 56 0.75 0.75 0.89 7293 CU2002BS38 0U20028809 14.79 02 0 66 0 50 0.80 72D4 QJ20028812 14 47 0 29 0.73 0 59 0 64 7295 1845 0.33 1.00 0 62 0.75 1.37 O D9 7296 OU2002BB14 ' OU2002BC05 17.05 0.7f 0.78 0.71 0.77 7297 72s6 OU2002BC06 17.07 0.33 0.78 0 of 0.77 17 56 0.39 0 64 0.76 0.72 0.87 7299 OU2002BC00 18.01 0.38 0 51 0.6a 0.74 0.98 DOC OU2002BC10 OU2002BC11 18 99 03 0.77 0.71 0.74 037 7301 7302 Q12002BC12 16.63 - 0.34 0 85 0.01 0 88 fe et om 0 74 0 63 0.85 0.01 M03 OU20020011 22.04 0.32 0.be 0.87 0.s0 0.94 7304 OU2002DD12 OU2002BD13 1833 0 33 0.57 0.73 C AO 0.70 7306 QJ20CSD14 18.00 0.29 0.75 0.81 0.83 DOS 7307 OU2002BD15 16.10 0.26 0 60 031 0 54 15 81 0.2D 0 62 0 S4 0.36 7308 OU2002BD16 i OU2002BE12 23.46 0 2e 0 49 0 62 0.65 7 30s 21.10 0.46 1 14 1.00 1 32 1.48 7310 OU20020E13 7311 OU2002BE14 17.41 02 0.59 038 0 66 7312 OU2002BE10 18.39 02 0.57 051 013 7313 OU2002SF04 1732 0.27 0.79 0 64 0 64 7344 OU2co2BF06 15 68 0.25 039 0 81 0 66 OU2002BF07 18 02 0 41 0 64 0.76 0A4 0.95 7315 OU2002BF15 18 66 0.27 0.50 0.63 0.69 0.78 7316 7317 OU2x)$G01 19 16 0.32 0.70 0 63 0.66 0.32 0 40 0.72 0,75 7314 OU2002BG02 18 A3 CU2002DG05 18 3 0.25 0.83 0 61 0.73 3.31 7319 7320 OU2002BG07 19.30 0.29 0.67 0.70 0.67 7321 OU2002BGoe 15 82 0 19 0 de 0.57 0 60 7322 OU2002BG09 16 49 0.38 0 61 0.70 0.76 7323 OU2002BG10 18.77 0 45 0.77 a.E2 0 83 0.21 033 045 0.57 0 64 7324 OU2002BGti 17.52 7325 OU2002BG12 16.21 0.21 050 0 42 0.62 7326 OU2002BG13 15 62 0.32 0.70 0 66 0 60 OU2002BG14 16.98 0.30 0.79 0.64 0.91 7327 to 41 0.34 0 95 0 64 0.85 1.04 732s OU200sG15 7329 OU20020H03 16.h 0.22 0.72 0.54 0.73 OU2002DH04 17.s4 OR 0 74 0 85 055 0.85 7330 7331 OU2002BH05 10.75 03 0.78 0.09 0.84 7332 OU2002SH06 16.16 0.67 055 0 62 7333 ' OU2002BH07 15 65 0.22 - 0 60 0.73 7334 ' OU2002DH06 15 95 0.33 0 75 0.65 0 44-OU2002DH10 15 32 0.30 0 6v 0.58 0.70 7335 j OU2002DH12 18.32 0 26 0.73 0.74 0 64 t es 733e* 7337 OU2002BH13 17 2 0.27 0.74 0.64 0 53 7338 OU2002B101 1655 0.21 0 47 0.42 0 43 7 330 OU2002 Blue 16 63 0.82 0 60 0a5 OU2002 Bio 7 1742 0.26 0 65 0 53 0 62 0.71 7340 7341 OU2002B109 15 61 0.22 0.47 ' O.50 0 58 7342 CU2002Dit t 15.76 0 22 0.44 0 de 0 59 7343 002002B112 16.06 0 26 0.48 0.72 0.60 OU20028t13 15 96 0 29 037 0.00 0.75 0.98 7344 7345 002002B115 17 93 0.32 c.70 0.79 0 80 D4e OU2002Bl16 17.03 03 0 68 0.83 0 59 7347 OU2002BJD4 15.76 0.22 0.57 0.76 0 64 OU2002BJ05 17.06 0.30 0.56 0.64 0 63 7346 OU200.!BJ07 16 60 0.19 0.80 0.61 0.78 0 95 7340 7350 0U2002658 18.38 0.29 0.75 0.51 0 81 7351 OU2002BJ10 14.80 0.19 0.48 050 0.00 OU2002BJ12 15 57 0.18 0.72 053 0 65 0.81 7352 7353 OU2002BJ13 15 12 0.P1 0 82 0.59 055 OU200$J16 17.51 0 29 0 et 0 50 0.50 0.78 7354 14 40 0.26 0.69 0 82 0 62 0 68 7355 ' OU2002BK04 7354 OU2002BK06 17.63 0 29 0.75 0 60 0 68 7357 OU2002BK00 1720 0.27 0.64 038 O so ' 7358 OU2002BK10 15.76 0.24 0.74 CAO 0 59 7359 OU2002DK13 16 75 0.#4 0.71 0.65 0.70 7360 OU2002BK14 17.38 0.34 0 66 - 031 0.76 7381 OU2002BK15 15 40 02 0 66 0.46 0 44 7382 OU2002K16 17.23 0.21 0 65 0.90 053 OU2002HLD4 16.77 052 0.60 0.73 7363 7364 OU200SLOS 17.46 0.33 0 57 0 es 0.65 OU2002BLO7 15.11 0 24 0 64 0 60 0.56 7365 7366 OU2002DLDS 14 40 0.23 052 0.81 0 47 7367 OU2002B1.10 17.61 0 28 030 0 72 - 0 13 0.59 7365 OU2002BL11 15.85 0.29 0.60 0.53 0.71 7360 OU2002BL12 15.33 0.31 0.67 0 63 0 68 7370 OU2002DL15 16.33 0.24 0 83 0 68 - 0.54 16 96 047 0.28 0.68 0 65 0.66 1.37 2 49 0 00 ME 4N** 0 06 0 14 0 12 0 15 1.17 0 17 STD DfW4 TOM 1 75
. _ m ,4 ..%
wrumsmwrmwmmes 32 of 48 REVISION 1
APPENDIX B O Bldg 100, Yard Area 0, Dirt Mound A Direct Alpha Survey of Soil - 3* xxam Abha cbm/ 200 sr g 100 q 0 gogg waggagg gwo agoggwwwa -
-100 5 . iiii>ii .iiiiiiiii>>>iiii bA bOOOAO bOOOA Survey Mecruement Lccat'm Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary for 10:13 am Bldg 100, Yard Area 0, Dirt Mound A dpm/100 sq. cm. ,
95% Confidence Level Upper Bound on Mean Maximum N Radiation Mean
-10 -8 1 28 Alpha File Name for this graph: RYOARA .EPS r,
Figure B-10 Area O Mound A Direct Alpha Sun'ey Results O
""*"""" Page 33 of 48 REVISION 0
1 APPENDE B l i I f x Bldg 100, Yard, Pipe Chase Trench I Direct Alpha Survey of Soil 1 1 m _ Abha ctm/ a g 100 m k O bd2 d- n 03 S-a -be- om-tuc",- U- om -mane
-100 i,. oimi o.... i........i... ....i. ......i. .. ... .....
000PCHOF01 000pCHOF01 000PCHOF01 000PCHOF01 000PCHOF01 000PCFl0F01 000PCHOF01 Surwy Memurtment Lccatbn Codes (D D 3/24/93 Alpha Radiation Measurement Statistical Summary 10:17 am for Bldg 100, Yard, Pipe Chase Trench dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N
-3 -1 16 60 Alpha File Name for this graph: RYPCRA .EPS Figure B-11 Area O Pipechase Direct Alpha Survey Results h
mmn.r w.sn w sxucs " Page 34 of 48 REVISION 0
APPENDIX B (- ~/ Bldg 100, Yard Area 1, Dirt Mound A Direct Alpha Survey of Soil 3m KX>^XXX] Abha dpm/ 200 N a g 100 t O v ,'. . . . . . 'l- c,. ,'. . . . ,',, .wc4b'.'-we
-100 p ,
pi.,umu..7....
...e.re.-.~...p.m.m.i...p.. -> p. 4.-.y ODOOO1 AF01 ODOOO1AF01 CDOOO1AF01 ODOOO1AF01 0D0001 AF01 CDOOO1AFD1 0D0001AF01 ODOOO1 AF01 Survey Memurement Locatkn Ccdes O 3/24/93 10:14 am Alpha Radiation Measurement Statistical Summary for !
Bldg 100, Yard Area 1, Dirt Mound A dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha -7 -6 23 164 File Name for this graph: RY1 ARA .EPS Figure B-12 Area 1 Mound A Direct Alpha Survey Results O 1
" " " * " " Page 35 of 48 REVISION 0
APPENDIX B O Bldg 100, vara Area 1, Dirt Mound B Direct Alpha Survey of Soil
' wxocoa Abba ctm/
200 a g 100 R V O o , W ,, , ." ." d ek .m EL . ' ' - A!E --J h N '. 8 4
-100 p in .n. n n o pn u. u n ni pin n o n in. in o n.u nn .p ..o n..n...in n nu.n np u ui nn iui 000001BF01 ODOOO1BF01 ODOOO1BF01 OD0001BF01 OD0001BF01 OD0001BF01 OD00018F01 ODOOO1BF01 Surwy Mecrurement Loccfrn Ccen O 3/24/93 10:15 am Alpha Radiation Measurement Statistical Summary for Bldg 100, Yard Area 1, Dirt Mound B dpm/100 sq. cm. ;
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N ) l' Alpha 4 6 43 106 l i File Name for this graph: RY1 BRA .EPS l Figure B-13 Area 1 Mound B Direct Alpha Survey Results , 1 O
"'""""" Page 36 of 48 REVISION 0
.I
APPENDIX B N CJ Bldg 100, Yard Area 2, Dirt Mound A Direct Alpha Survey of Soil
'* vx moa .
