ML22340A009
| ML22340A009 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 06/28/2011 |
| From: | Ely P Aerotest, EnergySolutions |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML22340A004 | List: |
| References | |
| CS-HP-PR-004, Rev 0 | |
| Download: ML22340A009 (1) | |
Text
ENERGY~ SOLUTIONS
CS-HP-PR-004
Historical Site Assessment ofthe Aerotest Radiography and Research Reactor
Project No. 313150 Revision 0
Prepared for:
Aerotest Operations, Inc.
Prepared by :
EnergySofutions, LLC Comme rcial Services Division 1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830
Authored By:
Dat~ 7
Rev iewed By:
Approved By:
Ben Sklar, Project Manager Date
[JO New Report D Ti tle Change D Report Revision D Report R e write
Effective Date
Electronic doc um e nts, onc e pri nted, are un co ntrol led and may b ecome o utd at ed.
Refer to the intra web or the Document Control authority for the co rrect revision.
Historical Site Assessment of the CS-HP-PR-004 Aerotest Radiography and Research Reactor Revision 0
TABLE OF CONTENTS
Section Page
LIST OF FIGURES........................................................................................................................ 4 LIST OF TABLES.......................................................................................................................... 6 1.0 ACRONYMS AND ABBREVIATIONS........................................................................... 9 2.0 EXECUTIVE
SUMMARY
.............................................................................................. 10 3.0 PURPOSE OF THE HISTORICAL SITE ASSESSMENT............................................. 12 4.0 PROPERTY IDENTIFICATION..................................................................................... 13 4.1 Physical Characteristics........................................................................................ 13 4.1.1 License Holder.......................................................................................... 13 4.1.2 Location.................................................................................................... 13 4.1.3 Topography............................................................................................... 14 4.1.4 Stratigraphy............................................................................................... 14 4.2 Environmental Setting.......................................................................................... 15 4.2.1 Geology..................................................................................................... 15 4.2.2 Hydrogeology........................................................................................... 15 4.2.3 Hydrology................................................................................................. 15 4.2.4 Meteorology.............................................................................................. 16 4.2.5 Seismology................................................................................................ 16 4.3 Facility Description............................................................................................... 16 4.3.1 Reactor Building....................................................................................... 16 4.3.2 Building Addition 1.................................................................................. 25 4.3.3 Tagging Area Building............................................................................. 26 4.3.4 Demineralizer Building............................................................................. 27 4.3.5 Heat Exchanger Building.......................................................................... 27 4.3.6 Cooling Towers......................................................................................... 27 4.3.7 Maintenance Office Building.................................................................... 28 4.3.8 Compressor Building................................................................................ 28 4.3.9 Chemical Shed.......................................................................................... 28 4.3.10 Class 1.1 Explosive Storage Container..................................................... 28 4.3.11 Storage Building....................................................................................... 28 4.3.12 Waste Storage Tanks and Sump............................................................... 28 4.3.13 Land Area.................................................................................................. 29 5.0 HISTORICAL SITE ASSESSMENT METHODOLOGY............................................... 72 5.1 Approach and Rationale........................................................................................ 72 5.2 Boundaries of Site................................................................................................. 72 5.3 Documents Reviewed........................................................................................... 72
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TABLE OF CONTENTS (CONTINUED)
Section Page
5.4 Personal Interviews............................................................................................... 72 5.4.1 Richard Newacheck.................................................................................. 72 5.4.2 Ray R Tsukimura...................................................................................... 73 5.4.3 Sandra L Warren....................................................................................... 73 5.4.4 Christopher E Bauman, Alfredo W. Meren, Mitch A. Wilkinson, and Toni R. Richey................................................................................................... 73 6.0 HISTORY AND CURRENT USAGE.............................................................................. 75 6.1 History................................................................................................................... 75 6.1.1 Pre-Operation............................................................................................ 75 6.1.2 Operation................................................................................................... 75 6.1.3 Building Additions and Changes.............................................................. 76 6.2 Contaminant Releases........................................................................................... 76 6.2.1 Reactor Fuel Releases............................................................................... 76 6.2.2 Liquid Releases and Spills........................................................................ 76 6.2.3 Gaseous Releases...................................................................................... 78 6.3 Current Usage....................................................................................................... 78 6.4 Adjacent Land Usage............................................................................................ 78 7.0 FINDINGS........................................................................................................................ 82 7.1 Current Status of the Facility................................................................................ 82 7.1.1 Reactor Building....................................................................................... 82 7.1.2 Building Addition 1.................................................................................. 82 7.1.3 Tagging Area Building............................................................................. 83 7.1.4 Demineralizer Building............................................................................. 83 7.1.5 Heat Exchanger Building.......................................................................... 83 7.1.6 Maintenance Office Building.................................................................... 83 7.1.7 Compressor Building................................................................................ 83 7.1.8 Chemical Shed.......................................................................................... 83 7.1.9 Storage Building....................................................................................... 83 7.2 Potential Contaminants of Concern...................................................................... 84 7.3 Potential Waste Streams/Risk Items..................................................................... 84 7.4 Potential Contaminated Areas............................................................................... 85 7.4.1 Impacted Areas......................................................................................... 85 7.4.2 Non-Impacted Areas................................................................................. 85 7.5 Potentially Contaminated Media........................................................................... 85 7.6 Related Environmental Concerns......................................................................... 86
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TABLE OF CONTENTS (CONTINUED)
Section Page
8.0 CONCLUSION
S............................................................................................................... 89
9.0 REFERENCES
................................................................................................................. 90 9.1 U.S. Nuclear Regulatory Commission (NRC), NUREG-1575, Rev. 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), August 2000....................................................................................................................... 90 9.2 U.S. Nuclear Regulatory Commission, NUREG-1757, Vol. 2, Rev. 1, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria, Final Report, September 2002.............. 90 9.3 Aerojet-General, Drawing CF-64-33-02 Sheet 1 of 11, Nuclear Test Laboratory Civil Site Utilities & Paving Plan, 1964............................................................... 90 9.4 State of California, Department of Finance, E-5 Population and Housing Estimates for Cities, Counties and the State, 2001-2008, with 2000 Benchmark.
Sacramento, California......................................................................................... 90 9.5 USGS Information Services, Box 25286, Denver Federal Center, Denver, Colorado 80255-0046, Preliminary geologic map emphasizing bedrock formations in Contra Costa County, California: A digital database, 1994........... 90 9.6 City of, City of General Plan 2030, Draft EIR, April 5, 2010....................................................................................................................... 90- -
9.7 United States Department of Agriculture, National Cooperative Soil Survey, Web Soil Survey Data for the State of California, Contra Costa County with Area Of Interest around California.................................................................. 90 9.8 Contra Costa County Flood Control & Water Conservation District, Mean -
Seasonal Precipitation Raster from Drawing B-166, December 1, 2009............. 90 9.9 Aerojet-General Nucleonics, AN-1405, Aerojet-General Nucleonics Industrial Reactor (AGNIR) Technical Specifications, April 1965....................................... 90 9.10 Conversations with Richard L. Newacheck, Former President and Manager of Aerotest Operations, March 17, 2011................................................................... 90 9.11 Conversations with Ray R. Tsukimura, Former President and Manager of Aerotest Operations, March 17, 2011.................................................................................. 90 9.12 Conversations with Sandra L. Warren, General Manager of Aerotest Operations, March 17, 2011..................................................................................................... 90 9.13 Conversations with Christopher E. Bauman, Nuclear Engineer; Alfredo W.
Meren, Manager of Reactor Operations; Mitch A. Wilkinson, Manager of Quality Assurance; and Toni R. Richey, Manager of Neutron Radiography, March 17, 2011....................................................................................................................... 90
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TABLE OF CONTENTS (CONTINUED)
Section Page
9.14 Aerojet-General Nucleonics, AN-1193, Aerojet-General Nucleonics Industrial Reactor Hazards Summary Report, September 1964, R. L. Newacheck, Project Engineer................................................................................................................ 91 9.15 Aerojet-General, Drawing (number not readable), Nuclear Test Lab Structural Foundation Plan & Details, 1964.......................................................................... 91 9.16 Aerotest Operations, Inc, Aerotest Radiography and Research Reactor (ARRR)
Updated Safety Analysis Report (USAR) Proposed Revision 0, 2005.................. 91 9.17 Aerotest Operations, Inc, Annual Summary of Changes, Tests and Experiments Performed at the Aerotest Radiography and Research Reactor (ARRR), NRC Docket No. 50-228, reported annually.................................................................. 91
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LIST OF FIGURES
Figure Page
Figure 4-1: Aerotest Operations Site Location............................................................................. 30 Figure 4-2: Aerotest Aerial Image................................................................................................ 31 Figure 4-3: ARRR Local Area View............................................................................................ 32 Figure 4-4: ARRR Area Showing Population Density................................................................. 33 Figure 4-5: ARRR Site and Surrounding Area Topography........................................................ 34 Figure 4-6: Stratigraphy of the ARRR Site Region...................................................................... 35 Figure 4-7: Regional Soil Survey Data......................................................................................... 36 Figure 4-8: Surface Water............................................................................................................. 37 Figure 4-9: Contra Costa County Mean Seasonal Isohyets.......................................................... 38 Figure 4-10: San Francisco Regional Earthquake Hazard Maps.................................................. 39 Figure 4-11: Geotechnical Hazards Map................................................................... 40 Figure 4-12 General ARRR Arrangement Plan -............................................................................ 41 Figure 4-13: Plan Layout of ARRR Reactor Building.................................................................. 42 Figure 4-14: Cross Section of ARRR Reactor Building............................................................... 43 Figure 4-15: Photograph of ARRR N-Ray Area........................................................................... 44 Figure 4-16: ARRR Reactor Core and Support Structure............................................................ 45 Figure 4-17: Reactor Cutaway View Showing Neutron Radiography Facility............................ 46 Figure 4-18: In-Core Irradiation Capsule..................................................................................... 47 Figure 4-19: Radioactive Material Storage Room........................................................................ 48 Figure 4-20: ARRR Machine Shop............................................................................................... 49 Figure 4-21: ARRR Chemistry Lab.............................................................................................. 50 Figure 4-22: ARRR Preparation Lab............................................................................................ 51 Figure 4-23: ARRR Mezzanine Sheet Metal Fabrication Area Looking North........................... 52 Figure 4-24: ARRR Mezzanine Sheet Metal Fabrication Area Looking Northwest.................... 53 Figure 4-25: ARRR Mezzanine Storage Area.............................................................................. 54 Figure 4-26: ARRR Mezzanine Instrument Calibration Area...................................................... 55 Figure 4-27: ARRR Electronics Lab............................................................................................. 56 Figure 4-28: Shipping & Receiving.............................................................................................. 57 Figure 4-29: N-Ray Setup Area.................................................................................................... 58 Figure 4-30: Office Space............................................................................................................. 59
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LIST OF FIGURES (CONTINUED)
Figure Page
Figure 4-31: Customer Viewing Area........................................................................................... 60 Figure 4-32: Quality Control Room.............................................................................................. 61 Figure 4-33: Computer and Counting Room................................................................................ 62 Figure 4-34: Tagging Area............................................................................................................ 63 Figure 4-35: Tagging Area Back Room........................................................................................ 64 Figure 4-36: Backup Cooling Tower............................................................................................ 65 Figure 4-37: Main Cooling Tower................................................................................................ 66 Figure 4-38: Storage Building...................................................................................................... 67 Figure 4-39: Waste Storage Tanks................................................................................................ 68 Figure 5-1: AGN Site and AGNIR Fence (Circa 1960s).............................................................. 74
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LIST OF TABLES
Table Page
Table 4-1 : Gelogic Formation Descriptors.................................................................................. 69 Table 4-2 : Meterological Summary for, CA............................................................ 70 Table 4-3 : Fault Summary for, CA.......................................................................... 71--
Table 6-1 : ARRR Annual Operating Report Summary............................................................... 79 Table 6-2 : ARRR Facility History and Modification Summary.................................................. 80 Table 7-1: Preliminary Classifications Based on MARSSIM Guidance...................................... 87
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1.0 ACRONYMS AND ABBREVIATIONS
° Degrees
°F Degrees Fahrenheit Aerotest Aerotest Operations, Inc.
AGN Aerojet-General Nucleonics, a division of General Tire AGNIR Aerojet-General Nucleonics Industrial Reactor ARRR Aerotest Radiography and Research Reactor CA State of California Ci Curies Co Cobalt COC Contaminants of Concern DOE U.S. Department of Energy HSA Historical Site Assessment L Liter MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual mCi MilliCuries mR/hr MilliRoentgen per hour NRC U.S. Nuclear Regulatory Commission pCi PicoCuries pCi/g PicoCuries per Gram pCi/L PicoCuries per Liter RHB California Radiologic Health Branch of California Department of Health RSSI Radiation Site Survey and Investigation [Process]
UO2 Uranium Oxide TRIGA Teaching Research Isotope General Atomic reactor TS Technical Specification USNRC U.S. Nuclear Regulatory Commission U-ZrH Uranium fuel in a zirconium-hydride matrix
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2.0 EXECUTIVE
SUMMARY
The Aerotest Radiography and Research Reactor (ARRR) consists of a shut-down 250-Kilowatt, TRIGA Conversion reactor. Principal structures include the High Bay Building, the Setup Room Building, the Tagging Room Building, the Forklift Garage, plus several sheds.
The ARRR is a TRIGA (Training, Research, Isotopes, General Atomics) Mark I type reactor that was designed and constructed by the Nuclear Division of Aerojet-General in 1964. It is an open pool type reactor with the pool (i.e., reactor tank) located below ground level. The reactor achieved initial criticality on July 9, 1965 with a licensed steady-state thermal power limit of 250 kW. The TRIGA reactor fuel elements, reflecto r elements, control rods, control rod drive mechanisms, control rod drive controls, and react or protection system were purchased from General Atomics and were incorporated into the ARRR without any significant changes.
The TRIGA is fueled with uranium in a zirconium-hydride matrix sealed inside Type 304 stainless steel or aluminum tubes. The fuel is "less than 20% enriched," so that it is LEU fuel.
The reactor was operated from 1964 to 2010. Aerotest Operations provided Neutron Radiographic Inspection Services since 1969 using the ARRR for the neutron source.
A sites complete history from the start of site activities to the present time is documented in this HSA using existing information collected as part of the RSSI process. Guidance regarding the completion of an HSA is provided in Section 2.4 and Chapter 3 of the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) and Section 4 of NUREG-1757, Vol. 2, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria.
The HSA was completed in two phases. First, a preliminary investigation was performed to collect readily available information concerning the site and surrounding areas. Second, a site reconnaissance was performed to evaluate site conditions and record hazards that would apply to future work. Current potential sources of radiological and chemical contamination as well as hazardous conditions adverse to worker safety are listed below.
Radioactive The reactor fuel is currently in the re actor tank but it will be removed prior the start of any decommissioning activities involving demolition and removal of reactor components.
There are stored activated components and items in reactor tank, in mezzanine storage areas of the High Bay Building, and in the Radioactive Material Storage Room with cobalt-60 as the primary radionuclide of concern with potential for nickel-59 and nickel-63.
There is ion exchange resin contaminated with fission and activation products in the pool water demineralizer and in the spare bed within the Demineralizer Building and also in a larger demineralizer bed located alongside the Maintenance Office and in drums located in the Radioactive Material Storage Room.
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There are potential low levels of building surface contamination with fission and activation products and fuel radionuclides.
There are licensed and exempt radioactive sources used in instrument response testing.
Chemical/Hazardous There are explosives devices to be examin ed by N-Ray that are stored in special vaults. All explosive items will be removed prior the start of any decommissioning activities.
There are areas where Film Developer and Fixer chemicals were used and stored.
All chemical inventories will be removed prior the start of any decommissioning activities.
There are areas where asbestos floor tiles are installed and there may be asbestos insulation on piping.
Based on the age of the facility there are probably areas where lead paint was used. In addition stacks of lead bricks are used in a few locations for local shielding.
There are items with suspected or potential polychlorinated biphenyls containing materials such as fluorescent light ballasts and capacitors.
There are items with mercury such as sealed switches and vapor lights.
There is Freon in the HVAC systems.
There are worker safety concerns including trip areas, and low overhead hazards, and ledges without fall protection.
Contaminant migration is unlikely. The stored activated components and items do not have significant surface contamination. Radioactive waste is stored in closed containers. All historical radiological surveys indicated very low alpha and beta-gamma removable surface activity levels.
The removable activity site limits are 30 dpm/100 cm2 alpha and 200 dpm/100 cm2 beta.
All areas inside the ARRR fenced area were considered impacted except for the roofs of the Buildings and the north parking area. The impacted areas were preliminarily classified using MARSSIM guidance to facilitate future characterization surveys.
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3.0 PURPOSE OF THE HISTORICAL SITE ASSESSMENT
A sites complete history from the start of site activities to the present time is documented in the HSA. Guidance regarding the completion of an HSA is provided in Section 2.4 and Chapter 3 of the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM, Reference 9.1) and Section 4 of NUREG-1757, Vol. 2, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria (Reference 9.2). Specific objectives of the HSA include:
Identify current potential sources of radiological and chemical contamination, Provide assessment for the likelihood of contaminant migration, Determine impacted and non-impacted areas of the site, and Provide information useful to characterization surveys.
Preliminary classifications are assigned to im pacted areas of the site. These preliminary classifications are subject to change based on characterization survey results.
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4.0 PROP ERT Y ID EN TI F I CATIO N
Descr iptions of the phys ical charncter istics and environmental setting of th e ARRR an d smTOlm ding ar ea ar e discussed in this secti on.
4.1 PHY SI C AL C HARA C T E RI S TI CS
4.1.1 Licen se H older
Aero test Operatio ns, Inc., (Aerotest) is th e h older of NRC Faci lity Operating License No. R-98
4.1.2 Locatio n
Th e ARRR is located on the east side of the San Francisco Bay area in _, Contra Costa County, Cali fo rnia. It is located within the city an d ther e are nearby res idential ar eas. Figm e 4-1 sh ows th e ARRR site locatio n and Figme 4 -2 shows aerial imagery of th e site. The site address is give n be low:
The property on which the ARRR is located covers approximate ly 0.9 acres w i th the r eacto r and assoc iated structmes locate d approximate ly in the center of the property. Access to t h e faci lity is v ia a driveway which j oins at a cul-de-sac to t h e n01th of the site. E lectr icity is prov ided to th e site by ove rhead lines, water is provided from an 8-inch water line, gas is prov ided from a 6-inch gas line, sewer is handled by a 4-inc h sewer pipe, and te lephon e and cable ar e prov ided to the site by ove rh ead lines. (Reference 9.39.4 fo r gas, water and sewer and observation for electrical, teleph one and cab l e)
Th e area sm Toundin g ARRR is r esidentia l an d light industr i al. The n ear est r esident resides about 250 feet to t h e east in on as show n in Figme 4 -3 an d there ar e li gh t industrial businesses with in 200 feet of t h e faci lity. The total popu lation of_, estimated for 2008,
is 59,002 (Reference 9.4). The sate ll ite image in Figm e 4-3 provides a vis u al illustration of th e popu lation density around t h e ARRR site.
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4.1.3 Topography
The ARRR is located in the Valley about miles east of San Francisco and miles east of Oakland. It is separated from the East Bay urban complex by a series of ridges and - I I hills up to 1,600 feet high. The site's ground surfaces slopes gently to the southwest. The topography of the surrounding area slopes gently downward to the north and to the south as shown in Figure 4-5.
4.1.4 Stratigraphy
Bedrock formations in Contra Costa County are divided into six Assemblages with a unique stratigraphic sequence bounded by faults. The distinction may be either the presence of rock types not present in other Assemblages (e.g. the diatomite (Tdi) in Assemblage III) or a different stratigraphic relationship among similar rock units (e.g. The Domingene Formation (Td) is depositional on Cretaceous rocks in Assemblage V, but is underlain by other Tertiary rocks (Tm, Tmz) in Assemblage VI). The stratigraphic differences between Assemblages are almost certainly due to angular unconformities and changes in depositional environment in one or more large depositional basins. The significant differences in the stratigraphy of different Assemblages, originally separated but now in close proximity, denotes the juxtaposition of different basins or parts of basins by large offsets along the faults that bound them (as much as hundreds of kilometers, see below).
The Great Valley Sequence is depositionally linked to the Coast Range Ophiolite. Although the contact between the two is a fault everywhere in Contra Costa County, elsewhere in California (as close as Alameda County) the lowest part of the Great Valley Sequence (the Knoxville Formation) is clearly deposited on the ophiolite.
The Franciscan Complex presumably underlies all of Contra Costa County. It was emplaced below the Coast Range Ophiolite by accretionary faulting during Cretaceous time, so the contact between the Franciscan and Coast Range Ophiolite and the overlying Great Valley Sequence is everywhere faulted. This fault is known as the Coast Range fault.
Two types of Tertiary intrusive rocks occur in Contra Costa County, both of which intrude the strata of Assemblage V. In the Concord area, the Markley Formation is intruded by plugs and dikes of Pliocene basalt. East of Mount Diablo, the Great Valley Sequence rocks are intruded by fine grained, quartz bearing rhyolite stocks, dikes, and sills of late Miocene age. The relationship of these hypabyssal intrusives is unknown. Although they occur only in the rocks of Assemblage V, these rocks are not included in th e Assemblage because of their intrusive nature.
The stratigraphy of San Ramon was provided by USGS Information Services Reference 9.5.
Figure 4-6 illustrates the stratigraphy of area located in the southwest corner of Contra Costa County. The geologic data descriptors on the map are described in Table 4-1.
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4.2.1 Geo logy
Geo logy is t h e sci ence t hat deals with t h e h istory of t h e ear th as recorded in rocks. Refere n ce 9.6 prov ided the geolog ical info n nat ion which is smmnai-i zed below.
- is located w it hin th e Cali fo rnia Coast Ranges geomo tphic province. In general the geologic structure an d topograp h y of t he - Valley are ch aracte r is tic of the San Francisco Bay Area. T he regio n is genera~ by n orthwest - tr ending ri dge~ s th at genera lly parallel the geolog i c stmct ures, in clu ding th e majo r fault systems. -
Valley fi ll include ~- age~ pproxima te ly 300 feet t hickness. Th e valley is dra ined by both-and - creeks th at are active ly cutting into th e alluv i al surface soils.
The - va lley is surr ounded by the E ast Bay Hi lls. The hi lls were fo1med from yo unger rocks, up li fted betwee n t he H ayward and Calaveras fau lt zones. The - area is underla in by Te1tia1y (about 2 to 62 mi llio n years ago) marin e and n on-marine sedimenta 1y rocks. Sandstone bedrock crops out locally on r i dge crests and underlies upper hi ll slopes at sha llow depths.
Soils within the gen eral area consist of clays and l oams. Dia bl o Clay, C l ear Lake C l ay, Botella C l ay Loam, Alo Clay, Cropley C l ay, Los Osos Clay L oam, Con ej o C l ay Loam, an d Pescadero C l ay Loam are amo n g th e most common soi ls found in t he gen eral ar ea. Prope1t ies of th e soils va1y, w it h we ll-drained clay so i ls an d the clay loams being moderate or poorly dra in ed. In addit i on, clay so i ls often exhibit substantia l shrink-swell pote nt ial, endemic of expansive so i ls.
The site is on t he bounda1y of two so i l types base d on so i l sm vey data provided by in the U.S.
Depa1t me n t of Agr icult ure. Th e two types of soil indicated are DdE (D i ablo Clay, 15 to 30 per cent sl opes) and Cc (Cleai-L ake C l ay). (Refe r ence 9.7)
Figure 4 -8 displays soil smvey data for th e area around San Ramo n.