Abbacbm/ t 200 a g 100 m E O 3-U-a a 3 "'a ""et- a b 0a~~-a
-100 i...i .i...i...i...,,..i OD0002AF01 OD0002AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 ODOOO2AF01 CD0002AF01 Surwy Mecmremmt Locatbn Codes O 3/24/93 Alpha Radiation Measurement Statistical Summary for 10:15 am Bldg 100, Yard Area 2, Dirt Mound A dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 3 7 30 28 File Name for this graph: RY2 ARA .EPS Figure B-14
/ rea 2 Mound A Direct Alpha Survey Results O
omtrwarrnwmo m Page 37 of 48 REVISION 0
APPENDIX B O Bldg 100, Yard Area 2, Dirt Mound B
~
Direct Alpha Survey of Soil 3 xxx> coa
' Abho cbm/
2T N a 8 15 e o vm w w s w m e m - v v ^ va ner
-100 p o . . o p i o o . . . . . . . o p i . . o o p . o o i o i p o . o . . . . o i OD0002BF01 OD0002BF01 OD0002BF01 000002BF01 OD0002BF01 ODOOO2BF01 000002BF01 Surey Memurement Locxfon Codes ca ,,,,,,, ,1,,, ,,,1,,1,, ,,,,,,,,,,, ,,,,,,,1,,1 s, ,,,
10:16 am for Bldg 100, Yard Area 2, Dirt Mound B dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha -16 -15 - 13 72 File Name for this graph: RY2 BRA .EPS Figure B-15 Area 2 Mound B Direct Alpha Survey Results O
* * * " " "
- Page 38 of 48 REVISION 6
~ APPENDIX B Bld.g 100, Yard, Cistern 242 Trench Direct Alpha Survey of Soil KXXXXX]
Abha rim / 200 b a " g 100 mE O l I ' ~ " U b "- "#""'- ~ 0 - - l- --
~100 pio , u m , p . o u , ,, o p , , ,,, o i,, p . o m o . . p o o , u m p , o . . . ,opooon, poi, CUOOO2AF01 OUCOO2AF01 OUOOO2AF01 OUOOO2AF01 OUOOO2AF01 OUCOO2AF01 OUOOO2AF01 OUOOO2AF01 Suney Mecmment LocdJcn Co&s O 3/24/93 Alpha Radiation Measurement Statistical Summary for 10:12 am Bldg 100, Yard, Cistern 242 Trench dpm/100 sq. cm.
95% Confidence Level Radiation i. ; Upper Bound on Mean Maximum N Alpha 6 8 52 90 File Name for this graph: RYCIRA .EPS Figure B-16 Area 2 Cistern 242 Trench Direct Alpha Survey Results j 3
) ! " " " "#*2* Page 39 of 48 REVISION 0
APPENDIX B O Bldg 100 Yard Secondary Sump Trench Direct Alpha Survey of Soil KM4 Abha ctm/ 200 s g 100 m I ' ' L " ' O [ [A T' I I "" f[ I ' '- I ' l'
-100 .i . .. .. . .r ....r . .. .. . . . .i .. . .. -."r" >=' ' - ' r " a '""'''i b 01SurwybMeccummet JF LocdJm Codes rmR bF01 O 3/24/93- Alpha I.adiation Measurement Statistical Summary 10:18 am for Bldg 100-Yard Secondary Sump-Trench dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Alpha 12 14 88 162 File Name for this graph: RYSSRA .EPS Figure B-17 Area 2 Secondary Sump Trench Direct Alpha Survey Results O
" " " " *"5" Page 40 of 48 REVISION 8
APPENDIX B l b Bldg 100, Yard Area 0, Dirt Mound A Direct Beta Survey of Soil ; 15 ,, D;m/100cm2 10 IJ Al r Lf
- hlII' b.k2.k d J ku alid alti m g
-5 p...m ...m.o r.imm m u.u 7 m o .m m.y m u oi... ...m y.m ...... .m 3m m .m.o...y."m..... .m y m n CDOOOOAF01 ODOOOOAF01 ODOOOOAF01 ODOOOOAF01 CDOOOOAF01 ODOOOOAF01 . ODOOOOAF01 ODOOOOAF01 Survey Manrerret LocatJon Codes 3/24/93 Beta Radiation Statistical Summary 9:05 am for Bldg 100, Yard Area 0, Dirt Mound A dpm/100 sq. cm.
95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 727 792 2324 140 File Name for this graph: RYOARB .EPS Figure B-18 Area O Mound A Direct Beta Survey Results [D v _ manrummmmmm Page 41 of 48 REVISION 9 F m-
APPENDIX B' I 7d Bldg 100, Yard, Pipe Chase Trench , Di. rect Beta Survey of Soil 15 , Dpm/100cm2 10 g 5 r o b.AfjdL1df4 ufuihhlff l AlbldLf11 AldRJd,thIIIh
-5, , , , , , , ,.
ObCHOF OCbPCHOF OF ObCHOF01 Surwy Measurement ta:ct'rn Codes () 3,24,,, 9:10 am e.ma ,,di,,1,m Se,,1.,1ca1 s,mma,, for Bldg 100, Yard, Pipe Chase Trench dpm,100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 699 740 1871 304 File Name for this graph: RYPCRB .EPS Figure B-19 Area O Pipechase Direct Beta Survey Results O : c30892-runstmeratxsc25." Page 42 of 48 REVISION 0
APPENDIX B O Bldg 100, yard Area 1, Dirt Mound A Direct Beta Survey of Soil .
'15 Dpm/100cm2 j 10 N
g 5 t , > ! . ', 6,;}'jf O , pu H11bdIldd EllO} ah'(hhflbMM$ e s
, w - n
-5 . , , , ,
COO 1 AF 1 O OOO1AF 1 b 1AF 0 OOO1AF01 Surwy Mecourement Lcx:ctim Codes O 3/24/93 Beta Radiation Statistical Summary 9:06 am for Bldg 100, Yard Area 1, Dirt Mound A dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 535 566 2071 820 File Name for this graph: RY1ARB .EPS F Figure B-20 Area 1 Mound A Direct Beta Survey Results O
"""""* Page 43 of 48 REVISION 6
. . _ ~
APPENDIX B Bldg 100, Yard Area 1, Dirt Mound B Direct Beta Survey of Soil 15 Dpm/100cm2 10 N sr 8l 5 Nkbdd' Jb 2H} o 1. di,dLiddilkd!.!dhtd
)
r n - E1lMOSI c >
-5 ===== , ==1====== p= - - , =, ,
OOO1BF OOO1BF OOO1BF BF01 Suney Mecourement LecdJon Codes O 3/24/93 Beta Radiation Statistical Summary , 9:07 am for Bldg 100, Yard Area 1, Dirt Mound B dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Beta 589 626 2268 520 File Name for this graph: RY1BRB .EPS Figure B-21 Area 1 Mound B Direct Beta Survey Results O 4 mor9numsmnw.ano25.ao Page 44 of 48 REVISION 0
2 ,a L a . APPENDIX B e O Bldg 100, Yard Area 2, Dirt Mound A Direct Beta Survey of Soil 15 , Opm/100cm2 10 b sr# ' g 5 j I d idJIb . no A ist dJk .d d gdl g 4]h O f I
-5 r. .. m " .m r . . . ." .....o r u. . " . . . . ~r..- .. m.~r e ..- u mi"o m m-m c - ii-o.myii".
ODOOO2AF01 OOOOO2AF01 ODOOO2AF01 ODOOO2AF01 CDOOO2AF01 ODOOO2AF01 ODOOO2AF01 - ODOOO2AF01 Surwy Measurement t.cedJcn Cochs O 3/24/93 Beta Radiation Statistical Summary for i 9:08 am Bldg 100, Yard Area 2, Dirt Mound A , dpm/100 sq. cm. 95% Confidence Level i Radiation Mean Upper Bound on Mean Maximum N - Beta 667 727 1617 140 File Name for this graph: RY2ARB .EPS Figure B-22 Area 2 Mound A Direct Beta Survey Results O
""*"""#"* Page 45 of 48 REVISION 0
_ _ _ - _ - - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - = _ - - - _ .
APPENDIX B' i O Bldg 100, Yard Area 2, Dirt Mound B Direct Beta Survey of Soil i 15 Dim /100cm2 10 h g9 5 t O b ' ' I t
-5 ; , , , , , , r <
b aF1 0002BF 1 b2LiF01 - Surwy Mecourement Location Cochs O 3/24/93 Beta Radiation Statistical Summary 9:09 am for l
.P Bldg 100, Yard Area 2, Dirt Mound B dpm/100 sq. cm. I 95% Confidence Level ,
Radiation Mean Upper Bound on Mean Maximum N Beta 552 588 2061- 360 File Name for this graph: RY2BRB .EPS Figure B-23 , Area 2 Mound B Direct Beta Survey Results
" " " * " " " Page 46 of 48 REVISION 8 !
i l'
APPENDIX B n V Bldg 100, Yard, Cistern 242 Trench l Direct Beta Survey of Soil 15 Dpm/100cm2 10 N g 5 -
- EWtIIL Mlldibdhtd /LildWiklkhlf I
hlbd d%Id D ' - 4 i r 4
-5 n=- , , , , ,
bF 2A O Surwy Mcxnrement Locatkn Co&:s 01 F01 O' 3/24/93 Beta Radiation Statistical Summary 9:04 am for Bldg 100, Yard, Cistern 242 Trench dpm/100 sq. cm. 95% Confidence Level Rad 3ation Mean Upper Bound on Mean Maximum N Beta 878 923 2446 449 File Name for this graph: RYCIRB .EPS l Figure B-24 Area 2 Cistern 242 Trench Direct Beta Survey Results O
" " " " " " " Page 47 of 48 REVISION 0
APPENDIX B o O Bldg 100 Yard Secondary Sump Trench Direct Beta Survey of Soil - 15 Dpm/100cm2 10 {$ 9 g 5 o h.I
-5, , , , , ,
1 r AF b )OO2BF01 Suney Memurcment Locatbn Codes O 3/24/93 9:11 am Beta Radiation Statistical Summary for Bldg 100 Yard Secondary Sump Trench dpm/100 sq. cm. 95% Confidence Level Radiation Mean Upper Bound on Mean Maximum N Deta 1419 1465 3902 800 File Name for this graph: RYSSRB .EPS Figure B-25 Area 2 Secondary Sump Trench Direct Beta Survey Results O 3=nmana m2m Page 48 of 48 REVISION 9
1
-l
-l -
v' O ( f l 4 l APPENDIX C l BACKGROUND DATA I i l 6 O l l [. '
APPENDIX C. (^') v l I l l l l l APPENDIX C n U BACKGROUND DATA I 1 7% i (') OX893-MTB'SrnAMTL\fMJUG026.RD REVISION 0 l l
APPENDIX C APPENDIX C pl
' Background Data Soil Background Thirty-six soil samples were taken offsite to develop a background action level for soil onsite. The locations of these samples were determined in accordance with the Decommissioning Plan. SE;6fil piii@aysa@((@phj{ufl6iisTsiEisf95F67fakEiiK6IEti165sti6ii. Soil samples were analyiidior gross beta and alpha activity, and gamma spectroscopy was perforrned for nuclide identification and activity in pCi/g. DifesfsipEsiid bisikdisil6iiniesidFdihE5ffWeisisksi~siss6til66 Ail 6iil Tlisis nicasnfinibriis[c561dibsjussi $td[dktset;. contamination { bdt @ere[n66 $dhuate116{qdannfylilis concentratiogjof radioactiv6Lmalerialjin thelsoill All data a:e presented in tables which list the activity, mean and standard deviation. The action level was then calculated as the mean plus three times the standard deviation.
Samples are identified by the sample number (shown on the area map) and location code. This code was determined by the distance from the reactor (0.5,1.5 and 3.0 km) and the radial direction (e.g. 150*). Building Background A series of gamma measurements were taken in an effort to determine the background radiation level in Building 100. These measurements were made 1 meter from concrete surfaces in buildings where licensed radioactive materials were not used or stored. Four separate buildings (on the AMTL site) were used for this determination. The data for this background determination are presented in graphical form, both by individual ! building and as a single population. The population mean and standard deviation accompany each graph. 1 l I i I 1 O asom rumsnwmm.axwwm*6 Page 1 of 14 REVISION 1 l
APPENDIX C I @8 b i$N I MIN ki' hkkh []Nj% fG'Cd'Sk[b Nk $ h. ' Y ,, . . .^' ?h$ Nh*.f.?'fl.k.'5nA =
./~g ff bhi 's. .
,+" E 2
; ./
Q . . ~ \;j L 2 e , , ' ' " " - ./ h K ' ', jrd. ..>Sj Si 4( C
%f ' 'i " "yE
'qt. 't s "T
. 9 1
,( I k
. k " d . [ f f ! d h hkIhd[Og e .kh5
'. y y - . .
71 - 7 t, g, h k }fl h"w*T*f'hiy L) I * '
' '*y
}
E$! -.N . , d,Fi y,l- Q"$ h,.?p',[-s,.3 M; Q~s~ by; fh.!sM}dk t d.
.gk bh .mV@@gq,I6 t ., . ,
I i
- 2 b
. ,, ,,,. g ...},~, .
Y h$$Q'%r'?> f Qyg Z'hk N 3}f W =si Z SLl P.1: ~T3sf.hhhb[ b) - f' 5&~J . Y< I k> -
- w. 3%- % ' "-
&y*
-y,K
%. . 5Adie
. . : < W Q' ' ' , : hk'=&' ,; ~ fp sghh -Q- . 4 hiIhhh5)g'd+kgQCC s.,a L fm . -0'c 2; ff% ;yy sgl 4 &e. \ ~l
? .M %
f g 'E &?)]?5?E1?f.kl'W k $<f K ;l fip ^% 4 E &{..ijffMs~4' .~ % ' ,' ~
. ~
3 y h: R Q .
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f . k k' j .i k sQ\% 9 h T r > 7 4 8 $. 7 a /mj7'4' un( pp> Ww-h[ee1 W)l f Ed My < red^ q b4' gan ,p.'cm ! g.
$almt)d&p;%k3"$5L?bk$,.
vu 3< ; n bd WN$py..., ^ $Y} %. $ :W,hg o,... h* &g j ';td5P
'$w Figure C-1 Off Site Soil Sample Locations aum n msmumanmmme " Page 2 of 14 REVISION 0
APPENDIX C Table C-1 Off-site Soil Sample Locations Sample Location Number Code Location 1 P05000 Front of 14 Hosmer, Watedown (city property) west of Boylston St. 2 P05030 Side of 18 Putnam, Watertown south of Hazel St. 3 P05060 Cypress /Quimby intersection, Watertown (city property) north of Boston Edison 4 P05090 Northeast corner of AMTL, south of main entrance 5 P05120 In Arsenal Park, Watertown (city property) near picnic area, ball field 6 P05150 Across from 46 Newton, Newton (city property) south of railroad tracks, Charles River 7 P05180 East of MDC football field on Charlesbank, Newton (city property) 8 P05210 In front of MDC skating rink on Charlesbank, Newton (city property) 9 P05240 Side of 328 Charlesbank, Watertown (city property) at Pequossett St. 10 P05270 Front of 96 Beechwood, Watertown (city property) south of Beacon St. I1 P05300 Front of 30 Frank, Watertown (city property) west of Louise S t. 12 P05330 Front of 136 Walnut, Watertown at Cypress St. 13 P15000 Front of 29 Commonwealth, Watertown (city property) south of Belmont St. 14 P15030 Front of 56 Salisbury, Watertown (city property) 15 P15060 Front of 133 Grove, Watertown (city property) south of Mt. Auburn St. 16 P15090 Old Arsenal property, Watertown on Greenough St. 17 P15120 Front of 117 Murdock, Boston at Cushman St. 18 P15150 Peters Park, Boston (city property) across from 21 Rogers Park Ave. O ownrumsnw.nur"" "" Page 3 of 14 REVISION 0