4.2.2 Hydrogeo logy
Hydrogeo logy is t he ar ea of geology that deals with th e dis tribut ion and moveme nt of groundwate r in th e soil an d rocks of t h e Eait h 's cm st, common ly in aqui fe rs. No sources of info1matio n r egarding hydrogeo logy of the ARRR site cou l d be located.
4.2.3 Hydrology
The ARRR is betwee n two waters heds: As noted in th e section on T opograp h y, the surround ing ar ea sl opes gently down o t h e n01th and to th e south. The site sto1m wate r mn off is to the n 01t h and west towa r d Creek is the r inci al l ocal drainage, with - Cr eek and r ek being *-
tr ibutai. Creek meanders n 01thwai*d thro u gh and ultimately
, whi ch discha r ges into S uisun Bay near (Refere n ce 9.6). Ther e is a ocated just p as t the site bounda1y to the n 01t acil ity.
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Figure 4-9 shows surface water near the ARRR site (Reference 9.7).
4.2.4 Meteorology
is characterized by a Mediterranean climate, with mild winters and warm summers.
-Temperatures range from an average low of 36.6 degrees Fahrenheit (°F) in January to an average high of 89.0°F in July. Average rainfall is approximately 14 inches.
Table 4-2 summarizes local meteorology, as measured at Livermore Municipal Airport which is about air miles south west from the ARRR site. (Reference 9.6) I
The Contra Costa County data indicates an estimated annual rainfall of 20.5 inches as indicated in Figure 4-9 relative to approximately 14 inches at the Livermore Municipal Airport.
(Reference 9.8)
4.2.5 Seismology
The ARRR is located in the Valley which is surrounded by the East Bay Hills. The hills were formed from younger rocks, uplifted between the Hayward and Calaveras fault zones. -
The area is underlain by Tertiary (approximately 2 million to 62 million years ago) marine and non-marine sedimentary rocks. Sandstone bedrock crops out locally on ridge crests -
and underlies upper hill slopes at shallow depths.
There are several active faults in the immediate and surrounding areas that could affect the area. The nearest major active fault is the Calaveras Fault, which lies parallel to and just
-west of. The California Legislature has established an Alquist-Priolo Earthquake Fault Zone along the Calaveras Fault, requiring detailed studies of rupture hazards prior to construction. The seismic activity, along with the approximate distance and direction of all known mapped active faults with the potential to affect, is summarized in Table 4-3. (Reference 9.6) -
The San Francisco Bay area experiences relatively frequent earthquakes as illustrated in the earthquake hazard map shown in Figure 4-10 (Refer ence 9.9). The region in which the ARRR is located has experienced relatively frequent earthquakes. The nearest known fault, the Calaveras Fault, is about 0.7 miles from the site as can be estimated from the Geotechnical Hazards Map shown in Figure 4-11. (Reference 9.6) -
4.3 FACILITY DESCRIPTION
The ARRR facility includes the reactor building and support buildings as well as several support buildings that were added since the reactor wa s constructed. Figure 4-12 provides a layout of the ARRR buildings and Figure 4-2 provides an overhead view of the site.
4.3.1 Reactor Building
The reactor building is made of steel with inte rnal rooms built of fire resistant framing and sheetrock covering. An automatic sprinkler system covers the entire building. The building has
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airflow control from the standpoint that certain rooms are maintained at a positive pressure relative to the reactor room. The building as a wh ole is not sealed or contained and requires no air-locks. The reactor control room and certain offices are housed in a single building. The control room and offices are in areas where a fre sh air intake is used to maintain the positive pressure relative to the reactor room. The 40 feet x 80 feet main building has a 3 ton capacity bridge crane that can cover the entire area. The reactor tank is embedded in the floor, extending 22 feet below and one foot above the floor surface. A 20 inch thick by 80 inch high block wall made of normal density concrete encloses the reactor area above the floor level. The top of this shield is covered with an 11 inch thick wooden shield. The floor in the N-Ray area is covered with an industrial grade carpet.
Figure 4-13 provides a plan view of the reactor building, Figure 4-14 provides a cross section view of the Reactor Building and Figure 4-15 is a photograph of the N-Ray Area with shielding in place.
4.3.1.1 Reactor Tank and Core
The ARRR was designed and constructed by Aerojet General Nucleonics (AGN) in 1964. The reactor fuel elements, reflector elements, control rods, control rod drive mechanisms, and control rod drive controls were purchased from General Atomics and were incorporated without any significant changes. A standard G ring core grid plate design was provided by General Atomics and manufactured by Aerojet. All other components were designed and constructed by Aerojet or their subcontractors. Figure 4-16 shows the ARRR Core and Support Structure.
The basic nuclear design and core geometry follow General Atomics TRIGA reactor design characteristics. The original core was comprised of all aluminum clad fuel elements; however, new fuel elements are stainless steel clad. The original fuel elements are enriched to 8 weight %
U-235 and the stainless steel clad fuel elements are 12 weight % U-235. As of June 2004, twenty of the stainless steel clad elements have been added.
The principal characteristics of the ARRR are as follows:
(1) Fuel: < 20% enriched U-235.
(2) Moderator: zirconium hydride and water.
(3) Reflector: demineralized water and graphite.
(4) Coolant: demineralized water.
(5) Control: 1 safety rod, 1 shim rod, 1 regulating rod, all boron carbide.
(6) Structural material: aluminum and stainless steel.
(7) Shield (principal materials): demineralized water, concrete, lead, and wood.
(8) Active core dimensions: 19.44 inches diameter (nominal) by 14 inches high for aluminum clad elements and 15 inches high for stainless steel elements.
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4.3.1.2 Experimental Facilities
(1) The N-Ray Facility (Figure 4-17) consists of two part s: a vertical beam tube and the radiography facility. Note that this image does not show the additional concrete and wood biological shielding that was added at a later time. The vertical beam tube is a hollow sealed tube, located adjacent to the core on the east side of the reactor, which extends from the floor of the reactor tank to above the reactor tank water surface. This vertical beam tube, by providing a path that does not contain the water that acts as a shield, allows a beam of neutrons from the core to reach the radiography facility located above the reactor.
The vertical beam tube consists of a two-section tapered tube with rectangular cross section with the weight supported directly by the bottom of the reactor tank. The vertical beam tube has a total length of approximately 23 feet. The top of the beam tube terminates at the bottom of the reactor bridge structure. The extern al dimensions of the beam tube are about 8 inches by 10 inches near the base and tapers to 22 inches by 34 inches at the top. The top of the vertical beam tube is supported laterally at the top of the pool.
The lower 48 inches of the lower section of the vertical beam tube is filled with graphite for moderation of fast neutrons. The upper section of the vertical beam tube is filled with helium which is a better medium for collimat ed neutrons than air which scatters the neutrons. Both the upper and lower sections of the vertical beam tube are equipped with fill and drain lines that are used to remove water or purge the vertical beam tube.
The lower 84 inches of the vertical beam tube is covered with lead for gamma shielding.
This lead shield is 3 inches thick on the reactor side and 1 inch thick on the other three sides. The lead is protected from the pool water by welded sheets of aluminum. All components contacting the pool water are fabricated from aluminum or stainless steel.
The vertical beam tube includes a pneuma tically operated boral (boron carbide and aluminum) shutter mechanism that offers a se lection of 5 aperture settings to provide varying depths of field or resolution. The aperture is located near the bottom of the vertical beam tube just above the graphite.
The neutron radiography facility is integrated into the shielded enclosure directly above the vertical beam tube. The shielded enclosure consists of 20 inch thick concrete block shielding stacked to a nominal height of 80 inches above the floor that surrounds the entire top of the reactor water tank. The neutron radiography facility is supported by 10 inch steel I beams that transmit the weight of the shielding to beams imbedded in the floor of the reactor building. This shielding supports the 11 inch thick wood (fir) beams that cover the reactor enclosure. This sh ielding provides operating personnel additional shielding.
This shielding enclosure is penetrated at the north and south ends on the east side of the reactor by the neutron radiography facility. Access to the top of the vertical beam tube is through openings on both the north and south ends with cross sectional dimensions of
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approximately 37 inches wide by 18 inches high. The facility was designed to allow the neutron radiography of contained detonating cords having lengths in excess of 25 feet.
Concrete blocks in the shield structure may be moved as necessary to accommodate taller objects.
The top of the vertical beam tube is covered by a movable radiation shield called the neutron beam catcher. The beam catcher shield is wood that is 48 inches by 47 inches by 16.5 inches and has wheels that roll on tracks attached to the tunnel. The wheels allow the beam catcher shield to be rolled to the s outh end to radiograph large items on the north end. The beam catcher shield reduces the radiation level due to neutrons and gammas within the reactor room and at the exclusion area fencing.
Figure 4-15 is a photograph of the radiography facility with biological shielding in place.
(2) The Graphite Thermal Column (Figure 4-17) is a large block of graphite, encased in aluminum, containing five rows of seven vertical holes through the graphite block. The vertical holes allow specimens to be inserted into the graphite block for irradiation. The five rows of irradiation holes (A through E) are six inches apart with each row at an increasing radius from the core. The increasing radius of each row allows samples being irradiated to be subjected to different ratios of thermal to fast neutrons.
There are seven irradiation holes in each row. The irradiation holes are 1.5 inches in diameter, similar to the reactor core grid plate, which allows the same capsules or devices that are inserted into the core to be in serted into the graphite thermal column.
The thermal column graphite block measures 4 feet along the radial axis of the core and is 2 feet wide and 2 feet deep. It is located on the south side of the reactor and positioned adjacent to the core. The thermal column is positioned using tapered pins and is bolted to the bottom of the reactor pool tank. Installation and removal of the whole assembly is accomplished with the facility crane and remote handling tools.
Two irradiation holes in the thermal column are configured for specific tasks:
One irradiation position in the first (A) row is fitted with an aluminum tube, identical in design to the glory hole (described later), that extends to the top of the reactor water tank above the wood (fir) block shield. Material to be irradiated is lowered through the tube into the thermal column. This tube has a rotating motor to slowly rotate the sample and thus provide an evenly distributed irradiation to the sample. A shield plug is placed in the top of the tube to reduce gamma scattering to acceptable levels.
A second position in the first (A) row is fitted with a detector calibration system.
Small fission detectors can be calibrated against a standard in this facility.
A third position includes a one inch diameter neutron beam tube which can be located between the thermal column and N-ray tube and which extends to the area above the top reactor shield. This tube is used for the source of neutrons for the N-gage device.
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The thermal column structure is also used to mount other experimental facilities. Four slotted beams, two on each side, are provided to allow experiments to be attached directly to the thermal column. Extensions of th ese beams allow experiments to be placed immediately adjacent to the reactor core.
(3) The Glory Hole Facility is an aluminum tube, 1.5 inches in diameter, which will fit into any fuel element hole. The hollow tube extends from the lower grid plate to above the top of the wood (fir) shield on top of the reactor water tank. The tube is not filled with water and is used to lower material to be irradiated through the tube into the core region. The glory hole will accept capsules with a maximum diameter of 1.35 inches.
Technical Specifications allow a maximum of one glory hole facility that may be installed in selected locations in any of the seven rings in the core grid plates. At the ARRR, the glory hole is typically installed in the F-2 position of the core.
The glory hole may be used with or without an internal shield plug that reduces the radiation streaming at the top of the reactor water pool in the vicinity of the CRDs.
Technical Specifications require that the glory hole be purged with CO2 to prevent the formation of excessive amounts of 41Ar during reactor operation. When operated with a shield plug, the glory hole is purged prior to each insertion of the shield plug. When operated without a shield plug, the glory hole is purged continuously when the reactor is operating. Additionally, when operated without a shield plug, the installed gas sampling system must be selected to sample in the immediate vicinity of the glory hole so that corrective action can be taken to prevent the release of gaseous activity in excess of 10 CFR 20 limits.
(4) The Central Core Irradiation Facility is a hexagonal section th at can be removed from the center of the upper grid plate to allow insertion of specimens into the core region of highest flux. Use of the central core irradiation facility requires prior relocation of the central fuel element and the six elements fr om the B-ring. Technical Specifications limit the size of the central core irradiation facility to 16 square inches. The facility will accommodate specimens up to about 4.4 inches in diameter.
(5) The Triangular In-Core Irradiation Facilities consist of two sections cut out of the upper grid plate, each of which encompasses one D-ring and two E-ring holes. When fuel elements are placed in these locations, th eir lateral support is provided by special aluminum pieces. With the aluminum spacers removed, each of these triangular sections allows the insertion of circular experiments to a maximum of 2.35 inch diameter or triangular experiments to a maximum of 3.0 inches on a side.
(6) The In-Core Irradiation Capsules (Figure 4-18), approximately the same size and shape as a fuel element, are used to irradiate samples and can be used in any open position of the core or in the graphite thermal column. The capsules are usually sealed at the top by a gasket and threaded fitting but also have provisions for bringing instrumented tubes to the surface.
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In-core irradiation capsules are inserted and removed from the core using the fuel element handling tools. A transfer shield is used to transport the capsule within the ARRR building.
The capsules are designed to have a maximum inner void volume of 34 cubic inches in the active fuel region.
(7) The Large Component Irradiation Box is an aluminum box with an internal volume of up to 20 cubic feet that can be installed in the reactor water tank. The walls of the box are thin to minimize parasitic neutron absorption.
The large component irradiation box can be installed, as needed, by being lowered onto the movable table and bolted in place with remote handling equipment. The box is positioned on the movable table using tapered locating pins and bolted to the movable table that is, in turn, bolted to the bottom of the ARRR reactor water tank. To remove or install the experiment box, the movable table is required to be moved two or more feet away from the reactor core. The movable table is positioned remotely relative to the reactor core but has positive mechanical stops that prevent moving the box closer than 5 centimeters from the outer ring. When at th e position closest to the core, the large component irradiation box cannot encompass more than a 120° arc of the core.
The large component irradiation box must be purged of air prior to exposure to neutrons.
Therefore, when installed, the large component irradiation box is pressurized with CO2 to 0.5 psi above the water pressure. The box is weighted with lead to eliminate buoyancy.
The large component irradiation box is not currently installed in the reactor water tank, because ARRR does not currently use and has no plans for future use of the large component irradiation box.
(8) The Pneumatic Transfer Facility is designed to quickly transfer individual specimens into and out of the reactor core. The specime ns are placed in a small polyethylene holder, "rabbit," which in turn is placed into the receiver. The rabbit travels through aluminum tubing to the terminus at reactor core centerline and then returns along the same path to the receiver. Directional CO2 flow moves the rabbit between receiver and terminus. A solenoid valve directs air flow using a timer to regulate the exposure of the sample. A manual control, capable of overriding the automatic timer control, is also provided.
The pneumatic transfer facility may be lo cated in any reactor core position. When installed, the facility is operated with dry CO 2 and exhausted through a filter ventilation system, which is monitored for radioactivity. The in-core portion of the transfer facility has a maximum void volume of 34 cubic inches so that the effects on reactivity are similar to other experiments that are placed in the active core.
The pneumatic transfer facility is not currently installed in the reactor water tank because ARRR does not currently use a pneumatic transfer facility and most of the parts to this system are no longer on site.
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(9) The Beam Port was never finished but the ARRR was designed to facilitate future installation of a horizontal beam port. The ARRR reactor tanks concrete embedment includes one penetration consisting of one 24 inch outside diameter pipe about 13 ft long that butts up against the outside of the reactor tank on the center line of the core. The pipe sleeve was provided so that a horizontal beam port could be installed without having to break through the concrete around the tank. However, the beam port facility was never installed and the reactor tank wall is not cut open at this location.
4.3.1.3 Coolant System
The ARRR cooling system is comprised of three basic parts: the reactor water tank, the cooling system, and the demineralizer system. The pool water provides convection cooling, neutron and gamma shielding and neutron moderation. The cooling system provides heat removal to a cooling tower via a heat exchange r. A new cooling tower was installed several years ago and the old cooling tower with redwood louvers was retained as a backup for the new tower. The demineralizer system maintains the purity of the water. A replacement demineralizer with a much larger capacity was obtained several years ago and it was used for a short period. Because of its large size it could be operated for a long period before change out of the resin was required.
However this also resulted in the accumulating of greater quantities of radioactive isotopes which raised radiation levels in the resin bed to unacceptable levels and further used of the large bed demineralizer was halted. A fourth component is the reactor water tank makeup system. This system is comprised of a small ion exchange co lumn connected to the city water supply and redundant level control valves for the reactor water tank. Figure 4-12 provides locations for the demineralizers, the heat exchanger and the cooling towers.
4.3.1.4 Radioactive Waste and Radiation Protection
The ARRR generates very little radioactive waste. Most of the induced radioactivity is short half life material and can be stored until the radioactiv ity decays. Radioactive waste is stored in the Radioactive Material Storage Room as located in Figure 4-12. The radioactive materials stored in the room include demineralizer resin removed from the demineralizers and stored in a drum, contaminated Personal Protective Equipment, radioactive sources, filters, contaminated or irradiated materials removed from reactor durin g repairs and modifications, and miscellaneous contaminated or irradiated items.
4.3.1.5 Radioactive Material Storage Area
The Radioactive Material Storage Area is a locked room with restricted access and it is used to store demineralizer resin removed from the demineralizers and stored in drums, contaminated Personal Protective Equipment, radioactive sources, used filters, contaminated or irradiated materials removed from reactor during repairs and modifications, and miscellaneous contaminated or irradiated items. The floor in the room is covered with what appears to be 8-in by 8-in asbestos floor tiles.
Figure 4-20 is a photograph of the Radioactive Material Storage Area which encompasses
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4.3.1.6 Office Supply Room
The Office Supply Room is located against the south wall of the reactor building as shown on the general layout drawing in Figure 4-12. It is used to store office supplies and has a concrete floor and no false ceiling. The area was previously a tagging room that used acetone and Gd(NO3)3.
4.3.1.7 Machine Shop
The Machine Shop is currently little utilized but it was used to machine repair parts and parts for new experimental facilities. There is a box of unused 8x8 asbestos floor tiles on the floor in the room and the floor is covered with similar tile s. The shop was reported to have been used to machine contaminated or activat ed parts in the distant past.
Figure 4-20 is a photograph of a portion of the Machine Shop.
4.3.1.8 Control Room
The Control Room contains the r eactor operating console and lies at the end of the western utility trench. The floor is carpeted; there is a false ceiling, a viewing window into the N-Ray area and a locked door entry into the N-Ray area. No records indicating radiological or chemical use or storage were identified.
4.3.1.9 Chemistry Lab
The Chemistry Lab is a small room that contains two work bench cabinets, a fume hood and two sinks, the Cold Sink which drains to the sewer and the Hot Sink which drains to an outdoor waste holdup and sampling tank. The regular sink has overflowed and flooded the Chemistry Room and the adjacent Prep aration Lab and before the water was shut off. The floor in the room is covered with what appears to be vinyl 12-in by 12-in floor tiles.
Figure 4-21 is a photograph of a portion of the Chemistry Lab including the Cold Sink.
4.3.1.10 Preparation Lab
The Preparation Lab is a small room that contains a work table, marble weighing table and non-radioactive waste disposal drum. The floor in the room is covered with what appears to be vinyl 12-in by 12-in floor tiles.
Figure 4-22 is a photograph of a portion of the Preparation Lab.
4.3.1.11 N-Ray Gauge Office
The N-Ray Gauge Office is a small room across a hallway from the Preparation lab that has a desk and work table for preparing the N-Ray gauges prior to use. The hallway and office floors are covered with what appears to be 8-in by 8-in asbestos floor tiles.
The N-Ray Gauge Office has a doorway to the hall and a doorway that accesses the top of the bioshield.
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4.3.1.12 - StorageArea
The-Storage Area is an open topped po1tion of the-tha t is ne xt to the N Ray area. This area contains the control room HV AC system, a storage area for spare mechanical
~ s01ts, a storage area for inadiated i tems, and wall mounted cabinets j ust off the
- and over the bioshield that are u sed to store reactor pool tools. The floor in the a rea is mostly bare wood but a small po1tion is covered with room is covered w ith what appear to be 8-in by 8-in asbestos fl oor tiles.
Figure 4 -23 is a photograph of the Storage Area and Figure 4-24 is a photograph of the Storage Area and HV AC System.
4.3.1.13 Shee t Metal Fabrication Area
The Sh eet Meta l F abrication Area is an open to pped po1tion-that is j ust an extension of the-Storage A re a. It is cmTent ly a st~ are mechanical paits and the floor is cove r ed with what appear to be 8-in by 8-in asbestos flo or tiles.
Figure 4 -25 is a photograph of the Shee t Metal Fabrication Area.
4.3.1.14 Instrument Calibration Are a
The-Storage Area is an open topped portion of the-th at is n ext to the Che~ and Preparation Lab. This area is used for insb~rations and coatin g of Exposme Trays. It contains a drawing table used for reviewing drawings and calibrating insbuments at fixed dis tances from som ces, a coating mixer, drawing storage drawers and files, and miscellaneous other equipmen t and HV AC compone n ts. The fl oor is covered w ith what appeai* to be 8-in by 8-in asbes tos floor tiles.
Figure 4-26 is a photograph of the Insbument Calibration A re a.
4.3.1.15 Electi*onics Lab
The Electronics Lab is a sma ll room th at is next to the Instrument Calibra tion Area. This ai*ea contains spare electi*ical parts of all so11s and the floor is cove red with what appeai* to be 8-in by 8-in asbes tos floor tiles. No r ecords indicating radiological use or storage were identified. Records indicate tha t there may ha ve been a PCB oil spill in the room tha t was cleaned up immediately after the sp ill.
Figure 4 -27 is a photograph of the Electi*onics Lab.
4.3.1.16 Offices and Resti-oom Areas
The Restrooms and Offices in the reactor building are as sh own on the general layo ut in Figure 4 -1 2. Rooms 14 and 15 ai*e r esti*ooms with wh at appears to be viny l 12-in by 12-in fl oor tiles, false cei lings and drains that connect to the city sewer system. Room 17 is the General Manager's Office, Room 18 is a h allway and the Business Office, and Room 19 is the
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Accounting Office. These offices have floors covered with industrial grade carpet and they have false ceilings. No records indicating radiological or chemical use or storage were identified.
4.3.2 Building Addition 1
Building Addition 1 is a 45 foot by 60 foot steel structure with internal rooms built using fire resistant framing and a double layer or sheetrock. An automatic sprinkler system covers the entire building. The building as a whole is not sealed or contained and requires no air-locks. This area provides essential support functions for the N-Ray operation. This building contains the shipping and receiving, N-Ray Setup Area, Counting Room, office space, film viewing room for customers, Quality Control Room, Dark Room, Explosive Store Room & Safe, and the Film Storage Room as shown on the general layout in Figure 4-12.
4.3.2.1 Shipping & Receiving
The Shipping and Receiving area is sometimes referred to as the garage as it has a garage type rollup door. This area has large metal shelves and a high ceiling, approximately 25-ft by 14.5-ft by 13 feet tall, metal shelving, a bare concrete floor and the doorway into the Film Storage area.
No records indicating radiological use or storage were identified.
Figure 4-28 is a photograph of the Shipping & Receiving area.
4.3.2.2 N-Ray Setup Area
The N-Ray setup area includes a large portion of the Building Addition 1 structure, approximately 38.5ft by 34-ft, as shown in Figure 4-12. The floors are bare concrete, the ceilings are over 13 feet in height and there are doorways to the outside, and operating areas. This area also includes several heavy duty work tables that are used to setup the exposure trays for N-Ray radiography work. No records indicating radiological use or storage were identified.
Figure 4-29 is a photograph of the N-Ray Setup Area.