APPENDIX C Table C-1 Off-site Soll Sample Locations (continued) Sample Location Number Code Location 19 P15180 Park across from 375 Faneuil, Boston (city property) 20 P15210 Front of 15 Nonantum, Newton at Road St. 21 P15240 Front of 8 Eldridge, Newton (city property) south of Elmwood St. 22 P15270 Front of 66 Capital, Newton (city property) east of Galen St. 23 P15300 Side of 91 Church, Watertown at Palfrey St. 24 P15330 Front at 119 Robbins, Watertown at Bellevue St. 25 P30000 Front of 22 Bow, Belmont (city property) 26 P30030 Front of 17 Bright, Belmont (city property) 27 P30060 Side of 157 Brattle, Cambridge (city property) on Appleton S t. 28 P20090 Front of 7 Rena, Boston at Travis St. 29 P30120 Across from 1302 Commonwealth, Boston (city property) at Griggs St. 30 P30150 MDC Pool / Park, Boston (city property) at Beacon and Chestnut Hill Sts. 31 P30180 South of parking lot at Boston College Football Field, Newton (city property) 32 P30210 Front of 286 Ward, Newton at Grant St. 33 P30240 In Cabot Park, Newton (city property) west of ball field 34 P30270 Front of 103 Bridge, Watertown at Chandler St. 35 P30300 Front of 103 Chapman, Watertown (city property) at Grandview St. 36 P30330 Side of 91 Waverly, Belmont (city propeny) at Irving St. O v mom rumsmurnuwacas. Page 4 of 14 REVISION 0
APPENDIX C k TABLE C 2 OFFSITE BACKGFOUND SOIL GAMMA SPECTRAL ANALYSIS RESULTS O AMMA SPECTRUM NUCLIDES pCHg w t.mnm eau w
$AnoptE Ce40 fe152 Ee154 NUMotR LOCATION K40 C e137 71200 Pt>210 50212 ' Pb-212 81214 Ptr214 Re.224 Re.226 Ae-226 7h234 0 25 2.99 0 41 0.66 0 55 0 60 1.75 0 63 4502 Po%00 13 47 1.19 1 90 0.56 0 66 0.68 0.72 0.73 2.24 0.81 0.59 4149 P05::30 13 02 0 57 0.31 0 57 C 00 0 60 0 60 0.75 2.04 0.70 1.24 4604 P050eo 14 64 1.85 0 77 0 29 23 0 59 0 85 0 05 0 65 0.75 2.17 0.78 0 91 5054 P05090 14 34 0.20 0 ml 0 43 0 43 1.14 0 54 4150 P0512D 17.53 0 05 0 22 0.33 0.72 0 51 0.45 0 47 1.20 0 85 0 se 5056 P05150 15 91 0 41 0 75 0.19 0.26 0.65 0 51 042 0.76 0.73 4146 P05180 16.64 0.30 1 47 0.57 0.77 0.60 0 63 1.70 0.83 1.17 4147 P05210 19M 0.09 0.59 0.65 1.76 0.74 1,21 POS240 15.63 0.14 0.25 0 43 0 89
$056 0 57 1.20 c.82 0.67 0 66 2 53 0.85 1.69 4643 P057/0 21.94 0 00 0 42 om 0.37 0.76 0 63 0 63 0 43 2 19 0.70 4144 P05300 15.36 0 25 0.12 0.31 1 S2 0.31 0.97 0.74 0.71 036 1.72 0.66 0.76 4646 P05330 17.72 0.95 0.30 0 46 0.70 O s0 0.73 1.00 DAO 4690 P15000 1441 03 1.96 0 40 0.71 0 49 055 0.57 1.76 0.70 0.34 5055 P t5030 13 98 0 16 0.23 1.30 0 62 0 45 030 1.36 0.62 0.66 4144 P15000 15 46 0 19 0.30 02 0 65 0 55 0 55 1 46 017 4151 P15090 15 64 0 54 0.64 0.67 0.70 2 06 0.76 1.06 ILN4 P15120 16.46 0 03 0.31 0.31 2 57 0.50 1.05 0.72 0.71 2.14 0.63 5052 P15150 13 50 0 40 0.36 0 03 0 01 0 50 0.53 1,91 0,70 5053 P15160 15 47 CE 0.29 2.07 0 50 0.93 0 61 0 63 1 69 0.05 1.04 4621 P15210 16 85 0.36 0 30 4 04 0.50 0.74 0.53 050 0.51 1 62 0.72 0 59 5059 P15243 15 30 0.34 0 28 0.26 0 45 0 82 0.56 036 0.61 1.31 0.67 0.96 5000 pts 270 14 57 0.54 055 0.87 0.62 0 63 0.56 2 04 0.70 0.99 4154 P15300 13.01 0.36 03 2.16 3 23 0.60 1.36 1.07 1.21 0.83 3 20 1.23 1.00 4695 P15330 19 53 0 45 0 43 0.27 139 0 44 0.74 0.54 0.56 0 55 1.60 0 68 0.70 5095 P30000 15.06 0.30 237 014 0 63 0 61 0 67 2 10 0.71 0 82 5696 P30030 14 92 1.12 0.30 0.34 0 65 0 55 0 44 1 43 0.69 1.17
'47 P30060 14.73 0 27 0 if 0 63 1.09 0 93 0.96 0.78 1.96 1.03 1.71 5091 PyJoeo 15 40 0 49 0.36 0 40 ' O.30 0 52 0.95 0 68 0.72 0 46 1.91 CJT 1.21 5002 P30120 15 91 0.62 0.31 0 41 0.74 0 67 0.70 0,86 2.18 0.62 5093 P30150 15 19 0.15 0.34 0 66 0.68 0.72 0.72 0.90 2.11 0.64 013 4145 P30160 18 05 0 60 037 0.76 2 16 0.70 1.06 4'52 P30210 13.02 0 43 OD 1.87 0 41 0.61 0 46 0.24 1.2s 0 43 0 65 0.58 0 55 0.58 130 0.56 4 t53 P30240 16.24 0.37 0.71 1.10 0 64 0 68 0.75 2.21 0.03 1.10 4589 P30710 16 25 OM 2 29 0.31 2 40 0 es 0.00 0.74 0 64 059 1.88 0.69 0.74 4667 P30300 17.78 0.no 2.39 0 23 0 62 0 48 0 53 1.58 0.50 0 85
. !007 P30110 15 04 0 2D 0 25 0.63 0 t.6 0.% 1,66 0.76 QM MIM' 15hl G.42 0.2fd 2.26 0.4w 0 . 71 1 0 40 0.13 0.32 0.37 0 05 0 64 0.13 0 22 0.13 0.15 0.14 STD D0/14704 1.82 0 44 4 20 0 se 1 47 1.02 1 11 i C7 3 De 1 15 1 92 8KGD Lfvn 21 23 1 53
. . ~ . . ~
osmrummuunuwunurmas Page 5 of 14 REVISION 1
APPENDIX C *
+
TABLE C-3 f r E OFFSITE B ACKGROUND SOIL GROSS ALPHA / BETA ACTIVITY INST: LB5100#1352 ALPHA ANALYSES BETA ANALYSES CAL.DUE: 08/18/93 > SAMPLE MASS MDA Activity MDA ACTIVITY NUMBER LOCATION (g) (pCl/g) (pCl/g) (pCl/g) (pCI/g) 4692 P05000 0.684 1.09 0.54 3.55 26.24 , 4149 P05030 0.541 1.24 2.43 4.28 19.73 4694 P05060 0.536 1.39 1.26 4.53 24.48 P05090 0020 41.54 -10.93 132.16 -143.00 5054 4150 P05120 0.348 0.92 1.70 4.49 28.61 P05150 0.027 30.77 -2.43 97.89 -105.93 5056 4146 P05180 0.529 1.27 2.07 4.38 27.37 4147 P05210 0.451 1.48 2.42 5.14 23.27 P05240 0.412 1.80 2.49 5.90 27.94 5058 4693 P05270 0.636 1.17 1.17 3.82 27.66 4148 P05300 0.359 1.87 3.05 646 31.07 , 4688 P05330 0.024 34.61 2.73 110.13 99.06 P15000 0.166 4.48 0.53 14.64 18.41 4690 P15030 0.845 0.88 0.80 2.88 23.63 5055 P15060 0.368 0.87 2.02 4.25 27.40 f 4144 4151 P15090 0.468 1.43 1,73 4.95 31.70 e 5094 P15120 1.258 0.59 0.89 1.93 23.93 P15150 1.028 0.72 1.72 2.36 24.71 5052 5053 P15180 0.794 0.94 1.21 3.06 24.85 4691 P15210 0.293 3.47 0.97 7.09 29.47 P15240 0.051 16.29 3.00 51.83 -25.59 5059 5060 P15270 0.466 1.59 1.92 5.21 23.82 P15300 0.129 5.19 8.48 17.97 27.71 4154 4695 P15330 0.244 3.05 4.21 9.96 23.74 P30000 0.033 25.17 -11.26 80.09 -72.04 5095 P33030 0.047 17.67 3.28 56.24 -34.23 l 5096 1 P30060 0.029 28.64 -9.80 91.14 -86.29 5057 P30090 0.391 1.90 4.87 6.21 32.64 5091 P30120 0.696 1.07 0.85 3.49 24.32 i 5092 1 P30150 0.557 1.33 0.82 4.30 25.90 , 5093 0.44 0.67 1.52 19.97 l 4145 P30180 1.525 4152 P30210 0.471 1.42 3.57 4.92 28.46 .l P30240 C.302 2.22 2.90 7.67 28.82 4153 P30270 0.015 55.38 -18.95 176.21 162.07 4689 l 4687 P30300 0.019 43.72 14.98 139.11 -137.36 l P30330 0.033 25.17 4 61 80.09 -88.29 5097 MEAN: 0.48 MEAN: -7.72 STD.DEV: 5.89 STD.DEV: 59.67 l l i
-l 030mrusummnumaxwam016 Page 6 of 14 REVISION 1 l i
APPENDIX C Table C-4 Off-Site Gamma Exposure Rate at 1 Meter ( R/hr) Addras Average StA Dev. Number of Mensuresnents f Imcation Code 0.5 km North,14 Hosmer 10.6 0.8 21 N5000 0.5 km NNE,18 Putnam 12.7 0 1 105030 0.5 km ENE, Quimbly/ Cypress 12.9 1 20 P05060 0.5 km West, NE Corner AMTL 13.4 0.5 20 P05090 P05120 0.5 km ESE, Arsenal Park 12.8 0 1 0.5 km SSE,46 Newton 10.8 0.8 20 F05150 0.5 km South, East of MDC Field 13 1.2 21 F05180 0.5 km SSW. MDC Skating Rink 13.2 0. 8 21 P05210 0.5 km WSW,328 Ct.arles Bank Rd. I1.4 0.7 20 P05240 0.5 km West. 96 Beechwood 12.8 0.6 20 N5270 0.5 km WNW,30 Frank 12.2 1.2 18 N5MO 14.7 1.6 21 M5330 0.5 km NNW.136 Walnut St. 1.5 km North,29 Commonwealth 11.7 0.4 20 P150r10 1.5 km NNE,56 Satisbury 9.5 0.5 20 P150M 1.5 km ENE,133 Grove 11.5 0.7 40 P1504) 1.5 km West, Greenough Blvd. 11 1 40 P15090 1.5 km ESE,117 Murdock 11.4 0.7 20 P15120 1.5 km SSE, Rogers Park Ave. 9.5 0.4 20 Pl5150 0.6 20 ( Pl5180 1.5 km South Hareman Park 10.4 12.4 0.3 20 P15210 1.5 km SSW,15 Nonantum 1.5 km WSW. 8 Eldredge St. 13.1 0.8 20 P15240 P15270 1.5 km West,66 Capital 12.2 0.6 19 1.5 km WNW. 91 Church St. 9.9 1.2 39 P15300 P15330 1.5 km NNW,119 Robbins 12.9 0.4 19 3 km North,22 Bow Road 9.7 1.3 21 P30rX10 i 3 km NNE,17 Bright 11.3 1 21 PM030 l 0.8 20 I PVXMO 3 km ENE,157 Brattle St. 10.9 3 km East,7 Rena St. 11.8 0.5 20 ITXYX) P30120 3 km LSE.1302 Commonwealth Ave. 13.3 0.7 20 3 k m SSE, MDC Pool and Park 12.3 0.6 20 P30150 3 km South. Boston College 13.8 1 41 PMlHO 3 km SSW,2&6 Ward St. 11.4 1 39 P30210 3 km WSW. Cabot Park 11.6 0.8 40 P30240 P30270 3 km West,103 Bridge 13.5 0.7 20 3 km WNW,103 Chapman 13.4 0.6 20 P30300 P30330 3 km NNW. 91 Waverly 11.3 0.7 20 03059.1. PUB \SmAMTL71N\RX\026 RD Page 7 of 14 REVISION 0