4.3.2.3 Film Storage Room
The Film Storage Room is a 9.8-ft by 6-ft by 8-ft tall room of the Shipping &
Receiving area as shown in Figure 4-28. There is also space between the roof of the Film Storage Room and the ceiling of the Building 1 Additio n that is used for temporary storage of miscellaneous items. This room was used as a second explosive storage safe when two non-compatible explosives needed to be stored in-house at the same time.
4.3.2.4 Explosive Storage Safe
The Explosive Storage Safe is a 9.8-ft by 6-ft by 8-ft tall room of the Shipping & Receiving area as indicated in the layout drawing shown in Figure 4-12. Some of the items that are radiographed contain explosive initiators and that are temporarily stored in this room before and after radiography. No records indicating radiological or chemical use or storage were identified.
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4.3.2.5 Offices and Film Handling Areas
There is a hallway, Office Space area, a Customer Viewing Room, a Quality Control Room and a Dark Room located along the of the Building 1 Addition. The Office Space area is a 16-ft by 13-ft by 8-ft tall room with carpeted floor and drywall finished walls and ceiling that -
includes desks and work tables for staff use as shown in Figure 4-30. The film viewing room for customers is a 16-ft by 10-ft by 8-ft tall room with carpeted floor and drywall finished walls and ceiling that includes facilities for clients to view completed radiographs as shown in Figure 4-31.
This room also has a closet that holds the fixer sump and backup replenishment tanks along with a water heater. The Quality Control Room is a 16-ft by 9-ft by 8-ft room with tiled floor and drywall finished walls and ceiling. This room includes film processing equipment, facilities for temporary storage of radiographs, and equipment for viewing radiographs as shown in Figure 4-32. The Dark Room is a 16-ft by 11-ft by 8-ft tall room with vinyl tiled floor and black drywall walls and ceiling, as shown on the general layout in Figure 4 12. This room is utilized for film processing and it contains a sump that receives overflow from the developer along with running water. The sump water is passed through a Filter and then steel wool. The steel wool collects excess silver that is then removed by an independent contractor for processing. The processed water passes down the sewer. No records indicating radiologica l use or storage were identified.
4.3.2.6 Computer and Counting Room
The Computer and Counting Room is an 11-ft by 7.5-ft room located at the of the N-Ray Setup area as indicated in the layout drawing shown in Figure 4-12. This room has a shielded cave with sodium iodide detector and instrumentation and supplies for counting samples as well as exempt sources for performing instrument response checks.
Figure 4-27 is a photograph of the Computer and Counting Room.
4.3.3 Tagging Area Building
The Tagging Area Building is a 20 foot by 40 foot steel structure with internal rooms built of fire resistant framing and sheetrock covering except for the wall toward the Reactor Building which is a cinderblock wall. An automatic sprinkler system covers the entire building. The building as a whole is not sealed or contained and requires no air-locks. It contains the Tagging Area, the Tagging Area Back Room, a Safe, and an entry vestibule as shown on the general layout in Figure 4-12.
4.3.3.1 Tagging Area
The Tagging Area includes a 35-ft by 19-ft portion of the Tagging Area Building as shown in Figure 4-12. The floors are bare concrete, the ceiling is over 12 feet in height and there are doorways to the outside, and operating areas. This area also includes many heavy duty work tables that are used to setup the exposure trays for N-Ray radiography work. No records indicating radiological use or storage were identified.
Figure 4-34 is a photograph of the Tagging Area with the entry vestibule shown at the back.
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4.3.3.2 Tagging Area Back Room
The Tagging Area Back Room is a portion of the tagging operation that was walled off and contains several pieces of equipment used in the tagging operations. No records indicating radiological use or storage were identified.
Figure 4-35 is a photograph of the Tagging Area Back Room.
4.3.3.3 Safe
The safe is 6.5-ft by 7-ft by 3-ft tall locked room that is used to if there is any on site.
4.3.3.4 Entrance Hallway The Entrance Hallway is a by 4.5-ft by 8-ft by 8-ft tall room - that connects to the outside, the Reactor Building and the Tagging Area as shown in Figure 4-12. It has a concrete floor with -
drywall on walls and ceiling. No records indicating radiological or chemical use or storage were identified.
4.3.4 Demineralizer Building
The Demineralizer Building is a 7.5-ft by 3.6-ft by 7-ft tall small metal structure on the of the Reactor Building as shown in Figure 4-12. It contains the demineralizer system which -
includes a pump, demineralizer bed, filters, gauges, valves and typically a used resin bed left in the building for decay prior to removal of the resin for disposal.
4.3.5 Heat Exchanger Building
The Heat Exchanger Building is a 12-ft by 4-ft by 7-ft tall metal structure built with a shallow concrete basin for the floor. It is located at the of the Reac tor Building as shown in Figure 4-12. It contains a stainless steel shell and tube heat exchanger, a primary side stainless -
pump with 5-HP motor, a flow switch and various valves. This building also contains a water monitor (radiation detector) and check source.
4.3.6 Cooling Towers
There are two cooling towers located close to the Heat Exchanger Building. The old tower is currently a backup system in case the current tower is shut down for any reason. The old tower is approximately 8-ft by 16-ft by 7-ft tall with a painted steel shell, blower on top and redwood vanes on the interior as shown on Figure 4-36. The new tower is approximately 6-ft by 5.5-ft by 8-ft tall with a painted steel shell, blower on top and galvanized steel packing on the interior as shown on Figure 4-37.
Located in the area between the Heat Exchanger building and the Backup Cooling Tower is the heat exchanger secondary side iron and bronze pump with 5-HP motor, piping and valves. No records indicating radiological use or storage were identified.
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4.3.7 Maintenance Office Building
The Maintenance Office Building is a 12.5-ft by 9.5-ft by 7-ft tall wood structure with metal roof on the of the High Bay Building. There is a plywood panel addition on the south exterior of the building that houses a backup demineralizer that is much larger than the regular -
demineralizer. The backup demineralizer was obtained several years ago and it was used for a short period. Because of its large size it could be operated for a long period before change out of the resin was required. However this also resulted in the accumulating of greater quantities of radioactive isotopes which raised radiation levels in the resin bed to unacceptable levels and further used of the large bed demineralizer wa s halted. The backup demineralizer is disconnected and left in place.
4.3.8 Compressor Building
The Compressor Building is a 14-ft by 8-ft by 8-ft tall metal structure on the of the Operations Building. It contains two conventional piston type air compressors and three oil-filled -
vacuum pumps. No records indicating radiological use or storage were identified.
4.3.9 Chemical Shed
The Chemical Shed is a 6.5-ft by 4-ft by 6-ft tall metal structure mounted on wooden skids located the of the Operations Building as shown on Figure 4-1. No records indicating radiological use or storage were identified. -
4.3.10 Class 1.1 Explosive Storage Container
Class 1.1 Explosive Storage Container is a 6-ft by 4-ft by 4-ft tall metal box on skids located on the of the Storage Building. It has not been used. No records indicating radiological or chemical use or storage were identified.
4.3.11 Storage Building
The Storage Building also known as the forklift garage is an un-insulated 24 foot by 26 foot steel structure built of fire resistant framing and metal walls and ceiling. The Storage Building is not connected to any other buildings and it has a It is used for forklift parking, equipment and supply storage, and fabrication area. The interior of this building is shown in Figure 4-38.
4.3.12 Waste Storage Tanks and Sump
The Waste Storage Tanks and Sump are located on the of the Reactor Building as shown on Figure 4-12. There is a larger tank and a smaller tank and a below grade sump. The -
smaller tank is out of service and lying on its side awaiting repair as the painted surface had shown signs of corrosion. These tanks are shown in Figure 4-39
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4.3.13 Land Area
All of the sites 0.9 acres are fenced in with a chain link fence. The fence has a truck gate that allows access to the Shipping and Receivng area and a personnel gate that enters the Reactor Building near the Control Room as indicated on Figure 4-12. Most of the outside area is paved as can be seen in Figure 4-2. There are seepages of groundwater upward through cracks in the pavement on the north end of the site that are collected and drained by a ditch just outside the north site fence.
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Figure 4-10: San Francisco Regional Earthquake Hazard Maps
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Figure 4-16: ARRR Reactor Core and Support Structure
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Radiation Beam Catcher Shield
Neutron Radiography Facility
Reactor Core
Thermal Column
Figure 4-17: Reactor Cutaway View Showing Neutron Radiography Facility
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LEAD BALLAST
SEAL
IRRADIATION VOLUME
Figure 4-18: In-Core Irradiation Capsule
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Figure 4-19: Radioactive Material Storage Room
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Figure 4-22: ARRR Preparation Lab
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Figure 4-30: Office Space
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Figure 4-39: Waste Storage Tanks
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T a bl e 4-1 : Ge olo gic F ormati on D esc ript or s
Va lu e D efinition
Qu Surficia l deposits, undivided (Pleistoce n e and Holoce n e)
Tbe E member ofWa!Ziler (1978) - Bri ones F01mat i on (Mi ocene)
Tbg G membe r of Wagne r (1978) - B r iones F 01matio n (Mioce n e)
Tbr Brion es Formatio n (Miocene)
Tc Cierbo Sandstone (Mi ocene)
Tgvt Green Va lley and Tassajara Fo1mat i on s of Condu i t ( 1938), un div i ded (Mioce n e and Pli ocene)
Tn Nerolv San dsto ne (Mioce n e)
Tro R odeo Sh ale, H ambre Sandstone, Tice Sh ale, an d O ursan Sandsto n e, undiv i ded (Mi oce ne)
Tus Unnamed sed imenta1y and volcan i c rocks (Miocene and Pliocene)
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T a bl e 4-2 : M et e rolo g ic a l S umma ry for C A
T emp e rature ( 0 F)
M onth Pr ecipitation ( in ch es)
Ave r age M inimum A ve rage M a ximum
Janu a1y 36.6 56.7 3.00
Febmruy 39.4 61.2 2.48
Mru*ch 4 1. 2 65.3 2.14
Apr i l 43.5 70.5 0.99
May 47.6 76.4 0.44
Jun e 51.6 83.1 0.1
July 54.2 89.0 0.02
August 54.0 88.2 0.04
September 52.4 85.8 0.22
October 47.6 77.8 0.64
November 4 1.0 66.4 1.56
December 37.0 57.5 2.57
A nnual Ave ra ge 45. 5 7 3.2 14. 2 1
Notes :
Measurements taken a t Live1more Municipa l A it'port, the nearest weather st ation to the ARRR 9ru 1es).
Period of Record : Janua1y 1, 1903 through Augus t 3 1, 2009 Sour c e : Wes t ern Regiona l Clima te Center, 2010.
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Table 4-3 : F ault Summ ary for CA
Dis ta n ce fr om R e la t i on ship to Slip R at e Max imum Move ment Fa u lt/Fault Z o n e -- (in c h es/year ) M a gnitude
Cal av eras Southwes t 0.24 6.8
Conco rd-Green Valley No1th 0.24 6.9
Hayward Southwest 0.35 7. 1
Greenville No1theast 0.08 6.9
Grea t Valley No1theast 0.06 6.7
San Andreas Southwes t 0.94 7.9
Monte Vista -Shannon Southwes t 0.02 6.5
Rodgers Creek Northwes t 0.35 7.0
San Gre gorio Southwes t 0.2 7.3
West Napa Northwes t 0.04 6.5
Sargent South 0. 12 6.8
O1tigali ta Southeast 0.04 6.9
Point Rayes No1thwest 0.01 6.8
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5.0 HISTORICAL SITE ASSESSMENT METHODOLOGY
5.1 APPROACH AND RATIONALE
This HSA describes the Aerotest site history from the start of activities to the present time. The completion of this HSA followed guidance provided in Section 2.4 and Chapter 3 of MARSSIM (Reference 9.1) and Section 4 of NUREG-1757, Vol. 2 (Reference 9.2). The HSA was completed in two phases. First, a preliminary investigation was performed to collect readily available information concerning the site and surrounding areas. Second, a site reconnaissance was performed to evaluate site conditions and record hazards that would apply to future work reconnaissance information was included as part of Section 4.3.
5.2 BOUNDARIES OF SITE
The ARRR site boundary has always been approximately 0.9 acres. However the ARRR was originally known as the Aerojet-General Nucleonics Industrial Reactor (AGNIR) and it was part of the Aerojet-General Nucleonics plant that occupied property that is now adjacent to ARRR.
The Aerojet-General Nucleonics facilities for nuclear research, development, and production were located on a 498 acre tract. A plan of the site, showing the location of the AGNIR facility is shown in Figure 1 (Reference 9.9). All of the other property was sold and only the ARRR remains.
5.3 DOCUMENTS REVIEWED
Aerotest has maintained historical records at the site including many drawings and sketches.
Section 9.0 lists ARRR-related documents that were reviewed and referenced in this report (excluding References 9.1 and 9.2). In addition, the document types listed below were reviewed and may not have been specifically referenced.
Operational records Diagrams of:
HVAC systems Ventilation systems Electrical systems Water piping Radioactive liquid waste piping Miscellaneous mechanical systems Tax records/property assessments 5.4 PERSONAL INTERVIEWS
5.4.1 Richard Newacheck
Richard Newacheck is a retired former president of Aerotest who managed operations from 1979 through 1988. Richard was also responsible for reactor designs that competed with General
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Atomics, Primarily the AGN 201 100 watt reactor. Richard Newacheck lives in the area and can be contacted through current ARRR staff. (Reference 9.10)
5.4.2 Ray R Tsukimura
Ray R Tsukimura is a retired former president of Aerotest who managed operations from 1993 through 2007. Rays home phone number is (925)934-0791, his cell number is (925)285-3809, and his e-mail address is rtsukimura@yahoo.com (Reference 9.11)
5.4.3 Sandra L Warren
Sandra Warren is the General Manager, Security Officer and Radiological Safety Officer for Aerotest Operations, Inc. Sandras office number is (925) 866-1212 and her e-mail address is aonray@prodigy.net or slwarren58@yahoo.com (Reference 9.12)
5.4.4 Christopher E Bauman, Alfredo W. Meren, Mitch A. Wilkinson, and Toni R. Richey
Christopher E Bauman is a Nuclear Engineer, Alfredo W. Meren is the Manager of Reactor Operations, Mitch A. Wilkinson is the Manager of Quality Assurance, and Toni R. Richey is the Manager of Neutron Radiography for Aerotest Operations, Inc. The office number is (925) 866-1212 and the office e-mail address is aonray@prodigy.net (Reference 9.12)
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0 IOO~JOl>HOSOO SCALE, ft 0 I I
'- FARM I
<J a BU ILDINGS EXCLUSION FENCE
{Owned ond contTOlled by AGN)
- *-*./":GNIR BUI LDING I
BUI LIND ICATED IN CIRCLES DING NUMBERS ARE
PROPERTY LI NE
Figure 5-1: AGN Site and AGNIR Fence (Circa 1960s)
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6.0 HISTORY AND CURRENT USAGE
6.1 HISTORY
A summary of the facility history and modifications is provided in Table 6-2.
6.1.1 Pre-Operation
In September 1964, AGN proposed to build the Aerojet-General Nucleonics Industrial Reactor (AGNIR), a 250-kw research reactor, at its plant site near, California and generated a Hazards Summary Report for the project (Reference 9.14). The justification for construction of -
the facility was for the facility to be used to generate hydrazine. Some experiments were conducted but this facility was never used to produce hydrazine (Reference 9.10).
The ARRR is a TRIGA Mark I type reactor that was designed and constructed by the Nuclear Division of Aerojet-General in 1964. It is an open pool type reactor with the pool (i.e., reactor tank) located below ground level. The reactor fuel elements, reflector elements, control rods, control rod drive mechanisms, and control rod drive controls were purchased from General Atomics and were incorporated without any signif icant changes. A standard G ring core grid plate design was provided by General Atomics and manufactured by Aerojet. All other components were designed and constructed by Aerojet or their subcontractors (Reference 9.16).
There was a Hot Cell in the building at one ti me and the Reactor Building footing drawing (Reference 9.15) shows a foundation slab for the hot cell in the general area of the current Machine Shop. The hot cell was never used as part of the AGNIR operations, but it was used by AGN for a short period of time and then it was removed from the Reactor Building in 1969 (Reference 9.10).
6.1.2 Operation
The initial fuel loading for the AGNIR utilized previously used aluminum clad fuel elements provided by GA. The reactor achieved initial criticality on July 9, 1965 with a licensed steady-state thermal power limit of 250 kW.
The ARRR has provided a neutron source for research and development and services, mainly neutron radiology. Irradiation services for activation analyses have included: crude oil and hydrocarbon samples for oil companies; plastic slides impregnated with microscopic quantities of fissionable materials; ocean silt samples for the Bureau of Mines; and, silver iodide in snow samples from cloud seeding. Other irradiation services have included: calibration of power reactor fission detectors; radiation damage effects studies of solid state electronic components; detection of gunshot residue in paraffin; lattice deformation studies in ammonium perchlorate; and, spallation experiments with uranium dioxide (Reference 9.16).
The reactor irradiation services were cataloged in an Experiments Logbook and reported to the NRC as part of an Annual Summary of Changes, Tests and Experiments Performed at the Aerotest Radiography and Research Reactor (ARRR) (Reference 9.17). These same reports document the annual operating hours and accumulate d kw-hours. The reactor has accumulated a
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total of 14,107,874 kw hours after 69,582 hours0.00674 days <br />0.162 hours <br />9.623016e-4 weeks <br />2.21451e-4 months <br /> of operation. A summary of the reactor operating history obtained from the annual reports to the NRC (Reference 9.17) is provided in Table 6-1.
6.1.3 Building Additions and Changes
Over the course of its operating life several buildings were added and several changes were made to existing facilities. These additions and changes are summarized below:
The Chemistry Lab was moved from the location of the current
. Date estimated between June of 1973 and July of 1974.
The Employee Locker Room was formerly the QC Laboratory.
The General Managers Office was a dark room for processing radiographic film between June of 1973 and 1982.
A portion of the Reactor Building was converted to office space and shops between June of 1973 and July of 1974. The new rooms included the Conference Room, three (3) offices, 2 shop areas and a quality control inspection area. The Conference Room is in its current location, the three offices were in the area where the Business Office and the Accounting Office are currently located, and the two shop areas include the current Machine Shop location and the current Office Supply Area.
The Building Addition 1 (N-Ray Setup Area etc.) was started in June of 1980 and was finished in February 1982.
The Tagging Area Building was added between June of 1981 and February of 1982.
The Storage Building was added between June of 1985 and July of 1986.
6.2 CONTAMINANT RELEASES
The investigation did not identify any releases of radioactive material (activity levels greater than public release limits for air or water to sewers). Details are provided below.
6.2.1 Reactor Fuel Releases
There was only one instance of a leaking fuel element reported during the operation of the ARRR. The reactor achieved initial criticality July 9, 1965 and the ruptured fuel element was located and removed from the core in November of 1965 (Reference 9.17). The fuel element was immediately shipped offsite for disposal (Reference 9.16).
6.2.2 Liquid Releases and Spills
Small quantities of liquid radioactive waste were generated by regeneration of the demineralizer in the demineralizer loop and, infrequently, from liquids irradiated as part of sample irradiation.
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The radiation level from such liquids is extremely low and does not produce radiation exposure hazards.
Most of the low level liquid waste was from th e reactor pool. The pool water contains very low levels of long half-life radioactivity so it was necessary only to store the water until the short half-life material decays away.
Two above ground storage tanks and one sump tank were used for storage of liquid wastes which could be contaminated. The sump tank was used to collect liquids from the trenches around the reactor, the heat exchanger building, the demineralizer building, and one of the chemical laboratory sinks. Potentially contaminated liquids were completely isolated from the sanitary sewer system. An automatic sump pump moved the waste to the primary waste storage tank.
When the primary tank was nearly full, which occu rred every few years, samples were taken for laboratory analysis of the level and type of radioactivity. After laboratory tests showed exempt levels of radioactivity, then the waste was released to the sanitary sewer system after permission was received from the Central Contra Costa Sanitary District. Typical releases, based on holdup tank sample analysis, were 5.68E-12 curies gross alpha and 2.46E-10 curies gross beta in 600 gallons of waste liquid. Sampling and analysis of a liquid release was performed by a certified laboratory and the release was controlled by a permit from the Central Contra Costa Sanitary District.
A second above ground tank was used to temporarily store waste while the primary tank liquid was being analyzed for radioactivity prior to releas e (Reference 9.16).
There were no instances of surface water flooding that may have contributed to an uncontrolled release of radioactive water. There were however several instances of work area flooding from internal water sources as described below:
In 2002 a pipe burst and flooded the N-Ray set-up room and garage. This was a clean area and it involved normal water cleanup and disposal methods. No radioactive material was involved (Reference 9.13).
There was a sewer backup that got into the trench system but there was never any overflow to the floors. The backup was resolved when the drain line was cleaned out by the city. No radioactive material was involved (Reference 9.13).
There were pipe breaks several times in the Conference/Lunch Room area and also in the QC wing area and in the High Bay area. No radioactive material was involved (Reference 9.12).
The sink in the Chemistry Room has overflowed several times where water ran down the stairs before someone realized that the water had been left on in the sink and shut off the water. No radioactive material was involved (Reference 9.12).
A capsule of Na-24 was spilled at the south end of the facility before carpet was laid in the area.
The spill was cleaned up immediately after it occurred (Reference 9.11).
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6.2.3 Gaseous Rel eases
The prima1y source of airborne radiatio n un der n01ma l operat in g cond it ions was t h e pro d uc tion of 16N in th e re a ctor wate r tank an d n eutro n activatio n of air in th e reactor poo l t ank and air fi lled expe rimental faci liti es.
Nitroge n - 16 (16N) is a gamma emitt ing isoto p e with a 7.1 seco n d h al f-life t h at is prod u ced by fast n eutron inadia tion of oxyge n in the water in t h e reac tor wate r tank v i a the r eact i on 160 (n,p) 16N. P ersonnel ar e shi elded from th e 16N gamma by th e wate r above th e top of cor e. The primary wate r r eturn is cmved to cause swir lin g in the pool which delays 16N comin g to the pool surface.
However, some 16N is tran sp o1i ed by eithe r diffusio n o r convect i on cmTent and r eaches th e reacto r water tank surface befo r e i t decays. Once at th e top of th e poo l, 16N can exchange w it h atmosp heri c nitroge n, leave th e wate r, an d become airborne. Due to the sho1i half-li fe, 16N released to the atmosphe r e does no t trave l fa r from t he reacto r water tank before it decays.
Therefore, 16N was a radiolog ical h aza r d only o n the reactor b ri dge.
Argon -4 1 (4 1Ar) was produced by n eutro n activatio n of the ar gon in air dissolved in th e r eac tor water tank water or in t h e air in exp erime nts such as g l o1y h ole or ve1i ical tubes. ARRR operat ing exper i ence was th at radiatio n expos ure from activation of ar gon disso lved in th e reacto r water does not pose a signi fi cant r isk to operating personnel.
Bui lding gaseo u s effl uents were continu ou sly mo nitor ed by samp lin g air from the area above th e reacto r water tank. The air int ake was eithe r j ust above t h e reacto r pool, which was the n 01mal positio n, o r in th e cei ling of t he reacto r room. These locat ions ensured th at i f gaseo us fiss i on products wer e re l eased th ey wou ld be de tec ted. No gaseo us fissio n prod ucts wer e detecte d.
In addit i on a bu il ding pa1ticu l ate sample r is u sed to cont inu ously withdraw an air sample from th e reactor room and collec t pa1ticulate ma teri al on a filter pape r. T h e reacto r room pruticu l ate sam p les ru*e an alyzed mo nthly an d no activ i ty in excess of was eve r n oted.