APPENDIX C Table C-5 Off-site Ilackground Soil Direct Alpha Activity (dom /100 cm 2) Incation Code Imation Mean Number of Meaerements Sad. Nr. MDA 195000 14 Haamer, Watertown 5 5 10 34 195030 18 istnam. Watertown -3 9 2 34 K15060 Quimbiv/Cypreas. Outskie Ikmion IMa<m 7 5 6 34 105090 NE Corner AMTL 12 5 9 34 105120 Arsenal f%rk by Picnic Area 4 10 7 34 195150 46 Newton 4 5 8 34 1415180 IAt of MDC T'outball Fickt. Newton (N t f 25 5 12 34 Charles Nnk R.l.) 005210 T ront of MDC Statmr Ilmk 1 5 0 34 IM)$240 32R Charles Bank thi 1 5 3 34 i POS270 96 Nechwood 5 5 14 34 POUOO T ront 30 T rank 10 5 8 34 195130 136 Walnut St . Watertown 2 5 6 34 P15000 29 Commonwealth Ave., Watertown 16 5 8 34 Pl5010 56 Sahabury 9 5 7 34 P1566n 133 Grove. Watertown R 5 7 34 Pl5090 Okt Arsenal Property. Greenpurh Ulvd, ! 5 4 34 P15120 117 Murdak 16 5 5 34 PI5150 S. Iht brers 1%rk Ave. 7 5 7 34 P15 tito breman Park - Acnma from 375 I:nnucit 8 5 3 34 P15210 15 Nonantum. Newton 17 5 10 34 P15240 R 1:kirafge st. Newton 6 5 8 34 P15270 66 Capital. Newton 2 5 0 34 Pl5300 91 Church St.. Newton 5 5 5 34 P!53l0 119 hbbins 13 5 9 34 P30000 22 Nw lui.. Iklimmt -I1 5 12 34 190030 17 Dnght. Iklmont 37 5 5 34 P30060 157 brntile St. Cambralpe -l 5 2 34 ; P30090 7 Rena 5t , futem 12 5 11 34 P30120 1302 (?r mnwnwrmhh Ave . Natrm 12 5 4 34 190150 bescue. St MIX? Pool & f%rk 3 5 7 34 190180 ihmton Collere 3 5 3 34 y P10210 2lt6 Ward St . Newton 4 5 4 34 13 0240 Calma 1%rk 1 5 4 34 P30270 10) Bruire 7 5 14 34 f l TSOMW) 103 Chnpmun. Watertown 2 5 5 34 19 0310 91 Waveriv. Ninumt 11 5 13 34 . j Note: Direct survey resuhs for alpha measurements on soil are shown as dptn/100 cm', as required by the Decommissioning Plan. Such
. measurements are suitable only for indication of the pr:sencs of relative levels of contamination. ne use of this unit of measurement is inappropriate for soil whers mixing can occur. No correlation is available for converting these numbers to pCirgram.
l i 1 05m3.ruasmAu rmwarumD" Page 8 of 14 REVISION 1 l
APPENDIX C 2 Table C-6 Off-site Background Soil Direct Beta Activity (dom /100 cm ) Imentum Os,de Imration Mean Number of Men uremente Sid. Dev. MIM 10 % 00 14 lir.nmer, Wetenown ION 5 115 770 195010 18 Putnam. Watenown 707 11 138 770 Tc5060 Quimbly/ Cyprus Omnide Itontnn IWon 704 5 107 770 Ni! Forner ALfit 778 5 55 770 P05000 Arsenal Park by Pumic Ares ?68 10 43 770 _ PO5170 195150 46 Newton 150 5 59 770 ; 195180 East of MDC Football Ficks. Newton (N. of Charlen Iknk RJ ) 105710 Front of MDC Skatine mnk 3no 5 134 770 P05740 378 Charles hank Romi 355 5 46 770 P05770 06 Incechwomi 570 $ 116 770 P05100 Front TO Trunk 746 5 63 770 005110 136 Walnut St . Watertown 177 5 105 770 Pl%000 79 Conunonwealth Ave , Watertown 767 5 60 770 P15010 56 Suliaborv 407 5 01 770 P150r.0 111 Grove, Watrnown 57 to 784 ??O _ Pl%000 ()LI Arsenal Property, Greenourh Disd 78 10 767 770 Pl5170 ll7 Munixk 460 5 97 770 P15150 S FAI Rorcen Park Ave. 181 5 1 01 770 P!SIBO lintemnn Park - Actma from175 T;nnaril 708 5 64 770
- Pli?lo 15 Nonantum Newton 165 5 160 7?O P15740 8 I kirestre $t . Newton 119 5 43 ??O P15770 66 repital. Newton 47 5 67 770 P15 90 01 Choreb St . Newen 618 10 518 770 P15130 110 Rohhina 376 5 170 270 N0000 77 ltow RI . helmons 258 5 18 770 P10010 17 brirht. Belmont 746 5 54 270 P300t.0 157 Itrattle St . Cambritre 314 5 81 720 P30000 7 Rens St , Ibaton 777 5 151 770 P30170 1907 Cnmmonwealth Ave . Ihmion 515 5 66 770 .
M 0150 fiencon St , MDP Pool & Park 191 5 44 770 M0180 Iwatan Coll. re 419 10 470 770 P10710 7R6 Want St , Newt. n 347 10 744 /70 , N0740 reibnt Park 347 10 579 ??O P10770 1011tritre ditit 5 50 770 M0100 101 Chapman. Watenown 345 5 G1 770 M 0110 01 Waveriv, Delmont 664 5 174 270 Note- Direct survey resuhn for beta measurements on soil are coun as di nn!!00 cm', as required by the Decomn6sioning Plan. Such measutt av nts are suitable only for indication of the presence of relative levels of colaanunation. The use of this unit of measurement is inappropt.dte for soil where nuxing can (nur, No correlation is available for converting ther.e numbers to pCilg. ff. Data hot avallais; c5cmrumsnwrrurwnxsAur2 ento *6 Page 9 of 14 REVISION 1
APPENDIX C , i Table C-6 Off-site Background Soil Direct Beta Activity (d.pm/100 cm2) l Location Code Lacaibo Mean Number of Mesaurements Std. Dev. MDA 1 198 5 115 220 I P05000 14 Haamer. Watertown 195030 18 Ih=. Watertown 207 11 138 220 195060 QuanMy/Cyprema.Outskie fkston Edmon 204 5 107 220 , i P05090 NE Carner AMTL 228 5 55 220 195120 Arsenal Park by Psenic Area 268 10 43 220 195150 46 Newton 150 5 59 220 195180 fut of MDC Football Field. Newton (N. of Charles fiank Rd3 P05210 Iront of MDC Skating Rink 380 5 134 220 1t5240 328 Charles Bank Road 358 5 46 220 t Et5270 96 Decchwood 520 5 136 220 195300 Front 30 Frank 246 5 63 220 105330 136 Walnui St., Watertown 372 5 105 220 P15000 29 Commonwealth Ave.. Waterewn 267 5 60 220 P15030 56 Salisbury 407 5 91 220 P15060 133 Grove. Waterewn 52 10 284 220 P15090 Okt Arsenal Property. Greenough Blvd. 71 10 262 220 P15120 117 Mard-k 469 5 92 220 P15150 181 5 101 220 S. Essi Rorers Park Ave. P15180 Hareman Park . Across from 375 Fanucil 298 5 64 220 + P15210 15 Nonantum. Newton 365 5 160 220 P15240 8 f:kiredge St.. Newton 339 5 43 720 P15270 66 Capital. Newinn 47 5 62 220 P15300 91 Church St.. Newton 618 to 538 220 P15330 119 Robbina 376 5 120 220 M0000 22 Itow Rd . Delmont 258 5 18 220 M0030 17 Bright. Delmons 296 5 54 220 P30060 15713 rattle St . Cambrafre 334 5 83 220 P30090 7 Rena St., Ikston 227 5 153 220 P30120 1302 Commonwealth Ave.. Ikmton $15 5 66 220 19 0150 Ikacon St.. MDC Pool & l' ark 191 5 44 220 P30180 Doston College 439 10 429 220 P30210 286 Ward SL. Newton 342 10 244 220 P30240 Cakd Park 552 to 529 220 M0270 103 Brxige 488 5 50 220 19 0300 103 Chapman Watertown 345 5 93 220 P30330 91 Waverty. Belrnont 664 5 124 220 8
- Ncde: Direct survey results for beta measurements on wil are shown as pCi/100 cm , as required by the Decommissioning Plan. Such rnepartments are suitable only for indication of the prer.ence of relative levels of contamination. The use of this unit of measurement is inappropriate fer soil where mixirg can occur. No correlation is available for converting these numbers to pCi/g.