6.3 C URRE NT USA G E
Th e Aerotest R adiograp h y and Resea r ch Reactor (ARRR) ceased operatio n s o n Octo ber 15,
2010. Aerotes t employees ar e perfo1ming clean-up of th e faci lity an d ar e con du cting mainte n ance and smve i llance duties as r equired by the r eactor T echnical Speci fi catio ns. T he reacto r is being maintained in an operab l e cond ition.
6.4 ADJ ACEN T L AND USAGE
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Tabl e 6-1: ARRR Annu a l Op e r a tin g Report Summar y
Period Annual Tot a l A nnual Tot a l Pow er L eve l E ndin 2 kw hour s kw hour s Hour s Hour s (Av 2. k w)
Jun-66 38, 152 38, 152 34 1.10 34 1.10 11 2 Jun-67 57,949 96, 10 1 359.13 700.23 16 1 Jun -68 80,409 176,5 10 38 1. 32 1,08 1. 54 2 11 Jun -69 6 1,744 238,254 452.00 1,533.54 137 Jun -70 140,279 378,533 603.90 2,137.44 232 Jun -7 1 2 15, 123 593,656 1,039.28 3, 176.72 207 Jun-72 208,086 80 1,742 87 1. 33 4,048.05 239 Jun-73 196, 16 1 997,903 874.13 4,922.19 224 Jun-74 165, 159 1, 163,062 728.77 5,650.95 227 Jun -75 203,827 1,366,889 880.85 6,53 1. 80 23 1 Jun-76 20 1,868 1,568,757 848.32 7,380.12 238 Jun -77 244,329 1,813,086 1,05 1. 93 8,432.05 232 Jun -78 266,586 2,079,672 1, 140.73 9,572.78 234 Jun-79 293,3 14 2,372,986 1,247.45 10,820.23 235 Jun-80 289,969 2,662,955 1,234.7 12,054.93 235 Jun -8 1 28 1,8 11 2,944,766 1,208.2 13,263. 13 233 Jun -82 275,699 3,220,465 1, 156.1 14,4 19.23 238 Jun-83 309, 172 3,529,637 1,327.7 15,746.93 233 Jun-84 374,479 3,904, 11 6 1,497.9 17,244.83 250 Jun -85 445,42 1 4,349,537 1,792.8 19,037.63 248 Jun-86 484,242 4,833,779 1,935 20,972.63 250 Jun-87 487,4 12 5,32 1, 19 1 1,948 22,92 1. 08 250 Jun -88 549,864 5,87 1,055 2, 199 25, 120.08 250 Jun -89 653,637 6,524,692 2,6 14 27,734.08 250 Jun-90 724,95 1 7,249,643 2,905 30,639.08 250 Jun-9 1 690, 150 7,939,793 2,763 33,402.08 250 Jun-92 676, 144 8,6 15,937 2,707 36, 109.08 250 Jun-93 37 1, 146 8,987,083 2,038 38, 147.08 182 Jun-94 344,002 9,33 1,085 1,9 12 40,059.08 180 Jun-95 350,692 9,68 1,777 1,948 42,007.08 180 Jun -96 352,727 10,034,504 1,960 43,967.08 180 Jun-97 340,389 10,374,893 1,892 45,859.08 180 Jun-98 447,745 10,822,638 2,487 48,346.08 180 Jun-99 369, 16 1 11, 19 1,799 2,049 50,395.08 180 Jun- 00 275,79 1 11,467,590 1,886 52,28 1.08 146 Jun -0 1 240,255 11,707,845 1,73 1 54,0 12.08 139 Jun -02 2 11,950 11,9 19,795 1, 178 55, 190.08 180 Jun -03 222,892 12, 142,687 1,490 56,680.08 150 Jun- 04 3 15,652 12,458,339 2, 104 58,784.08 150 Jun-05 284,958 12,743,297 1,904 60,688.08 150
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Period A nnual To ta l Annual Total Po wer Le ve l E ndine kw hour s kw hour s Hour s Hou rs (Av e. k w)
Jun -06 2 16,433 12,959,730 1,5 14 62,202.08 143 Jun-07 252,588 13,2 12,3 18 1,834 64,036.08 138 Jun -08 326,056 13,538,374 2,256 66,292.08 145 Jun -09 279, 18 1 13,8 17,555 1,662 67,954.08 168 Jun - 10 290,3 19 14, 107,874 1,628 69,582.08 178
Tabl e 6-2 : ARRR F a cility Hi s to ry and M odific a tion Summar y
R e po r t e d Dat es E ve nt
Constrnction Pemrit No. CPRR-86 issued by the Atomic Energy Commission to Aerojet-General Nucleonics for the constrnction of a 250 kW pool-type re actor at 4/16/1965 the Aerojet-General Nucleonics plant near California.
Facility License number R-98 is issued for the Aerojet General Nuclear hldustrial 7/2/1965 Re actor (AGNIR) 7/9/1965 AGNIR achieves initial criticality.
Nov-65 Ruotured fuel element removed from core.
1965 Fa il ed fuel el ement removed from site hlstalled a 6-inch diameter chy be am tube fo r use in lo w-power fissiochemist:Iy 6/1965 to 7/1966 experiments.
The graphite-filled reflector elements were taken from the thennal column and 6/1965 to 7/1966 repl aced in the reactor core.
Authotized the loading of 15 inch ac tive foel elements into the core in addition to 8/1/1966 the 14 inch el ements then in use.
Pneumatic Transfer Facility (Rabbit System) used fo r activa tion analys is of silve r 6/1967 to 7/1968 iodi de in snow samples.
8/15/1968 hlstall ation of Neutron Radiography Facility for class C expl osives was authorized.
1969 Ho t Cell removed from site The main Aerojet Nuclear Div ision Plant shuts down, necessita ting AGNIR to 4/20/1970 operate as a separate entity.
Additi on of a second neutron rad i ography facility. Changes the limitati ons of explosive devices that may be radiographed. Deletes in -core inadi ation of 6/24/197 1 explosives.
A larger cooling tower was added to allow con tinuous reactor operation if required.
6/1972 to 7/1973 The ori ginal 100 kw tower was retained for emergency use.
A small-beam radiography facility was installed which consists of a ve1t ical 2.5-6/1972 to 7/1973 inch di ameter tube to be used in scalllling expl osive cords and detonators.
6/1973 to 7/1974 Chemistiy lab moved to es tima ted date) 6/1973 to 7/1974 Change room conve1t ed to a dark room for processing of radioe.raphic film Area devoted to office space and shops added dming the past year. These consi st of the conference room, 3 offices, 2 shop areas and a quality conti*ol inspection 6/1973 to 7/1974 area.
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R eoo r t e d D a te s Eve nt Transfened li cense from Aeroj et-General Corp. to Aerotest Operati ons, Inc. and re-10/22/1974 designates the reactor as the ARRR.
New sintered boron carbi de rods were installed to replace powdered boron carbide 6/1977 to 7 /1978 rods.
6/1978 to 7/1979 Two (2) spare fuel elements were loaded into the reactor core The security fence smrnunding the building was moved outward to pennit future 6/1979 to 7/1980 bui lding expansi on Approximately 3,700 square feet of storage and neutron radiography work space was added to the east and north sides of the building (Building Addition 1 and 6/1980 to 7/1981 Ta22ing Area Building) 6/1980 to 7/1981 One fuel element removed from se1v i ce due to greater than 1101mal swelling.
The top of the concrete bioshi el d was covered wi th approximately 12 inches of fi r 6/1982 to 7/1983 blocks.
Dec-83 Two (2) new fuel elements were added to the core The Storage Bui lding was added adjacent to the main reactor building providing 6/1985 to 7/1986 400 square feet of space.
6/1986 to 7/1987 One fuel element added to the core.
One fuel element was removed from se1vice due to excessive bowing and a new 6/1988 to 7/1989 stainless clad element added that was 12 wt% uranium.
6/1988 to 7/1989 The large, 1 megawatt cooling tower was repl aced with a smaller cooling tower.
Seventeen (17) graphite reflector elements, obtained from U. C. Berkeley were 10/9/1989 added to the core of the reactor.
One graphite element was removed from se1vice and a new stainless clad element 6/1990 to 7/1991 added that was 12 wt% uranium.
6/1990 to 7/1991 One six inch expe1iment tube was added to the reactor pool for inadi ati ons.
Sep-91 One 2raphite element was replaced with a new stainless clad element.
On May 5th and May 11th two old stainless clad fuel elements were replaced with Mav-91 two new stainl ess fuel el ements.
Feb-92 A new 13 cubic foot de1nineralizer was installed in the demineralizer system.
The 1101mal reactor power was reduced to 180 kw to compensate for the faster film Sep-92 being used.
Concrete shielding was installed between the de1nineralizer shed and the fence on Feb-94 the east side of the facility to lower dose rates at the boundary of the exclusion area.
The fence on the west si de of the facility was moved back 10 feet in order to lower Mar-94 the dose rate at the boundaiy of the exclusion area.
1995 Thilt een cubic foot demineralizer bed removed from se1vice (estimated date)
Dec-95 Changed out the deinineralizer cart1idge due to high pool water conductivity.
Updated Safety Analy sis Repo1t subinitted to NRC as pa1t of facilities rel icensing Feb 2005 aoolication package.
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7.0 FINDINGS
The following sections document the results of the preliminary investigation and site reconnaissance.
7.1 CURRENT STATUS OF THE FACILITY
Descriptions and the current conditions of each building/facility as viewed during the site reconnaissance are discussed below.
7.1.1 Reactor Building
The Reactor Building is in good condition with all systems maintained in operable condition.
The building is cluttered with an abundance of non-contaminated used and unused fittings, parts and materials on the mezzanine that are not essent ial to reactor operation and could be removed at any time if there are no plans to resume operation of the facility.
There is an activated neutron gauge beam tube stored on the mezzanine along with an old glory hole tube (Reference 9.13). Also on the mezzanine is an irradiated neutron shutter that was at one time stored in one of the floor fuel storag e pits for decay (Reference 9.10). This item is no longer needs to be shielded but it has an elevated dose rate from its interior and it contains company sensitive components.
The pool tools, some of which may be activated, are located in storage cabinets on the mezzanine wall next to the reactor bioshield. This area is accessed by walking on the fir timbers over the bioshield walls.
There are asbestos floor tiles in the mezzanine area, in the M achine Shop, in the Radioactive Material Storage Area, and under the sink in the Conference/Lunch Room.
The Radioactive Material Storage Area has numerous items of waste that are not essential to reactor operation and could be removed if at any time.
There are also many paper records in this area. Client contracts require storage of records for 10 years after which they that could be sent off for disposal. Reactor Operat ing records and current client records could be sent to another location for storage.
7.1.2 Building Addition 1
The Building Addition 1 is in good condition with all systems maintained in operable condition.
This building includes space for storage of supplies for many different activities. Most of these supplies are necessary for performing N-Ray activities but are not essential to reactor operations and could be removed at any time if there are no plans to resume operation of the facility.
There are also many paper records in this area that could be sent off to storage or disposed of if there are no plans to resume operation of the facility.
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7.1.3 Tagging Area Building
The Tagging Area Building is in good condition with all systems maintained in operable condition. This building includes space for storage of supplies for tagging activities. Most of these supplies are necessary for performing taggi ng activities but are not essential to reactor operations and could be removed at any time if there are no plans to resume operation of the facility.
7.1.4 Demineralizer Building
The Demineralizer Building is in good condition and the demineralizer system must remain operable as long as the operating license is maintained at this facility.
7.1.5 Heat Exchanger Building
The Demineralizer Building is in good condition and the heat exchange system must remain operable as long as the operating license is maintained at this facility.
7.1.6 Maintenance Office Building
The Maintenance Office Building is in fair condition. The 13 cubic foot demineralizer that was only used for a brief period of time is located in a plywood addition on the south side of the shed.
This demineralizer is not essential to reactor operations and could be sent off for disposal at any time.
7.1.7 Compressor Building
The Compressor Building is in good condition and the compressors and vacuum pumps are necessary for performing N-Ray activities but are not essential to reactor operations and could be removed at any time if there are no plan s to resume operation of the facility.