( s 03089FPUD3fnAMTLTL%RX\026 RD Page 9 of 14 REVISION 0 i
APPENDIX C O Gamma Radiation at 1 Meter, Concrete All Ori-Site Bkg Building Readings 35 numma 30
'J)
'b' 4 20 -. -
l- - 15 '
.~
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j it ic ,# 2 B hO E h Lccartn Cccb O Gamma Radiation at l' Meter All On-Site Backgrc'"nd Building Readings from Concrete Surfaces l Number of Mean Std. Dev. Maximum Measurements 16.7 3.5 27.0 210 Figure C-2 J Gamma Radiation Background On-site Concrete l O om95rumsmrscunma.xso:6.n" Page 10 of 14 REVISION 0
A
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APPENDIX C O Gamma Radiation at 1 Meter, Concrete Building 36 Readings 25 mummmes UFUhr 30 25 - l.......g~.. D...........g.... 3
...g..........g..........j.........g.........ig.6 BkM2G BKG10 A KG100 G YKG100W2G wm O
1 Gamma Radiation at 1 Meter i Building 36 Readings l' from Concrete Surfaces Number of Mean Std. Dev. Maximum Measurements I 16.9 2.0 22.1 90 I l Figure C-3 l Ganuna Radiation Background Building 36 Concrete , O
- 0. %93-PUDiSITAhrnATIN'JtXiO26.RD P 11 of M RD'NM 0 1
l
APPENDIX C O(. Gamma Radiation at 1 Meter, Concrete Building 60 Readings s . UR/hr g 25 20
.E 15 -
7 , 10 5
..f ." .'
0- .. . . h G10 b h C1 25 D G100 G D G100W2G w:m Gamma Radiation at 1 Meter
~
Building 60 Readings from Concrete Surfaces Number of Medn Std. Dev. Maximum Measurements 13.2 2.- 21.1 60 l l l Figure C-4 Ganuna Radiation Background Building 60 Concrete mmruv.snuunawsxuc6" Page 12 of 14 REVISION 0 m
APPENDIX C O Gamma Radiation at 1 Meter, Concrete Building 111 Readings as rmem UR/hr 30 25 Il 20 - r"T " I- r I 15 - l- 'l, g 10 5 - 0 '...i 4.'. "'N.'.7..'.i. s
.. h-
[ God [G B[MI20 CC 20 B[GCCXT2G LcretJtn Code O Gamna Radiation at 1 Meter Building 111 Readings from Concrete Surfaces Number of l Mean Std. Dev. Maximum Measurements 20.3 3.5 27.0 30 Figure C-5 Gamma Radiation Background Building 111 Concrete ownruasnwnurummo n Page 13 of 14 REVISION 0
APPENDIX C O Gamma Radiation at 1 Meter, Concrete Building 131 Readings 35 mummu UR/hr y 25 GDOCF2A O Gamma Radiation at 1 Meter f rete ra Mean Std. Dev. Maximum Me ements 19.6 2.6 24.3 30 Gamma Radiation Bac o nd Building 131 Concrete O : ow3 rumsmurrurwxw:6.x Page 14 of 14 REVISION 0
h. O e O :
?
4 A P APPENDIX D
SUMMARY
OF EQUATIONS O l'
APPENDIX D
.i i
(j : 1 9 1 i i f i
.l; APPENDIX D 1 i,
O summiny or nourrious , i i
')
1 1
-l l
1 O 1 o20293-run'stnaurtv saxso24.mo REVISION S 1 l I i-
APPENDIX D
,.s ACTIVrrY EQUATIONS
( \ Efficiency and Corrected Activity Counting efficiency of the 2350 Data Imgger was used to convert an instrument response to activity. Efficiency was calculated using a plated Th-230 or ' Tc-99 source and background measurement. Source activities were decay corrected, if necessary, using the equation below. Tc-99 beta sources were not decay corrected because of their long halflife,2.13E5 years.
- B, [D-1]
E= A Where: E = Efficiency in counts / disintegration C = Counts t = Counting time R3 = Background count rate A = Source activity in dpm, and i LJ ;
-Atd [D-2]-
Where: A, = Original source calibration activity A = Decay constant for the source nuclide to = Decay interval between source calibration and the date . of correction (AMTL-INST-I-201, Operation ofLudlwn Model 2350 Data Logger) mm93-runssrnawTtwissaxw24" Page 1 of 8 REVISION 0 i
APPENDIX D Surface Activity The 2350 Data Logger measurements are reported as gross counts. An () V equation in Paradox
- was used to calculate # or a activity in dpm/100 cm 2
2 from the gross counts. Detector size was 100 cm ; therefore area was not , incorporated in the equation. [D-3] C
- x 60 - R, i
dpm/100 cm2, E Where: C = Integrated counts t = Counting time (seconds) R3 = Local background count rate in cpm E = Efficiency in counts / disintegration Countine Error The counting error at the 95%' confidence level was calculated when activity was determined m a unit other than dpm (i.e., cpm). These activities were reported with the associated counting error determined as follows: [D4] R, R
-+#
, s'95 = 1.96
\ t, t, Where: s.,3 = Counting error at the 95% confidence level R3 = Sample count rate R3 = Background count rate t, = Sample counting time ta = Background count time (AMTL-1NST-1-103, Quality Assurance ofCounting Systems and Portable Counters) l l
b ! MM93-PUInSTTMhfIUFINiRXW4.RD Page 2 of 8 REVISION 0 1
APPENDLX D
,Ch Gross Aloha /BetnGross alpha and beta analyses were performed on the Tennelee system for soil V; samples. Results were reported as counts. These were used to calculate activity in pCi/g as-follows.
l g [D-5]
- R, pCilg =
E M 2.22 x 106dpm/pCi Where: C = Gross counts from the sample ts = Sample counting time Ra = Background count rate E = Efficiency in counts / disintegration M = Sample mass (NUREG/CR-5849; ORAU-92/C57, (Draft), Manual for Conducting Radiological Surveys in Support ofLicense Tenninction) O l l 1 l 1 i l 4 osom-rumsnuwrurmuwmm*" Page 3 of 8 REVISION 1 I
)
- - - .~
APPENDIX D D MDA- Determining minimum detectable activity (MDA) was required for the d 2350 Data Logger and the Tennelec alpha / beta counter. MDA was determined one of two ways. For beta-gamma or depleted uranium alpha contamination the following equation was one way to calculate MDA.
] [D-6]
R, ' 1 + ,' t 2.69 + 3.28 - MDA = t' ) t, t t* i
,A' E '
s100s Where: ts = Sample counting time Ra = Background count rate to = Background counting duration , E = Efficiency in counts / disintegration A = Detector area in cm 2 (AMTL-CHR-1-106, Tennination Sun'eys of Site Structures) MDA was calculated in a slightly different manner for gross alpha and g beta sample analysis performed on the Tennelec system. Results were reported in counts, which were subsequently used to determine a minimum detectable count rate (MDCR). MDA was then calculated using the count rate, detector efficiency and volume or mass of the analyzed sample. , [D-7] R,+-R# 3.29 MDA
'* pCifml 6
E = M 2.22 x 10 dpmfpCi Where: R3 = Background count rate ts = Sample counting time 13 = Background counting time ; E = Efficiency in counts / disintegration M = Sample mass or volume (g or ml) l O l l oso393.ruirsrnasrrtuw,xxssunnu*'7 Page 4 of 8 REVISION 1 l
APPENDIX D W: STATISTICAL EQUATIONS U The objective of a survey was to take sufficient representative Nnniber of Measurements measurements such that the average measurement accurately represented the true measurement at the limiting average to within i 20% at the 95% confidence level. If the observed mean of the set of measurements approached 80% of the limit for the mean, a test was performed to ensure that a sufficient number of sample locations were evaluated to achieve this objective.
'tss. -i 3
s rx > Where: N = Required number of measurements t.u, a = Student's t statistic at 95% confidence level s = Estimated population standard deviation r = Acceptable relative error (0.20) i = Average of measurements , (AMTL-CHR-I-108, Termination Surveys of the Site Environment) em i i f\ i 1 man-rwsrrunmmum.e Page 5 of 8 REVISION 0 i
APPENDIX D em Confidence Level For direct and removable beta and alpha contamination measurements Q which were greater than the average contamination limits, a confidence test was performed. This test verified that the 95% confidence level upper bound for the survey unit sample mean didn't exceed the limit for the mean. The steps for determining this upper bound are shown below. [D-9] i = nb [x, Where: x = Average of the measurements xi = Individual measurement n = Number of sample measurements _ [D-10] E(i-x,)2 s=$ n-1 Where: s = Standard deviation of the population [D-11] 95% CL Upper Bound = x + tagg,,.h h Where: to.,5. .-: = Student's t statistic at 95% confidence level (AMTL-CHR-I-107, Termination Sunty Data Handling and Analysis) This test was incoroporated into the database so that the 95% confidence level was determined for all data. ee3-rummrururwax*" Page 6 of 8 REVISION 0
APPENDIX D [
~
Values for the student's t statistic are given in the following table taken from Statisticsfor Business and Economics, 4th Ed., James T. McClave and P. George Benson, San Francisco,1988. - N55E0f . . . . . . . Freedoni f(.951
) 6i314 2 2.920 5 2?355 4 21132 '
5 2:015' 8 E9d I M# 8 l'.860 . 9 L833 10 E812 15 1p53 20 1325 C) 30 UB97 (> O esaurumsnuunawnxiautwoso'7 l' age 7 of 8 REVISION 1 ,
APPENDIX D Confidence Level A confidence test was also performed to veri. the 99% confidence level b' upper bound for direct gamma radiation. ' lis test determined if any samples were statistically higher than the backeround for the survey unit. _ [D-12] x, < (t,,,, 3) (s) + x, Where: x3 = Individual gamma readings in the area being tested. ! t = student "t" statistic at 99% confidence level n = Number of measurements used to determine the background mean sa = Estimated standard deviation of the background population xn = Average of the measurements for the background sample (AMTL-CHR-I-107, Tennination Sutrvey Data Handling and Analysis) EsbEfof Freedom 499); : O > 2 x8u 6;965 3 4;541 h $N45 5 3;3.65 6 3{143 , 2 2.998 B 2.896 D ';821 2 30 2/764' l 15 2?605 i 2:528 l 20 30 2M57. ! I
-i
-i osenruunum1VMOGAM124D'A47 - Page 8 of 8 REVISION I I
l O. APPENDIX E PIIOTOGRAPIIIC FSSAY OF TIIE , AMTL REACTOR DECOMMISSIONING O ,
- - - - - - - - - - - - - ---- -- - --- -- - A
t APPENDIX E , ~ O : f APPENDIX. E PHOTOGRAPHIC ESSAY i Os OF THE AMTL REACTOR DECOMMISSIONING.