7.1.8 Chemical Shed
The Chemical Shed is in good condition but many of the chemicals are necessary for performing N-Ray activities but are not essential to reactor operations and could be removed at any time if there are no plans to resume operation of the facility.
7.1.9 Storage Building
The Storage Building is in good condition. This building includes space for storage of supplies for many different activities. Most of these supplies are necessary for performing N-Ray activities but are not essential to reactor operation s and could be removed at any time if there are no plans to resume operation of the facility.
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7.2 POTENTIAL CONTAMINANTS OF CONCERN
Potential contaminants of concern (COC) are summarized and discussed below.
Uranium - The source of uranium would be from leaking fuel. There was only one instance of a leaking fuel element reported during the operation of the ARRR. The leaking ruptured fuel element was located and removed from the core in November of 1965 and immediately shipped offsite for disposal. The potential for this COC to be widespread at the site is low.
Cobalt This radionuclide is a typical activation product in nuclear reactors, especially with the use of stainless steel in structural components.
Asbestos - There has not been an asbestos survey performed at this site. There are no suspicious exterior materials on site and minimal pipe insulation. There are asbestos floor tiles in some areas of the facility.
Lead - Because of the age of the facility lead paint may have been used but most of the original facility was unpainted. The paint on the bioshield concrete is a potentially candidate for lead paint. Lead bricks were identified during a walkdown of the Reactor Building.
Mercury - Mercury is normally used in a large number of electrical switches, which would classify these switches as hazardous waste. Because the switches are sealed, switches in a radiological controlled area can be free released and not managed as mixed waste.
Polychlorinated Biphenyls (PCB) - Inspections noted some potentially PCB-containing materials. Due to the age, fluorescent li ght ballasts probably contain PCBs and should be treated as PCB waste.
Chemicals - The KODAK Industrex developer and fixer are used in film processing. The unused inventory of these chemicals will be removed prior to the start of decommissioning. There is a contractor who removes the used film processing chemicals.
Explosives - Explosive devices were examined here but all such items are valuable and will have been returned to their owner prior to decommissioning.
Freon HVAC systems were also noted during a site walkdown.
7.3 POTENTIAL WASTE STREAMS/RISK ITEMS
The following waste streams/risk items:
Radioactive waste, Lead paint, Vacuum pump and compressor oil,
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Asbestos flooring, Asbestos covered piping, Fluorescent and mercury vapor lights, and Fluorescent light ballasts.
7.4 POTENTIAL CONTAMINATED AREAS
The following sections describe the areas that have been impacted and those areas that have not been impacted by site operations. Determination of the status of each area was based on both the preliminary investigation and site reconnaissance using MARSSIM guidance.
7.4.1 Impacted Areas
Currently, no criteria for release (from radiological controls) for unrestricted use has been defined for decommissioning the ARRR site. Recent historical surveys do not indicate any contaminated areas. The areas of the ARRR site were conservatively classified based on MARSSIM guidance. Descriptions of each classification are provided below.
Preliminary Class 1 (1p) - A Class 1 ar ea has or has had contamination levels approaching or exceeding the criteria for release for unrestricted use.
Preliminary Class 2 (2p) - A Class 2 area does not and has not had contamination levels approaching the criteria for release for unrestricted use.
Preliminary Class 3 (3p) - A Class 3 surv ey does not and has not had contamination levels exceeding a small fraction (e.g., 10%) of the criteria for release for unrestricted use.
Table 7-1 provides the preliminary classifications as result of completing the HSA. It is likely that many areas, as a result of characterization survey results may be down-classified (e.g., from Class 2 to Class 3). Conversely, the classificat ion may be increased (e.g., from Class 2 to Class 1) based on survey results.
7.4.2 Non-Impacted Areas
Areas that were considered non-impacted included the roofs of all Buildings and the parking area outside the fence.
7.5 POTENTIALLY CONTAMINATED MEDIA
Potentially contaminated media includes the used demineralizer resin stored in the Radioactive Material Storage Area, some other waste items fr om the same area, the used demineralizer resin being decayed in the Demineralizer Building, any silt on the bottom of the reactor pool.
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7.6 RELATED ENVIRONMENTAL CONCERNS
The Freon systems are still charged. If the HVAC systems are to be removed as part of decommissioning, then the Freon will need to be captured for proper disposal.
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Tabl e 7-1: Pr e limin a r y C la ssifi c ati o n s Ba sed o n MAR SS I M G uidan c e
Buildin g / Stru ctur e / Sit e Area Secti on P re limin a r y C lass
Reacto r Building Conference/Lunch Room 2p Control Room 2p Men's Room 3o Ladies ' Room 3p Busi n ess Office 3p Accounting Office 3p General Manager ' s Office 3p Office Suoolv Room 3o Mac hine Shop 2p Rad Material Storage Room 2p N-Ray Area 2p Insi de Biosh ield l p Emolovee ' s Lockers 2o N -Rav Gauge Office 3p Preparation Lab 2p Chemistiy Lab 2p Instmment Calibrat ion Ar ea 2p Electi*onics Lab 2o Sheet Metal Fabrication Area 2p Mezzanine Storage Area 2p Buil ding Addit ion 1 Office Space 3p Customer V i ewing Area 3p Oualitv Contro l Room 3o Dark Room 3p Explosive Storage Safe 3p Film Storage Room 3p Shipping & Receiving 3p N-Rav Setuo Area 3o Count ing Room 2p Tagging Building Ently Vest ibule 3p Tagging Area 3p Tagging Area Back Room 3p Safe 2o Storage Building Inside 3p Demineralizer Bui lding Inside l p Hea t Exchanger Building Inside l p Compres sor Bui lding Inside 3p Main tenance Office Insi de l o Chemical Storage Shed Inside 3p Main Cooling Tower Insi de & Outside 3p Backup Cooling Towe r Insi de & Outside 3p All build ings Drains 3p
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Buildin g / Stru ctur e / Sit e Area Secti on P re limin a r y C lass Building Exteriors (Excluding Roof) Reactor Building 3p Buil ding Addition 1 3o Tagging Building 3p Storage Building 3p Demineralizer Bui lding 3o Heat Exchanger Building 3p Compressor Building 3p Maintenance Office 3p Chemical Storage Shed 3p Roofs NOT IM PACTED N/S Front PaJlcing Area --3p No1th Parking Area (insi de fence) -- 3p Waste Storage Tanks --l p Waste Sump --l p Soils Inside Fence --3o Paved Areas Around Buildings -- 3p
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8.0 CONCLUSION
S
The HSA identified current potential sources of radiological and chemical contamination as well as potentially hazardous conditions adverse to worker safety.
Radioactive Stored activated components and items in reactor tank, in cabinets along mezzanine wall, in the Radioactive Ma terial Storage Room, and in the mezzanine storage area Co-60 as the pr imary radionuclide of concern with potential for nickel-59 and nickel-63 Potential low levels of building surface contamination with fission and activation products and fuel radionuclides Radioactive sources used for instrument calibration and response checks, startup source Radioactive Waste in Radioactive Material Storage Room There is ion exchange resin contaminated with fission and activation products in the pool water demineralizer and in the spare bed within the Demineralizer Building and also in a larger demineralizer bed located alongside the Maintenance Office and in drums located in the Radioactive Material Storage Room.
Chemical/Hazardous Asbestos floor tiles Lead bricks Suspected PCB-containing or potentially PCB-containing materials including fluorescent light ballasts, electrical units, and capacitors Mercury is contained in sealed switches and vapor lights Freon in HVAC systems Worker safety concerns which include trip and low-hanging overhead hazards, and ledges without fall protection
Contaminant migration is unlikely. The stored radioactive waste is all containerized. All historical radiological surveys indicated very low beta-gamma removable surface activity levels.
All areas of the ARRR site were considered impacted except for the roofs of all Buildings. The impacted areas were preliminarily classified using MARSSIM guidance to facilitate future scoping and characterization surveys.
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9.0 REFERENCES
9.1 U.S. NUCLEAR REGULATORY COMMISSION (NRC), NUREG-1575, REV. 1, MULTI-AGENCY RADIATION SURVEY AND SITE INVESTIGATION MANUAL (MARSSIM), AUGUST 2000.
9.2 U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1757, VOL. 2, REV. 1, CONSOLIDATED NMSS DECOMMISSIONING GUIDANCE, CHARACTERIZATION, SURVEY, AND DETERMINATION OF RADIOLOGICAL CRITERIA, FINAL REPORT, SEPTEMBER 2002.
9.3 AEROJET-GENERAL, DRAWING CF-64-33-02 SHEET 1 OF 11, NUCLEAR TEST LABORATORY CIVIL SITE UTILITIES & PAVING PLAN, 1964.
9.4 STATE OF CALIFORNIA, DEPARTMENT OF FINANCE, E-5 POPULATION AND HOUSING ESTIMATES FOR CITIES, COUNTIES AND THE STATE, 2001-2008, WITH 2000 BENCHMARK.
SACRAMENTO, CALIFORNIA.
9.5 USGS INFORMATION SERVICES, BOX 25286, DENVER FEDERAL CENTER, DENVER, COLORADO 80255-0046, PRELIMINARY GEOLOGIC MAP EMPHASIZING BEDROCK FORMATIONS IN CONTRA COSTA COUNTY, CALIFORNIA: A DIGITAL DATABASE, 1994.
9.6, GENERAL PLAN 2030, DRAFT EIR, APRIL 5, 2010.
9.7 UNITED STATES DEPARTMENT OF AGRICULTURE, NATIONAL COOPERATIVE SOIL SURVEY, WEB SOIL SURVEY DATA FOR THE STATE OF CALIFORNIA, CONTRA COSTA COUNTY WITH AREA OF INTEREST AROUND CALIFORNIA.
9.8 CONTRA COSTA COUNTY FLOOD CONTROL & WATER CONSERVATION DISTRICT-, MEAN SEASONAL PRECIPITATION RASTER FROM DRAWING B-166, DECEMBER 1, 2009.
9.9 AEROJET-GENERAL NUCLEONICS, AN-1405, AEROJET-GENERAL NUCLEONICS INDUSTRIAL REACTOR (AGNIR) TECHNICAL SPECIFICATIONS, APRIL 1965.
9.10 CONVERSATIONS WITH RICHARD L. NEWACHECK, FORMER PRESIDENT AND MANAGER OF AEROTEST OPERATIONS, MARCH 17, 2011.
9.11 CONVERSATIONS WITH RAY R. TSUKIMURA, FORMER PRESIDENT AND MANAGER OF AEROTEST OPERATIONS, MARCH 17, 2011.
9.12 CONVERSATIONS WITH SANDRA L. WARREN, GENERAL MANAGER OF AEROTEST OPERATIONS, MARCH 17, 2011.
9.13 CONVERSATIONS WITH CHRISTOPHER E. BAUMAN, NUCLEAR ENGINEER; ALFREDO W.
MEREN, MANAGER OF REACTOR OPERATIONS; MITCH A. WILKINSON, MANAGER OF QUALITY ASSURANCE; AND TONI R. RICHEY, MANAGER OF NEUTRON RADIOGRAPHY, MARCH 17, 2011.
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9.14 AEROJET-GENERAL NUCLEONICS, AN-1193, AEROJET-GENERAL NUCLEONICS INDUSTRIAL REACTOR HAZARDS
SUMMARY
REPORT, SEPTEMBER 1964, R. L. NEWACHECK, PROJECT ENGINEER.
9.15 AEROJET-GENERAL, DRAWING (NUMBER NOT READABLE), NUCLEAR TEST LAB STRUCTURAL FOUNDATION PLAN & DETAILS, 1964.
9.16 AEROTEST OPERATIONS, INC, AEROTEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR)
UPDATED SAFETY ANALYSIS REPORT (USAR) PROPOSED REVISION 0, 2005.
9.17 AEROTEST OPERATIONS, INC, ANNUAL
SUMMARY
OF CHANGES, TESTS AND EXPERIMENTS PERFORMED AT THE AEROTEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR), NRC DOCKET NO. 50-228, REPORTED ANNUALLY
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