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- U.S. ARMY MATERIALS TECHNOLOGY LABORATORY Owned and operated by the U.S. Army for the Department of Defense, the site was a part of the old Watertown Arsenal, originally established in 1816 to store, f
maintain and issue small arms and ammunition. l The open pool research reactor - the round, domed building in the bottom center of the picture - was constructed in the 1950s and was used between 1960 and 1970 to study molecular and atomic material structures and solid state physics. ! The site is shown above with the Boston skyline behind, the Charles River to the right, and Arsenal Street to the left. onsrwsrnrmxe2 Page 1 of 43
APPENDIX E 1 7 myg s- y g7@79g p f9pw Op4 y %y p ;g rg g@j (1 s. ^espN c rn y .,cyz MQ;;Qzs
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J . ,- O ; 1 i AMTL RESEARCII REACTOR The AMTL Research Reactor was housed in a concrete-lined, steel containment building. The pipe running around the upper part of the structure was the reactor vent system and previously connected to a stack. The stack was removed ; when the reactor ceased operations in 1970. Staged low-level radioactive waste i l is seen in the foreground. Building 97, which provided access to the reactor, etm I
- he seen in the background.
1 i l 1 l l l 02229LPUBd!T\!MRXiO12.R Page 2 of 43 l
APPENDIX E O u :, sL qa _ {, f
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e u m shte . : CISTERN 242 One of the initial decommissioning activities was the excavation of Cistern 242. The cistern, a 231/2 square feet by 15 feet deep tank constructed of I foot thick concrete, was used primarily as a liquid radioactive waste holdup tank. The cistern was used to store reactor pool water during reactor maintenance. O 022293 PUB;SITELYRX\012 Page 3 of 43
l l
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. Jks . I CISTERN 242 Preliminary radiological surveys inside the cistern revealed small amounts of fixed contamination. The internal surfaces of the cistern were decontaminated by scabbling with vacuum assisted needle guns. Subsequent surveys indicated that the surfaces were below detectable levels, and the cistern was removed for ,
disposal. l
/
cmnrwarrmmo22 Page 4 of 43
. ,. _ _ _ . . _ . _ . -____ ______ _---- _ L
i APPENDIX E 1 0 l I
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CISTERN 242 FollovMng free release surveys, the cistern was dismantled using concrete saws, and the sections were released to a local landfill. The steel pilings seen above were placed to stabilize the dirt walls during dismantling. O 02.2293-PUBNNW.RX\012.RO l' age 5 of 43
APPENDIX E O ! k l
\
1 s 'Q - l [ v.. . , ,1 q,. , O l l SECONDARY SUP IP i The secondary sump, a concrete tank, was located outside the reactor building. After all components (pumps, piping, etc.) were removed and the water drained, the sump was surveyed inside and out and free released. l O onm rastrauxxun2 Page 6 of 43
~- _.
4 APPENDIX E ! O I i 4 ene
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l . ACCESS CONTROL l Prior to any work taking place in the reactor building, an access control station i was set up in Building 97 at the entrance to the reactor building airlock. IIealth physics personnel controlled access into the reactor through the use of Radiation /Ilazardous Work Permits. Computerized dosimetry (FASTRAK II*) was used to track personne! exposure for all work inside the reactor vessel during ' l. component and liner removal. 1
- O mm rums
- ww.xm2 Page 7 of 43 1
APPENDIX E , a y ,~ O .' -
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a . .: [ bi j PERSONNEL CONTAMINATION MONITOR , All personnel leaving the reactor building were required to pass through the
- EberlineS Personnel Contamination Monitor (PCM-1B), where an array of gas-flow proportional detectors monitored all parts of the body. The PCM-1B has i
an automatic background subtract and adjustable alarm settings. 1 i s ( iO j om9mmsnuwxxici2 Py 8 of 43 i
APPENDIX E O 1 l.. i - 1a1 1 r r ' e wm
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I i i 1 i l TOOL CONTAMINNITON MONITOR i All small hand-carried items (tools, radios, clipboards, gloves, etc.) leaving the i reactor building were monitored for beta-gamma contamination with the Eberline* Tool Contamination Monitor (TCM-2). This gas-flow proportional ! detector has adjustable geometry, alarm systems and automatic background subtract. l l l l i O 1 onm rw.smrwaxwo Page 9 of 43 t
l l- ; APPENDIX E l O-nyrm:my rgg . ymm77;merm773 mp ,, yng 3 %pdg ' N : $ h . ,. ... ; ; ' ' "
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O l i i CONTROL ROOM ) As part of the reactor decommissioning, the control room was dismantled, surveyed and unconditionally released by health physics personnel. The control , room instrumentation and panels became artifacts and were packaged and stored j for historical preservation. l O m29nuw.srruwaxu2 Page 10 of 43
1 I APPENDLX E l
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l i REACTOR CAVITY i Initial dismantlement of the reactor cavity involved removal of the core support ( assembly, fuel racks and experiment tubes. The core support assembly, at the I j l bottom of the picture, is being removed. l l onm nnr.smrumon Page 11 of 43 1 E__ _ .. _ - . _ .
APPENDIX E O. 1 g.. t-9
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i N- . g i 4 t . .,,. , .. t-1 .O l l 1 i i j l fj l CORE SUPPORT l l The core support assembly (pedestal) was lowered into the gamma well for i interim storage until it could be shipped for disposal. l . l O unmwae w n m Page 12 of 43
- APPENDIX E i
1 l p%a M znc . ;cw QS"!["yf7."+TG8.%: .c. x .ly7#@@"" W.;E~,'Yn.f+s;C.:"'.q'.:::,.@;w . .& ;; e
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W y, y% ve r v n. : . . ~ . - '. ~.-' lw 1,m q,. d ;a%. pJ;h ;;'b,y;L. n.o:,n %g n a r:
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y3 Q.p?a.m . v wmj, g. ...:4 p:. w:.naqL. - A - 7W Md!? ..:-- - qm' eAj,.hy';w%,b" m . N e..b;n sq {@Mm?"si; 3 My ' y.e 5%K:wmy ' Nf ,
); - , . q .t.
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GAMMA FACILITY The 6 feet diameter by 16 feet deep stainless steel-lined well was set in the - basement of the reactor building. Previously used for gamma-ray experiments and fuel storage, it was used to temporarily store highly radioactive materials, thus keeping dose to a minimum during the decommissioning. Seen in the well are the core support pedestal and an activated experiment tube. am9manstrmne2 Page 13 of 43
APPFADIX E
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.. 8 0$% #T. ?- AiSSOO N: L i
i i STAINLESS STni i LINER The stainless steel liner was sectioned and removed using a plasma are cutting tool. The worker in the foreground is standing on the wall separating the reactor pool from the annulus. 3 iO I amunar.smiwmoi2 Page 14 of 43 1
1 I APPENDLX E 777pmmr-nn:;; ~~xm y. o-
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i i@ m , j lQ IgQ i m map tweg l e PLATFORM REMOVAL l The first and second platforms and portions of the operating deck were removed by diamond saw cutting. The concrete was surveyed and free released. i i i e O : 1 l emo naumns'.xx'oi2 Page 15 of 43 l l ____' i
APPENDIX E ! . .o. l s ; l p .
-+
. . . . . . . .u . . . . . . . . . . a . .. w. ~; . . . . . . > .. -} r i t
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1
- PLATFORM REMOVAL The floor support beams (steel I-beams encased in concrete) were cut away from the structure with jack hammers and oxy-acetylene torches. These beams were surveyed and free released.
d o cm9ntasmrmxw2 Page 16 of 43
APPENDIX E l l l
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i i h REACTOR ANNULUS WALLS : ! After the stainless steel liner had been cut away, the annulus walls were cut away
- using a d.iamond w. ire saw. i.
1 l Low levels of surface contamination on the inner walls were removed by ' scabbling to reduce the volume of radioactive waste generated. The blocks were then surveyed and free released, a O < l omo nnnsmrumen Page 17 of 43 l~ - . - - . . .
r r APPENDIX E II e i ' *- a fe.
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s.- ,. .-. . = . . - l l REACTOR CAVITY WALLS l Once the outer annulus walls had been removed by diamond wire sawing, the l c same procedure was applied to the inner annulus / cavity pool walls. Like the annulus walls, the cavity pool walls were also scabbled until no detectable activity was found and then free released. 027293-PUB'sTN'I!f.RX\012 p j g g[ g l i w- - ,, , .
-_ - a e-~ ~
APPENDIX E . O
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d l l l l 4 ) CAVITY WALL REMOVAL ! Concrete sections of the removed cavity and annulus walls were wrapped in herculite and plastic and stored outside the reactor building. The sections were then transferred to an enclosure where residual contamination was removed. 4 O a:2nnwismnwnu2 Page 19 of 43
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yde ? { h O i CAVITY WALL SCABBLING l Concrete blocks cut from the annulus and cavity walls were scabbled to remove low levels of fixed contamination inside a tent in the reactor yard. Vacuum assisted scabbling tools were used to eliminate airborne radioactivity problems. 4 lO ! l mmav.smnmn"2 Page 20 of 43 i I i . ~ - . - , _ . . . _ . . . . ---- _ , _ . . . . _
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l 1 l l FREE RELEASE OF CONCRETE All concrete found to be free of licensed radioactive material was transferred off-site for disposal. Approximately 1200 tons of concrete were released in this manner. 1 l l l l m2293 3 unwrisris.xxsoi2 Page 21 of 43 1 i
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l 'l l l REACTOR BIOSIIIELD i i j The bioshield consisted of approximately five feet of high density, magnetite impregnated concrete. This concrete could not be cut with diamond wire and had to be broken apart with Jack hammers to be removed. i I
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t BASEMENT TRENCIIES i All floor drains in the basement floor were removed by diamond saw cutting and jack hammering The resulting trenches were gridded for final status surveys. t i emmwsrmwxm2 Page 24 of 43 ir - - - - -_ m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _
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W W.J}W. 4R . .N t- - $g 4 IIEAT EXCIIANGERS In preparation for the removal of all piping and components, the floor area
- around the reactor water heat exchangers and recirculation pumps was covered with plastic. A health physics technician in the photograph is performing a routine radiological survey of the area.
1 O l 1 l omnrtastrwnw" Page 25 of 43 l
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sy me dd* . a wn.m < e - i IIEAT EXCIIANGERS l After removal, the exterior surfaces of the heat exchangers were decontaminated, ; and the openings were sealed. The heat exchangers were then stored outside until they could be shipped as radioactive waste. The two demineralizer vessels which were also shipped as radioactive waste are shown between the heat ! exchangers. , l 4 i I ( o m e w stru w usm 2 Page 26 of 43 l
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,1 OPERATING DECK AND BASEMENT A section of the operating deck floor was removed by diamond cutting to allow access to the reactor water system components (heat exchangers, pumps, ion exchangers) and the lower. portion of the reactor pedestal in the basement. The painted lines separate the four survey area quadrants.
i O , 1 l on293-runssrTwwatxio22 Page 27 of 43
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O . REACTOR BUILDING SUMP After removal of the stainless steel liner, all water and debris were removed from the sump before final surveys were performed. The drain pipes, which traveled under the floor and discharged into the sump, had been excavated and removed. During reactor operations, liquid waste was pumped from the sump to a waste process facility once located in Building 97. O l l cnmrumsmrw;onoi2 " Page 28 of 43
APPENDIX E l
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OPERATING DECK WALLS 1 1 I At the completion of the reactar decommissioning, a final status survey was carried out by SEG health physics technicians. All wall, floor, and ceiling surfaces were divided into reference grids. The grid intersections were permanently marked _ with paint, and an alpha-numeric identification was assigned. One meter grids can be seen on the lower part of the walls. Three meter grids were used on the upper walls. O on s rumstr m n w u Page 29 of 43 1 4
APPENDIX E I O l l I
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5 l l OPERATING DECK i llealth physics technicians entered final status survey location codes into the Ludlum Model 2350 Data Logger using a hand-held terminal. The Model 2350 l i is the central component in the survey set-up, which includes the P-10 gas bottle and regulator, the floor monitor cart and gas flow gauges. In this case, the detector in use is the Ludlum Model 43-68B 100 cm 2 gas flow detector. An l i extension handle is attached to allow for easier floor surveys. l l i O l i own rumsrnnmmoi2 no Page 30 of 43 i
_ - - - _ - - . - . . - .. - . . - - .~.-._ - _~.- - - - l APPENDIX E O _* 34, , _ . p9"A_}2,13*"'11 qggspa Ass;.49%,$~~'M. g
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1 x -.un Bigg.t av f.,a:- OPER\ TING DECK AND BASEMENT One meter grids were painted on all surfaces from the operating deck'down to the basement. The top of the gamma well can be seen in the lower center portion of the picture. The storage tubes are in the lower left against the basement wall. These tubes were core drilled to remove the contaminated steel liners. O mun runstnmawi2 8 Page 31 of 43 i i N g a 2- og yw--. --,w- -rv- .r %-+-v ve ---a
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1 1 1 l REACTOR BUILDING DOME AII insulation and light fixtures were removed from the reactor building ceiling for final survey. The Reactor Decommissioning Plan specified 3 meter grids on { the ceiling, however, the welds between the plates formed a natural grid pattern ! which did not exceed the nominal 3 meters and was adapted for the final status survey. i The polar crane can be seen across the upper left portion of the picture. 1 l t 022m-rursmrwm2 Page 32 of 43
APPENDIX E i i i
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l IIASEMENT FLOORS i As part of the decommissioning, all reactor drain piping buried in the basement i floor was uncovered and removed. The resulting trenches were gridded and surveyed during final status surveys. Seen in the photograph is a health physics technician performing a gamma dose rate measurement 1 meter above the trench. l l 027293 PUB'5!T.HN'<RXW12 Ro Page 33 of 43 l
i a APPENDIX E 3 1 I.O : i ! L l??; QM;-l:g. .. . f 1 1'g *
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I j BASEMENT CEILING l The basement ceiling, as an unafTected area, was gridded in three meter sections. I j Seen H the photograph is a health physics technician performing a gamma dose- ,
- rate survey using the Ludlum Model 2350 Data Logger and a Ludlum Model 44-2 I l 1"x1" Sodium Iodide Detector. l l
l: I 1 O cmurumsmrumn.no Page 34 of 43 1
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o p[. 5 w .m . j' , if. a: jf; - . Jg' _ _. o : LUDLUh1 AIODEL 2350 COhfPUTER DOWNLOAD l At the end of the survey, or when the data memory capacity. of 250 measurements was reached, the hiodel 2350 Data Logger was downloaded to a l computer. A total of 29,249 data points were collected: 3,047 direct alpha l measurements; 15,754 direct beta measurements; 6,604 measurements for ! removable activity; and 3,844 measurements for gamma exposure rates. In I addition,563 soil samples were collected and analyzed. l 4
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r, [_ L L: . Ia l i i REACTOR AIRLOCK The reactor airlock overhead was surveyed using the Model 43-68100 cm2 gas i flow detector. This detector can be operated in both the alpha and beta detection modes by changing detector parameters (i.e., operating voltage, setup number, etc.) stored in the Model 2350 Data Logger. i i i i lO l onm.nnr.smnnrm2 Page 36 of 43 1 l
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- REACTOR STACK SLAB i
l Following the cessation of operations in 1970, the reactor vent stack was removed and the remaining foundation covered with soil. The foundation was uncovered j during decommissioning and a final status survey was performed, confirming
- contamination levels were below NRC guideline values.
1 l i l O i om9n wsmrxxxsot2 Page 37 of 43 l d
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J 4 RADIOACTIVE WASTE A storage area was established at the north end of the reactor building for radioactive waste containers. Approximately 28,000 cubic feet of radioactive waste in 206 B-25 boxes,6 sealand containers, and various other packages were generated during the reactor building decommissioning. emnw.srnrwmoi2 Page 38 of 43
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e i i 1 REACTOR EQUIPMENT IIATCII i i Access for materials entering and leaving the reactor building was through a set i of double doors on the southwest side of the building. The 8'x8' size of the opening made it difficult to remove large pieces of materials - especially concrete sections from floors and reactor walls - from of the building. 1 i i O 1 1 l 022291-PUIr.SITW!ERX\012 Page 39 of 43 ;
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MOBILE DEMINERALIZER All water containing radioactive materials generated during the decommissioning was filtered through a mobile demineralization / filtration unit. This unit, an atmospheric ion exchange demineralizer was located outside the equipmeni hatch. Approximately 30,000 gallons of water, at a rate of 30 gallons per minute, were processed through the system. All water processed was monitored for radioactivity and released to the sanitary sewer if found to be free of detectable contamination. omnrursmnre.xxsoi2 no Page 40 of 43 i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ ._. ___.___.._____.___________J
APPENDIX E O.
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l A i CANBERRA
- GAMMA SPECTROSCOPY SYSTEM Radionuclide analysis of air sample filter, water, concrete, smear and soil I
samples was performed onsite in the radiochemistry trailer using a Canberra8 Genie-PC Gamma Spectroscopy System. This system utilizes a high purity germanium lithium (GELi) detector and a Multi-Channel Analyzer to determine activity for samples with known mass or volume and geometry. O c22m ew.smrwnwn Page 41 of 43
APPENDIX E lO J 1 i Il 1p w MN
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A f .- 4 b ,\) . %@@y k' t.$lw gp[ux WWf' , 1 i l l l , i i l l l TENNELEC8 LB 5100/W LOW BACKGROUND ALPIIA/ BETA COUNTER l Alpha and beta activity analyses were performed on all smear and soil samples i taken in the reactor building and yard using the Tennelec8 LB 5100/W
- Alpha / Beta Counter. This system utilizes a shielded gas-flow proportional l detector and computer software and automatically reports sample analysis l results.
i i I i O o-2mww.strrwmoi2 Page 42 of 43 l i I.. - _ - , . . . . . . . . _ _ , _ . , , , .. , . , _ ,
APPENDIX E i
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was j p;d a " % " # MycF=6:4~_d ?s' @ b., ggg k id[IIDsG , ~~ ' d . AUSTRLtN PINES , Much of the Watertown Arsenal was considered to be of historical significance. Among the features slated for preservation were five Austrian pine trees in the , reactor yard. A fence was erected around the trees before decommissioning to preserve them from damage. l l omewusmnuxwn." Page 43 of 43 ;
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